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


1

Nuclear Waste: Knowledge Waste?  

Science Journals Connector (OSTI)

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

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

2010-08-13T23:59:59.000Z

2

Nuclear Waste  

Science Journals Connector (OSTI)

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

Rob P. Rechard

2014-01-01T23:59:59.000Z

3

Solid Waste Management Act (West Virginia) | Department of Energy  

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

Act (West Virginia) Act (West Virginia) Solid Waste Management Act (West Virginia) < Back Eligibility Utility Fed. Government Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Tribal Government Low-Income Residential Schools Retail Supplier Institutional Multi-Family Residential Systems Integrator Fuel Distributor Nonprofit General Public/Consumer Transportation Program Info State West Virginia Program Type Siting and Permitting Provider Department of Environmental Protection In addition to establishing a comprehensive program of controlling all phases of solid waste management and assigning responsibilities for solid waste management to the Secretary of Department of Environmental

4

Solid Waste Assessment Fee Exemptions (West Virginia) | Department of  

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

Solid Waste Assessment Fee Exemptions (West Virginia) Solid Waste Assessment Fee Exemptions (West Virginia) Solid Waste Assessment Fee Exemptions (West Virginia) < Back Eligibility Utility Fed. Government Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Tribal Government Low-Income Residential Schools Retail Supplier Institutional Multi-Family Residential Systems Integrator Fuel Distributor Nonprofit General Public/Consumer Transportation Program Info State West Virginia Program Type Rebate Program A person who owns, operates, or leases an approved solid waste disposal facility is exempt from the payment of solid waste assessment fees, upon the receipt of a Certificate of Exemption from the director, if that

5

Virginia Nuclear Profile - Power Plants  

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

nuclear power plants, summer capacity and net generation, 2010" "Plant nametotal reactors","Summer capacity (mw)","Net generation (thousand mwh)","Share of State nuclear net...

6

Solid Waste Management Rule (West Virginia) | Department of Energy  

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

Rule (West Virginia) Rule (West Virginia) Solid Waste Management Rule (West Virginia) < Back Eligibility Utility Fed. Government Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Tribal Government Low-Income Residential Schools Retail Supplier Institutional Multi-Family Residential Systems Integrator Fuel Distributor Nonprofit General Public/Consumer Transportation Program Info State West Virginia Program Type Siting and Permitting This rule establishes requirements for the siting, financial assurance, installation, establishment, construction, design, groundwater monitoring, modification, operation, permitting, closure and post-closure care of any

7

Virginia Nuclear Profile - All Fuels  

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

total (percent)","Net generation (thousand mwh)","Share of State total (percent)" "Nuclear","3,501",14.5,"26,572",36.4 "Coal","5,868",24.3,"25,459",34.9 "Hydro and Pumped...

8

Nuclear Waste: Knowledge Waste?  

Science Journals Connector (OSTI)

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

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

2010-08-13T23:59:59.000Z

9

Chapter 19 - Nuclear Waste Fund  

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

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

10

High level nuclear waste  

SciTech Connect (OSTI)

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

Crandall, J L

1980-01-01T23:59:59.000Z

11

Nuclear waste solutions  

DOE Patents [OSTI]

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

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

1987-01-01T23:59:59.000Z

12

6 - Nuclear Waste Regulations  

Science Journals Connector (OSTI)

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

M.I. Ojovan; W.E. Lee

2014-01-01T23:59:59.000Z

13

The Discovery of Nuclear Waste  

Science Journals Connector (OSTI)

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

Göran Sundqvist

2002-01-01T23:59:59.000Z

14

Nuclear Waste Disposal Plan Drafted  

Science Journals Connector (OSTI)

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

1984-01-09T23:59:59.000Z

15

Pioneering Nuclear Waste Disposal  

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

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

16

Rhenium solubility in borosilicate nuclear waste glass  

E-Print Network [OSTI]

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

McCloy, John S.

2014-01-01T23:59:59.000Z

17

Nuclear Waste Disposal: Amounts of Waste  

Science Journals Connector (OSTI)

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

2005-01-01T23:59:59.000Z

18

WORLDWIDE FOCUS ON NUCLEAR WASTE  

Science Journals Connector (OSTI)

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

JEFF JOHNSON

2001-06-18T23:59:59.000Z

19

A Perspective on Nuclear Waste  

Science Journals Connector (OSTI)

The management of spent nuclear fuel and high-level nuclear waste has the deserved reputation as one of ... facing the United States and other nations using nuclear reactors for electric power generation. This pa...

D. Warner North

1999-08-01T23:59:59.000Z

20

Pioneering Nuclear Waste Disposal  

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

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

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


21

Managing America's Defense Nuclear Waste | Department of Energy  

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

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

22

Solving the Nuclear Waste Problem  

Science Journals Connector (OSTI)

Solving the Nuclear Waste Problem ... Of the many problems that beset the nuclear power industry, none has proved as perplexing as taking out the trash. ... Nuclear waste will remain a potential threat to man and the environment for as long as 10,000 years. ...

1988-09-12T23:59:59.000Z

23

Leaching of Nuclear Waste Glasses  

Science Journals Connector (OSTI)

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

L. L. Hench

1985-01-01T23:59:59.000Z

24

Funds denied for nuclear waste  

Science Journals Connector (OSTI)

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

David Dickson

1979-05-24T23:59:59.000Z

25

Nuclear Waste Policy Act | Department of Energy  

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

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

26

Hydration Aging of Nuclear Waste Glass  

Science Journals Connector (OSTI)

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

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

1982-10-01T23:59:59.000Z

27

Nuclear waste storage bill passes Congress  

Science Journals Connector (OSTI)

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

1983-01-03T23:59:59.000Z

28

Nuclear Waste Management using Electrometallurgical Technology - Nuclear  

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

Technology Technology Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Bookmark and Share The NE system engineering activities involve the conceptual design, through the manufacturing and qualification testing of the Mk-IV and Mk-V electrorefiner and the cathode processor. These first-of-a-kind large scale

29

Nuclear waste solids  

Science Journals Connector (OSTI)

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

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

1986-05-01T23:59:59.000Z

30

Pioneering Nuclear Waste Disposal  

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

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

31

Virginia Resources Authority Act (Virginia)  

Broader source: Energy.gov [DOE]

The Virginia Resources Authority provides financing options to support community investment in a number of areas, including wastewater, flood prevention and dam safety, solid waste, water, land...

32

Nuclear wastes: Small disposals  

Science Journals Connector (OSTI)

... Much to the relief of many east coast hospitals, universities and medical schools, the Nuclear Regulatory Commission (NRC) is proposing that liquid scintillation media used for detecting low levels ... for detecting low levels of radioactivity in biological samples need no longer be buried in nuclear ...

David Dickson

1980-10-16T23:59:59.000Z

33

Policy Issues in Nuclear Waste Disposal  

Science Journals Connector (OSTI)

The Congressional Research Service, in an issue brief on nuclear waste disposal, compactly described a common assessment when it noted that “nuclear waste has sometimes been called the Achilles’ heel of the nu...

2005-01-01T23:59:59.000Z

34

Nuclear waste, secrecy and the mass media  

Science Journals Connector (OSTI)

Invited media scholars and journalists examine the general issue of nuclear waste, risk and the sicentific promises that were ... . The mass media uncovered and reported on nuclear waste problems at Rocky Flats i...

Len Ackland; Karen Dorn Steele; JoAnn M. Valenti PhD

1998-01-01T23:59:59.000Z

35

GNEP Element:Minimize Nuclear Waste | Department of Energy  

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

Minimize Nuclear Waste GNEP Element:Minimize Nuclear Waste An article describing the ways in which the GNEP plans to minimize nuclear waste. GNEP Element:Minimize Nuclear Waste...

36

Disposal of Nuclear Wastes  

Science Journals Connector (OSTI)

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

Arthur S. Kubo; David J. Rose

1973-12-21T23:59:59.000Z

37

Nuclear Waste and Agenda 21  

Science Journals Connector (OSTI)

Nuclear power and its attendant waste are similar to the Ring in J....The Lord of the Rings. The Ring gave mastery over every living creature, but it was created by an evil power. As a result, it inevitably corru...

Kristin Shrader-Frechette

1995-01-01T23:59:59.000Z

38

Long-term nuclear waste storage urged  

Science Journals Connector (OSTI)

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

1984-08-27T23:59:59.000Z

39

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 Arlington Dear Speaker Pelosi, Senator Byrd, and Secretary Bodman: The Nuclear Waste Technical Review Board, and transporting high-level radioactive waste and spent nuclear fuel. The Board is required to report its findings

40

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

con202vf UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300, the Nuclear Waste Technical Review Board (Board) submits its second report of 2003 in accordance with provisions of the Nuclear Waste Policy Amendments Act of 1987, Public Law 100-203. The Act requires the Board

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


41

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD 2300 Clarendon Boulevard, Suite 1300 Arlington are pleased to transmit a technical report prepared by the Nuclear Waste Technical Review Board (Board. Based on its review of data gathered by the DOE and the Center for Nuclear Waste Regulatory Analyses

42

United States Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

United States Nuclear Waste Technical Review Board Experience Gained From Programs to Manage High-Level Radioactive Waste and Spent Nuclear Fuel in the United States and Other Countries A Report to Congress and the Secretary of Energy April 2011 #12;#12;U.S. Nuclear Waste Technical Review Board Experience Gained From

43

Nuclear Waste Policy Act Signed | National Nuclear Security Administra...  

National Nuclear Security Administration (NNSA)

Waste Policy Act Signed | National Nuclear Security Administration People Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

44

Campus Energy, Water, and Waste Reduction Policy Page 1 of 7 Virginia Polytechnic Institute and State University No. 5505 Rev.: 2  

E-Print Network [OSTI]

Campus Energy, Water, and Waste Reduction Policy Page 1 of 7 Virginia Polytechnic Institute __________________________________________________________________________________ Subject: Campus Energy, Water, and Waste Reduction Policy the highest standards in energy/water usage and waste reduction with consideration of the impact

Virginia Tech

45

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

SciTech Connect (OSTI)

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

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

1984-06-01T23:59:59.000Z

46

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...

47

Nuclear waste bill dead for this year  

Science Journals Connector (OSTI)

Nuclear waste bill dead for this year ... "Politics pure and simple" killed compromise legislation to create an interim storage facility in Nevada for commercial high-level nuclear waste, say bill proponents in Congress and in the nuclear power industry. ... Last year, bills passed both the House and Senate that would have required the government to, among other things, temporarily store nuclear waste until a permanent facility could be built. ...

JEFF JOHNSON

1998-06-08T23:59:59.000Z

48

AIChE issues nuclear waste conclusions  

Science Journals Connector (OSTI)

AIChE issues nuclear waste conclusions ... Long and extensive research, development, and demonstration activities in the U.S. and abroad have made possible the safe, permanent disposal of high-level commercial nuclear waste. ... Titled "The U.S. High-Level Nuclear Waste Management Program," it was prepared by an AIChE nuclear engineering division task force for the institute's government programs steering committee. ...

1986-02-10T23:59:59.000Z

49

Talk, No Action On Nuclear Waste Plan  

Science Journals Connector (OSTI)

Talk, No Action On Nuclear Waste Plan ... “Nowhere” was how an exasperated Lt. Gen. Brent Scowcroft, chairman of the Blue Ribbon Commission on America’s Nuclear Future, described the status of the U.S.’s search for a place to store spent commercial nuclear fuel and other radioactive waste. ... Although the blue-ribbon commission had completed its seminal report on nuclear waste in January, Scowcroft noted that action on its recommendations was “nowhere.” ...

JEFF JOHNSON

2012-09-30T23:59:59.000Z

50

Process removes Sr from nuclear wastes  

Science Journals Connector (OSTI)

Process removes Sr from nuclear wastes ... Scientists at Argonne National Laboratory have devised a chemical process for extracting and recovering strontium-90 from liquid nuclear wastes. ... Argonne chemist E. Philip Horwitz, head of the team, says it could be a significant aid in managing such radioactive wastes. ...

WARD WORTHY

1990-09-10T23:59:59.000Z

51

Bubblers Speed Nuclear Waste Processing at SRS  

ScienceCinema (OSTI)

At the Department of Energy's Savannah River Site, American Recovery and Reinvestment Act funding has supported installation of bubbler technology and related enhancements in the Defense Waste Processing Facility (DWPF). The improvements will accelerate the processing of radioactive waste into a safe, stable form for storage and permit expedited closure of underground waste tanks holding 37 million gallons of liquid nuclear waste.

None

2014-08-06T23:59:59.000Z

52

Bubblers Speed Nuclear Waste Processing at SRS  

SciTech Connect (OSTI)

At the Department of Energy's Savannah River Site, American Recovery and Reinvestment Act funding has supported installation of bubbler technology and related enhancements in the Defense Waste Processing Facility (DWPF). The improvements will accelerate the processing of radioactive waste into a safe, stable form for storage and permit expedited closure of underground waste tanks holding 37 million gallons of liquid nuclear waste.

None

2010-11-14T23:59:59.000Z

53

Metal Encapsulation of Ceramic Nuclear Waste  

Science Journals Connector (OSTI)

A conceptual flow sheet is presented for encapsulating a ceramic waste form in solid lead, using existing or ... encapsulation might be applied to other solid radioactive wastes from the nuclear fuel cycle. It is...

L. J. Jardine; M. J. Steindler

1979-01-01T23:59:59.000Z

54

Public risk perception of nuclear waste  

Science Journals Connector (OSTI)

Nuclear waste has emerged as a very salient issue in the nuclear power debate. In the present study, a broad range of risk perception and attitude dimensions concerned with nuclear waste was investigated. It was found that most respondents from the general public were not willing to accept a local high-level nuclear waste repository in their home region. Nuclear waste was seen, by the public, as a very important issue. Regression analysis of perceived nuclear waste risk yielded a high level of explained variance (about 65%). Fear of radiation appeared to be an important determinant of the perceived risk and so was attitude to nuclear power, risk sensitivity and a pooled measure of the traditional psychometric dimensions of risk perception. A structural equations model of acceptance of a local repository was quite successful in explaining acceptance.

Lennart Sjoberg; Britt-Marie Drottz-Sjoberg

2009-01-01T23:59:59.000Z

55

U.S. Nuclear Waste Technical Review Board Performance Evaluation  

E-Print Network [OSTI]

Addendum A Addendum A U.S. Nuclear Waste Technical Review Board Performance Evaluation Fiscal Year 2005 The U.S. Nuclear Waste Technical Review Board The Nuclear Waste Policy Amendments Act nuclear fuel and defense high-level radioactive waste. The Act also estab lished the U.S. Nuclear Waste

56

Chemistry related to isolation of high-level nuclear waste  

Science Journals Connector (OSTI)

Chemistry related to isolation of high-level nuclear waste ... This article discusses the isolation of high-level nuclear waste. ... Radioactivity, Radiation, and the Chemistry of Nuclear Waste ...

Darleane C. Hoffman; Gregory R. Choppin

1986-01-01T23:59:59.000Z

57

Nuclear Waste Storage in Gel-Derived Materials  

Science Journals Connector (OSTI)

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

T. Woignier; J. Reynes; J. Phalippou…

2000-12-01T23:59:59.000Z

58

Basic Research for Evaluating Nuclear Waste Form Performance  

Science Journals Connector (OSTI)

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste

Don J. Bradley

59

Rock Alteration and Mineral Transformations for Nuclear Waste Management  

Science Journals Connector (OSTI)

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management / Radioactive Waste

Philip A. Helmke

60

Nuclear Waste Repository Plan Approved by Senate  

Science Journals Connector (OSTI)

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

JANICE LONG

1987-12-07T23:59:59.000Z

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


61

CARTER MAPS PLAN TO MANAGE NUCLEAR WASTE  

Science Journals Connector (OSTI)

CARTER MAPS PLAN TO MANAGE NUCLEAR WASTE ... The first part of the 15-year program will concentrate on locating and characterizing a number of potential repository sites, capable of isolating from the biosphere both defense and commercial high-level nuclear wastes. ...

1980-02-18T23:59:59.000Z

62

Court blocks testing of nuclear waste site  

Science Journals Connector (OSTI)

Court blocks testing of nuclear waste site ... WIPP was authorized by Congress in 1979 to provide an R&D facility to demonstrate safe handling, transport, and disposal of "mixed" transuranic wastes (contaminated with radioactive plutonium-239 and hazardous chemicals), which are now stored temporarily at DOE nuclear-weapons-making facilities. ...

RICHARD SELTZER

1992-02-10T23:59:59.000Z

63

Nuclear Waste and the Distant Future Nuclear Waste and the Distant Future  

E-Print Network [OSTI]

Nuclear Waste and the Distant Future 1 Nuclear Waste and the Distant Future PER F. PETERSON WILLIAM://www.issues.org/22.4/peterson.html Regulation of nuclear hazards must be consistent with rules governing other of the radioactive material generated by nuclear energy decays away over short times ranging from minutes to several

Kammen, Daniel M.

64

Nuclear Waste Management. Semiannual progress report, April 1984-September 1984  

SciTech Connect (OSTI)

Progress in the following studies on radioactive waste management is reported: defense waste technology; Nuclear Waste Materials Characterization Center; and supporting studies. 33 figures, 13 tables.

McElroy, J.L.; Powell, J.A. (comps.)

1984-12-01T23:59:59.000Z

65

Nuclear Waste Management. Semiannual progress report, October 1984-March 1985  

SciTech Connect (OSTI)

Progress reports are presented for the following studies on radioactive waste management: defense waste technology; nuclear waste materials characterization center; and supporting studies. 19 figs., 29 tabs.

McElroy, J.L.; Powell, J.A. (comps.)

1985-06-01T23:59:59.000Z

66

Secretarial Determination of the Adequacy of the Nuclear Waste...  

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

Secretarial Determination of the Adequacy of the Nuclear Waste Fund Fee Secretarial Determination of the Adequacy of the Nuclear Waste Fund Fee I adopt and approve the attached...

67

Enforcement Notice of Intent to Investigate, Nuclear Waste Partnership...  

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

Nuclear Waste Partnership, LLC Enforcement Notice of Intent to Investigate, Nuclear Waste Partnership, LLC June 16, 2014 DOE Office of Enforcement issues a Notice of Intent to...

68

DOE woos scientists for nuclear waste work  

Science Journals Connector (OSTI)

DOE woos scientists for nuclear waste work ... The Department of Energy has established a $50 million-per-year program to involve for the first time the basic research community in cleaning up nuclear waste at DOE's widely scattered, heavily contaminated nuclear weapons facilities. ... Cleanup of waste at DOE's nuclear weapons facilities—at Savannah River, S.C.; Oak Ridge, Term.; Hanford, Wash.; and Paducah, Ky.; among others—is expected to take at least 50 years and cost at least $300 billion. ...

WIL LEPKOWSKI

1996-02-19T23:59:59.000Z

69

Managing Nuclear Waste: Options Considered  

SciTech Connect (OSTI)

Starting in the 1950s, U.S. scientists began to research ways to manage highly radioactive materials accumulating at power plants and other sites nationwide. Long-term surface storage of these materials poses significant potential health, safety, and environmental risks. Scientists studied a broad range of options for managing spent nuclear fuel and high-level radioactive waste. The options included leaving it where it is, disposing of it in various ways, and making it safer through advanced technologies. International scientific consensus holds that these materials should eventually be disposed of deep underground in what is called a geologic repository. In a recent special report, the National Academy of Sciences summarized the various studies and emphasized that geologic disposal is ultimately necessary.

DOE

2002-05-02T23:59:59.000Z

70

Nuclear Waste Policy Act.doc  

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

Civilian Radioactive Civilian Radioactive Waste Management Washington, D.C. 20585 March 2004 i THE NUCLEAR WASTE POLICY ACT OF 1982 1 An Act to provide for the development of repositories for the disposal of high-level radioactive waste and spent nuclear fuel, to establish a program of research, development, and demonstration regarding the disposal of high-level radioactive waste and spent nuclear fuel, and for other purposes. Be it enacted by the Senate and House of Representatives of the United States of America in Congress assembled, SHORT TITLE AND TABLE OF CONTENTS Section 1. This Act may be cited as the "Nuclear Waste Policy Act of 1982". Sec. 1. Short title and table of contents...........................................................................i

71

Plasma Mass Filters For Nuclear Waste Reprocessing  

SciTech Connect (OSTI)

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

Abraham J. Fetterman and Nathaniel J. Fisch

2011-05-26T23:59:59.000Z

72

Nuclear Energy Research Advisory Committee Meeting March 30-31, 1999, Marriott Crystal City, Arlington, Virginia  

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

March 30-31, 1999, Marriott Crystal City, Arlington, Virginia March 30-31, 1999, Marriott Crystal City, Arlington, Virginia NERAC members present: John Ahearne Robert Long Thomas Boulette Sekazi Mtingwa Thomas Cochran Richard Reba Joseph Comfort Joy Rempe Jose Luis Cortez Miguel Rios Maureen S. Crandall C. Paul Robinson (Tuesday only) Allen Croff Allen Sessoms (Wednesday only) James Duderstadt (Chair) Daniel C. Sullivan Marvin Fertel (Wednesday only) John Taylor Dale Klein Charles E. Till Linda Knight Neil Todreas NERAC members absent: Beverly Hartline Warren Miller J. Bennett Johnston Robert Socolow William Kastenberg Bruce Tarter Also present: Norton Haberman, Senior Technical Advisor, Office of Nuclear Energy, Science, and Technology (NE), DOE John Herczeg, Lead Nuclear Engineer, Office of Technology, DOE William Magwood, Director, Office of Nuclear Energy, Science, and Technology (NE), DOE

73

Removing nuclear waste, one shipment at a time  

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

Removing nuclear waste, one shipment at a time Removing nuclear waste, one shipment at a time The Lab's 1,000th shipment of transuranic waste recently left Los Alamos, on its way...

74

Whats Next for Nuclear Waste  

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

WHAT'S NEXT FOR NUCLEAR WASTE? A New Strategy for the CSRA September 2009 PREFACE This White Paper was prepared by the Savannah River Site Community Reuse Organization (SRSCRO) to...

75

US nuclear waste: Widespread problem of disposal  

Science Journals Connector (OSTI)

... individual states in the United States to develop facilities for disposal of low-level radioactive waste produced by ... produced by nuclear reactors, industry and biomdical research and treatment. The federal Low-Level ...

Christopher Earl

1984-07-19T23:59:59.000Z

76

Questioning nuclear waste substitution: a case study  

Science Journals Connector (OSTI)

This article looks at the ethical quandaries, and their social and political context, which emerge as a result of international nuclear waste substitution. In particular it addresses the dilemmas inherent within ...

Alan Marshall

2007-03-01T23:59:59.000Z

77

Lesson 7 - Waste from Nuclear Power Plants | Department of Energy  

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

7 - Waste from Nuclear Power Plants 7 - Waste from Nuclear Power Plants Lesson 7 - Waste from Nuclear Power Plants This lesson takes a look at the waste from electricity production at nuclear power plants. It considers the different types of waste generated, as well as how we deal with each type of waste. Specific topics covered include: Nuclear Waste Some radioactive Types of radioactive waste Low-level waste High-level waste Disposal and storage Low-level waste disposal Spent fuel storage Waste isolation Reprocessing Decommissioning Lesson 7 - Waste.pptx More Documents & Publications National Report Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Third National Report for the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

78

Federal nuclear waste cleanup plan proposed  

Science Journals Connector (OSTI)

Federal nuclear waste cleanup plan proposed ... The Department of Energy has asked Congress to find $19.5 billion over the next five years to finance initial cleanup of environmental contamination at its nuclear, primarily weapons, facilities. ... DOE estimates that to begin implementing the plan in 1990, it needs considerably more than the $1.3 billion originally requested for defense waste and environmental restoration activities. ...

JANICE LONG

1989-08-07T23:59:59.000Z

79

Virginia Geothermal Resources Conservation Act (Virginia) | Department of  

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

Virginia Geothermal Resources Conservation Act (Virginia) Virginia Geothermal Resources Conservation Act (Virginia) Virginia Geothermal Resources Conservation Act (Virginia) < Back Eligibility Commercial Construction Developer Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Systems Integrator Utility Savings Category Buying & Making Electricity Program Info State Virginia Program Type Safety and Operational Guidelines Provider Virginia Department of Mines, Minerals, and Energy It is the policy of the Commonwealth of Virginia to foster the development, production, and utilization of geothermal resources, prevent waste of geothermal resources, protect correlative rights to the resource, protect existing high quality state waters and safeguard potable waters from pollution, safeguard the natural environment, and promote geothermal and

80

Natural analogues of nuclear waste glass corrosion.  

SciTech Connect (OSTI)

This report reviews and summarizes studies performed to characterize the products and processes involved in the corrosion of natural glasses. Studies are also reviewed and evaluated on how well the corrosion of natural glasses in natural environments serves as an analogue for the corrosion of high-level radioactive waste glasses in an engineered geologic disposal system. A wide range of natural and experimental corrosion studies has been performed on three major groups of natural glasses: tektite, obsidian, and basalt. Studies of the corrosion of natural glass attempt to characterize both the nature of alteration products and the reaction kinetics. Information available on natural glass was then compared to corresponding information on the corrosion of nuclear waste glasses, specifically to resolve two key questions: (1) whether one or more natural glasses behave similarly to nuclear waste glasses in laboratory tests, and (2) how these similarities can be used to support projections of the long-term corrosion of nuclear waste glasses. The corrosion behavior of basaltic glasses was most similar to that of nuclear waste glasses, but the corrosion of tektite and obsidian glasses involves certain processes that also occur during the corrosion of nuclear waste glasses. The reactions and processes that control basalt glass dissolution are similar to those that are important in nuclear waste glass dissolution. The key reaction of the overall corrosion mechanism is network hydrolysis, which eventually breaks down the glass network structure that remains after the initial ion-exchange and diffusion processes. This review also highlights some unresolved issues related to the application of an analogue approach to predicting long-term behavior of nuclear waste glass corrosion, such as discrepancies between experimental and field-based estimates of kinetic parameters for basaltic glasses.

Abrajano, T.A. Jr.; Ebert, W.L.; Luo, J.S.

1999-01-06T23:59:59.000Z

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


81

Nuclear Fuel Cycle and Waste Management Technologies - Nuclear Engineering  

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

Nuclear Fuel Cycle and Nuclear Fuel Cycle and Waste Management Technologies Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Fuel Cycle and Waste Management Technologies Overview Bookmark and Share Much of the NE Division's research is directed toward developing software and performing analyses, system engineering design, and experiments to support the demonstration and optimization of the electrometallurgical

82

System Engineering Design [Nuclear Waste Management using  

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

System Engineering System Engineering Design Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology System Engineering Design Bookmark and Share Two major pieces of electrometallurgical process equipment are the Electrorefiner and the Cathode Processor. NE personnel have been involved in the conceptual design, final design, procurement, manufacture,

83

States want say in nuclear waste storage  

Science Journals Connector (OSTI)

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

1981-04-06T23:59:59.000Z

84

Vitrified municipal waste as a host form for high-level nuclear waste  

Science Journals Connector (OSTI)

Using glass as a safe and long term hosting matrix for hazardous wastes and for the immobilization of heavy metals and nuclear wastes has become an attractive method [3]. The most known glasses used as nuclear waste

N. A. El-Alaily; E. M. Abou-Hussein…

2014-01-01T23:59:59.000Z

85

Doing the impossible: Recycling nuclear waste  

ScienceCinema (OSTI)

A Science Channel feature explores how Argonne techniques could be used to safely reduce the amount of radioactive waste generated by nuclear power?the most plentiful carbon-neutral energy source. Read more at http://www.anl.gov/Media_Center/ArgonneNow/Fall_2009/nuclear.html

None

2013-04-19T23:59:59.000Z

86

Nuclear waste could bury itself  

Science Journals Connector (OSTI)

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

Tom Clarke

2003-08-13T23:59:59.000Z

87

US nuclear waste site "unsuitable"  

Science Journals Connector (OSTI)

... about the suitability of Yucca Mountain as the site for the nation's first highlevel nuclear ...

Mary Manning

1988-01-28T23:59:59.000Z

88

Pump targets hydrogen risk in nuclear waste tank  

Science Journals Connector (OSTI)

Pump targets hydrogen risk in nuclear waste tank ... Researchers believe that thermal and radiolytic breakdown of organic compounds in the tank's wastes produces the hydrogen. ...

DEBORAH ILLMAN

1993-07-12T23:59:59.000Z

89

Appendix A U.S. Nuclear Waste Technical Review  

E-Print Network [OSTI]

Appendices Appendices 37 #12;#12;Appendix A Appendix A U.S. Nuclear Waste Technical Review Board as chair, on the U.S. Nuclear Regulatory Commission's Advisory Commit tee on Nuclear Waste. His areas to the Nuclear Waste Technical Review Board on June 26, 2002, by President George W. Bush. Dr. Abkowitz

90

Appendix A U.S. Nuclear Waste Technical Review  

E-Print Network [OSTI]

Appendices Appendices 31 #12;#12;Appendix A Appendix A U.S. Nuclear Waste Technical Review Board.S. Nuclear Waste Technical Review Board as Chairman on September 10, 2004, by President George W. Bush. Dr­2004), 4 years as chair, on the U.S. Nuclear Regulatory Commission's Advisory Committee on Nuclear Waste

91

Radioactivity, Radiation, and the Chemistry of Nuclear Waste  

Science Journals Connector (OSTI)

Radioactivity, Radiation, and the Chemistry of Nuclear Waste ... A chemistry course for nonmajors, which centers on the chemistry of nuclear waste, has as a prerequisite at least two semesters of general chemistry. ... The final section of the course is devoted to the treatment of nuclear waste by vitrification and applications based on nuclear or radiation chemistry. ...

Nick Zevos

2002-06-01T23:59:59.000Z

92

Nuclear Waste Technical Review Board Members Appendix A 53  

E-Print Network [OSTI]

51 Appendix A Nuclear Waste Technical Review Board Members #12;#12;Appendix A 53 B. John Garrick, Ph.D., P.E. Chairman Dr. B. John Garrick was appointed to the U.S. Nuclear Waste Technical Review, on the U.S. Nuclear Regula- tory Commission's Advisory Committee on Nuclear Waste. His areas of expertise

93

Nuclear waste isolation activities report  

SciTech Connect (OSTI)

Included are: a report from the Deputy Assistant Secretary, a summary of recent events, new literature, a list of upcoming waste management meetings, and background information on DOE`s radwaste management programs. (DLC)

None

1980-12-01T23:59:59.000Z

94

Phosphates as Nuclear Waste Forms  

Science Journals Connector (OSTI)

...environment of the disposal site, the...the sustained funding of the Office...EP (1999) Yucca Mountain as a radioactive-waste...Ultimate disposal of radioactive...Adirondack Mountains, New York...for geologic disposal. Mater Res...

Rodney C. Ewing; LuMin Wang

95

Neutron sources and transmutation of nuclear waste  

Science Journals Connector (OSTI)

Intense neutron sources with different energy spectra are of interest for a variety of applications. In my presentation, after briefly touching on the situation of radioactive waste in Italy, I will try to give a broad picture of Italian existing or proposed neutron sources based on accelerators, ranging from thermal to fast neutrons. I will also describe a specific project for a low-power ADS, aimed at studying neutron spectra as well as at demonstrating incineration and transmutation of nuclear waste.

M. Ripani

2013-01-01T23:59:59.000Z

96

Nuclear waste management. Quarterly progress report, January-March 1980  

SciTech Connect (OSTI)

Reported are: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, criteria for defining waste isolation, and spent fuel and pool component integrity. (DLC)

Platt, A.M.; Powell, J.A. (comps.)

1980-06-01T23:59:59.000Z

97

The discourse of democracy in Canadian nuclear waste management policy  

Science Journals Connector (OSTI)

Canadian nuclear waste management policy has taken a deliberative democratic turn. What ... identify limitations in this turn by evaluating the Nuclear Waste Management Organization’s subsequent consultation proc...

Genevieve Fuji Johnson

2007-06-01T23:59:59.000Z

98

Move to test nuclear waste site draws fire  

Science Journals Connector (OSTI)

Move to test nuclear waste site draws fire ... The Department of Energy has stirred up a storm of opposition by taking administrative action, bypassing Congress, that would enable it to start testing an underground nuclear waste repository in New Mexico. ...

RICHARD SELTZER

1991-10-14T23:59:59.000Z

99

2008 DOE Spent Nuclear Fuel and High Level Waste Inventory  

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

Management >> National Spent Nuclear Fuel INL Logo Search 2008 DOE Spent Nuclear Fuel and High Level Waste Inventory Content Goes Here Skip Navigation Links Home Newsroom About INL...

100

E-Print Network 3.0 - alkaline nuclear waste Sample Search Results  

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

waste Search Powered by Explorit Topic List Advanced Search Sample search results for: alkaline nuclear waste...

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


101

E-Print Network 3.0 - acidic nuclear waste Sample Search Results  

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

waste Search Powered by Explorit Topic List Advanced Search Sample search results for: acidic nuclear waste...

102

Glossary of Nuclear Waste Terms  

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

measures 12 feet in diameter by 22 feet long and weighs 200 tons. Chain Reaction A self-sustaining series of nuclear fissions taking place in a reactor core. Neutrons produced in...

103

UK waives nuclear waste rule for Georgia  

Science Journals Connector (OSTI)

... Only hours before the government's announcement, the Nuclear Installations Inspectorate (NII), part of the UK government's Health and Safety Executive, ... material for reprocessing until a complete safety audit and an assessment of the plant's waste-management capability had been carried out. The other contract is with the Australian ...

Alison Abbott

1998-04-30T23:59:59.000Z

104

Nuclear waste plans enter critical phase  

Science Journals Connector (OSTI)

... London. Britain's newly privatized nuclear power industry is facing a critical few months as it contemplates how to dispose of ... as it contemplates how to dispose of up to 300,000 cubic metres of radioactive waste by early next century á" and answer critics who claim that its plans are ...

Ehsan Masood

1996-10-31T23:59:59.000Z

105

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD Report to January 1, 2001, to January 31, 2002 The U All NWTRB reports are available at www.nwtrb.gov, the NWTRB Web site. #12;#12;#12;NUCLEAR WASTE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 Appendices Appendix A U.S. Nuclear Waste Technical Review Board Members

106

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD Report to The U.S. Congress And The Secretary of Energy January 1, 2003, to December 31, 2003 #12;U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD Report to The U.nwtrb.gov, the NWTRB Web site. #12;#12;#12;NUCLEAR WASTE TECHNICAL REVIEW BOARD 2003 Dr. Michael L. Corradini

107

Nuclear Waste Fund fee adequacy: An assessment  

SciTech Connect (OSTI)

The purpose of this report is to present the Department of Energy`s (the Department) analysis of the adequacy of the 1.00 mill per kilowatt-hour (kWh) fee being paid by the utilities generating nuclear power for the permanent disposal of their spent nuclear fuel (SNF). In accordance with the Nuclear Waste Policy Act (NWPA), the SNF would be disposed of in a geologic repository to be developed by the Department. An annual analysis of the fee`s adequacy is required by the NWPA.

NONE

1990-11-01T23:59:59.000Z

108

Nuclear waste management. Quarterly progress report, October-December 1979  

SciTech Connect (OSTI)

Progress and activities are reported on the following: high-level waste immobilization, alternative waste forms, nuclear waste materials characterization, TRU waste immobilization programs, TRU waste decontamination, krypton solidification, thermal outgassing, iodine-129 fixation, monitoring of unsaturated zone transport, well-logging instrumentation development, mobile organic complexes of fission products, waste management system and safety studies, assessment of effectiveness of geologic isolation systems, waste/rock interactions technology, spent fuel and fuel pool integrity program, and engineered barriers. (DLC)

Platt, A.M.; Powell, J.A. (comps.)

1980-04-01T23:59:59.000Z

109

Nuclear waste problem solved, claims Sweden's nuclear industry  

Science Journals Connector (OSTI)

... "WE are not going to leave any waste around that is going to harm anybody." So says Asea-Atom's Dr Kare ... Manners, one of the authors of a just-published report which asserts that the Swedish nuclear power industry has found a way of safely storing unreprocessed, spent fuel from ...

Wendy Barnaby

1978-07-06T23:59:59.000Z

110

Nuclear Waste Fund Activities Management Team | Department of Energy  

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

Waste Fund Activities Management Team Waste Fund Activities Management Team Nuclear Waste Fund Activities Management Team The Nuclear Waste Fund Activities Management Team has responsibility to: Manage the investments and expenditures of the Nuclear Waste Fund; Support correspondence regarding Nuclear Waste Policy Act issues raised by congressional, Inspector General, Government Accounting Office and Freedom of Information Act inquiries; and, Manage the annual fee adequacy assessment process. Applicable Documents Nuclear Waste Policy Act of 1982 Standard Contract for Disposal of Spent Nuclear Fuel and/or High-Level Radioactive Waste Standard Contract Amendment for New Reactors FY 2007 Total System Life Cycle Cost, Pub 2008 FY 2007 Fee Adequacy, Pub 2008 2009 Letter to Congress OCRWM Financial Statements for Annual Report for Years Ended

111

Nuclear Waste Assessment System for Technical Evaluation (NUWASTE)  

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

NWTRB NWTRB www.nwtrb.gov U.S. Nuclear Waste Technical Review Board U.S. Nuclear Waste Technical Review Board: Roles and Priorities Presented by: Nigel Mote, Executive Director, U.S. Nuclear Waste Technical Review Board May 14, 2013 Hyatt Regency Buffalo, Buffalo, NY. Presented to: National Transportation Stakeholders' Forum NWTRB www.nwtrb.gov U.S. Nuclear Waste Technical Review Board The Board's Statutory Mandate * The 1987 amendments to the Nuclear Waste Policy Act (NWPA) established the U.S. Nuclear Waste Technical Review Board. * The Board evaluates the technical and scientific validity of DOE activities related to implementing the NWPA, including: - transportation, packaging, and storage of spent nuclear fuel (SNF) and high-level radioactive waste (HLW)

112

Office of the US Nuclear Waste Negotiator  

SciTech Connect (OSTI)

The Office of the US Nuclear Waste Negotiator was created as an independent federal agency by the US Congress pursuant to the 1987 amendments to the Nuclear Waste Policy Act of 1982. The office, which was authorized by Congress for 5 years following the enactment of the 1987 amendments, is headquartered in Boise, Idaho, and maintains a liaison office in Washington DC. The negotiator is charged with the responsibility of attempting to find a state or Indian tribe willing to host a repository or monitored retrievable storage (MRS) facility at a technically qualified site on reasonable terms. The negotiator is instructed to negotiate with any state or Indian tribe that expresses an interest in hosting a repository or MRS facility. The negotiator will formally submit the negotiated agreement and environmental assessment to Congress, and the agreement will become effective when acted on by Congress and signed by the President into law.

Leroy, D.H.

1991-11-01T23:59:59.000Z

113

Nuclear Materials: Reconsidering Wastes and Assets - 13193  

SciTech Connect (OSTI)

The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable ('assets') to worthless ('wastes'). In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or - in the case of high level waste - awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site's (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as 'waste' include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest. (authors)

Michalske, T.A. [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States)

2013-07-01T23:59:59.000Z

114

International nuclear waste management fact book  

SciTech Connect (OSTI)

The International Nuclear Waste Management Fact Book has been compiled to provide current data on fuel cycle and waste management facilities, R and D programs, and key personnel in 24 countries, including the US; four multinational agencies; and 20 nuclear societies. This document, which is in its second year of publication supersedes the previously issued International Nuclear Fuel Cycle Fact Book (PNL-3594), which appeared annually for 12 years. The content has been updated to reflect current information. The Fact Book is organized as follows: National summaries--a section for each country that summarizes nuclear policy, describes organizational relationships, and provides addresses and names of key personnel and information on facilities. International agencies--a section for each of the international agencies that has significant fuel cycle involvement and a list of nuclear societies. Glossary--a list of abbreviations/acronyms of organizations, facilities, and technical and other terms. The national summaries, in addition to the data described above, feature a small map for each country and some general information that is presented from the perspective of the Fact Book user in the US.

Abrahms, C W; Patridge, M D; Widrig, J E

1995-11-01T23:59:59.000Z

115

Seal welded cast iron nuclear waste container  

DOE Patents [OSTI]

This invention identifies methods and articles designed to circumvent metallurgical problems associated with hermetically closing an all cast iron nuclear waste package by welding. It involves welding nickel-carbon alloy inserts which are bonded to the mating plug and main body components of the package. The welding inserts might be bonded in place during casting of the package components. When the waste package closure weld is made, the most severe thermal effects of the process are restricted to the nickel-carbon insert material which is far better able to accommodate them than is cast iron. Use of nickel-carbon weld inserts should eliminate any need for pre-weld and post-weld heat treatments which are a problem to apply to nuclear waste packages. Although the waste package closure weld approach described results in a dissimilar metal combination, the relative surface area of nickel-to-iron, their electrochemical relationship, and the presence of graphite in both materials will act to prevent any galvanic corrosion problem.

Filippi, Arthur M. (Pittsburgh, PA); Sprecace, Richard P. (Murrysville, PA)

1987-01-01T23:59:59.000Z

116

Nuclear waste programs; Semiannual progress report, October 1991--March 1992  

SciTech Connect (OSTI)

This document reports on the work done by the Nuclear Waste Programs of the Chemical Technology Division (CMT), Argonne National Laboratory, in the period October 1991-March 1992. In these programs, studies are underway on the performance of waste glass and spent fuel in projected nuclear repository conditions to provide input to the licensing of the nation`s high-level waste repositories

Bates, J.K.; Bradley, C.R.; Buck, E.C.; Dietz, N.L.; Ebert, W.L.; Emery, J.W.; Feng, X.; Finn, P.A.; Gerding, T.J.; Hoh, J.C. [and others

1993-11-01T23:59:59.000Z

117

E-Print Network 3.0 - aqueous nuclear wastes Sample Search Results  

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

nuclear wastes Search Powered by Explorit Topic List Advanced Search Sample search results for: aqueous nuclear wastes Page: << < 1 2 3 4 5 > >> 1 Enabling a Sustainable Nuclear...

118

Disposing of nuclear waste in a salt bed  

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

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

119

The necessity for permanence : making a nuclear waste storage facility  

E-Print Network [OSTI]

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

Stupay, Robert Irving

1991-01-01T23:59:59.000Z

120

Nuclear waste disposal in Switzerland: science, politics and uncertainty  

Science Journals Connector (OSTI)

In Switzerland, radioactive waste arises from electricity produced by five nuclear power plants and from the use of ... fields of medicine, industry and research. The waste is grouped into three categories: High-...

Simon Loew

2004-04-01T23:59:59.000Z

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


121

WIPP Uses Recovery Act Funding to Reduce Nuclear Waste Footprint |  

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

Uses Recovery Act Funding to Reduce Nuclear Waste Footprint Uses Recovery Act Funding to Reduce Nuclear Waste Footprint WIPP Uses Recovery Act Funding to Reduce Nuclear Waste Footprint August 1, 2011 - 12:00pm Addthis Media Contact Deb Gill www.wipp.energy.gov 575-234-7270 CARLSBAD, N.M. - The U.S. Department of Energy's (DOE's) Carlsbad Field Office (CBFO) reduced the nuclear waste footprint by using American Recovery and Reinvestment Act funds to expedite the clean up of five transuranic (TRU) waste storage sites and to make important infrastructure improvements at the Waste Isolation Pilot Plant (WIPP). Expediting TRU waste shipments supports DOE's goal to dispose of 90 percent of legacy TRU waste by 2015, saving taxpayers million of dollars in storage and maintenance costs. Recovery Act funds allowed highly trained teams to safely prepare and load

122

Extraction of cesium and strontium from nuclear waste  

DOE Patents [OSTI]

Cesium is extracted from acidified nuclear waste by contacting the waste with a bis 4,4'(5) [1-hydroxy-2-ethylhexyl]benzo 18-crown-6 compound and a cation exchanger in a matrix solution. Strontium is extracted from acidified nuclear waste by contacting the waste with a bis 4,4'(5') [1-hydroxyheptyl]cyclohexo 18-crown-6 compound, and a cation exchanger in a matrix solution.

Davis, Jr., Milton W. (Lexington, SC); Bowers, Jr., Charles B. (Columbia, SC)

1988-01-01T23:59:59.000Z

123

U.S. Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

U.S. Nuclear Waste Technical Review Board Report to The U.S. Congressand The Secretary of Energy March 1, 2006­December 31, 2007 #12;#12;U.S. Nuclear Waste Technical Review Board Report to The U in this report. #12;#12;#12;U.S. Nuclear Waste Technical Review Board B. John Garrick, Ph.D., P.E., Chairman

124

Nevada nuclear waste storage investigations: briefing book  

SciTech Connect (OSTI)

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

NONE

1983-03-01T23:59:59.000Z

125

Hot demonstrations of nuclear-waste processing technologies  

Science Journals Connector (OSTI)

Several types of nuclear-waste-treatment technologies are currently being demonstrated at Argonne National Laboratory-West, ranging from complex,...

H. F. McFarlane; K. M. Goff; F. S. Felicione; C. C. Dwight; D. B. Barber

1997-07-01T23:59:59.000Z

126

Congressional Preferences and the Advancement of American Nuclear Waste Policy.  

E-Print Network [OSTI]

??The problem of nuclear waste disposal has existed since the time of the Manhattan Project in World War II. Although there exist a number of… (more)

Ternate, Rhoel Gonzales

2013-01-01T23:59:59.000Z

127

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… (more)

Hoag, Christopher Ian.

2006-01-01T23:59:59.000Z

128

Engineering of Deinococcus radiodurans R1 for Bioprecipitation of Uranium from Dilute Nuclear Waste  

Science Journals Connector (OSTI)

...radiodurans R1 for Bioprecipitation of Uranium from Dilute Nuclear Waste Published ahead of print on 20 October 2006. Deepti...situ approach to biorecovery of uranium from dilute nuclear waste. Nuclear waste contains a variety of heavy metals, radionuclides...

Deepti Appukuttan; Amara Sambasiva Rao; Shree Kumar Apte

2006-10-20T23:59:59.000Z

129

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

Science Journals Connector (OSTI)

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

Burkhard Heuel-Fabianek; Ralf Hille

2005-12-20T23:59:59.000Z

130

Aspects of Nuclear Waste Disposal of Use in Teaching Basic Chemistry  

Science Journals Connector (OSTI)

Aspects of Nuclear Waste Disposal of Use in Teaching Basic Chemistry ... Various aspects of nuclear waste disposal are discussed for their value in providing pedagogical examples. ... Radioactivity, Radiation, and the Chemistry of Nuclear Waste ...

Gregory R. Choppin

1994-01-01T23:59:59.000Z

131

The U.S. Nuclear Waste Technical Review Board Status Update ...  

Office of Environmental Management (EM)

The U.S. Nuclear Waste Technical Review Board Status Update The U.S. Nuclear Waste Technical Review Board Status Update The U.S. Nuclear Waste Technical Review Board Status Update...

132

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD The U.S. Congress And The Secretary of Energy Report.nwtrb.gov, the NWTRB Web site. #12;#12;#12;NUCLEAR WASTE TECHNICAL REVIEW BOARD Dr. Jared L. Cohon, Chairman Carnegie, California Dr. Debra S. Knopman Progressive Policy Institute Washington, D.C. Dr. Priscilla P. Nelson

133

NUCLEAR ARMS PLANTS: Idaho bars entry of plutonium wastes  

Science Journals Connector (OSTI)

The Department of Energy—already beset by massive cleanup and safety problems at its nuclear arms plants—now must grapple with a further dilemma in dealing with radioactive wastes. ... Gov. Cecil D. Andrus of Idaho closed the state's borders on Sept. 1 to waste shipments from the Rocky Flats nuclear weapons plant near Denver. ...

RICHARD SELTZER

1989-09-11T23:59:59.000Z

134

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment...  

Energy Savers [EERE]

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010 Review of Nuclear Safety Culture at the Hanford Site Waste...

135

E-Print Network 3.0 - affecting nuclear waste Sample Search Results  

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

Powered by Explorit Topic List Advanced Search Sample search results for: affecting nuclear waste Page: << < 1 2 3 4 5 > >> 1 Nuclear Waste Assessment System for Technical...

136

The Ethics of Nuclear Waste in Canada: Risks, Harms and Unfairness.  

E-Print Network [OSTI]

??The Nuclear Waste Management Organization (NWMO)  – the crown corporation responsible for the long-term storage of nuclear fuel waste in Canada  – seeks to bury… (more)

Wilding, Ethan

2010-01-01T23:59:59.000Z

137

Method of preparing nuclear wastes for tansportation and interim storage  

DOE Patents [OSTI]

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

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

1984-01-01T23:59:59.000Z

138

NUCLEAR WASTE VITRIFICATION EFFICIENCY COLD CAP REACTIONS  

SciTech Connect (OSTI)

The cost and schedule of nuclear waste treatment and immobilization are greatly affected by the rate of glass production. Various factors influence the performance of a waste-glass melter. One of the most significant, and also one of the least understood, is the process of batch melting. Studies are being conducted to gain fundamental understanding of the batch reactions, particularly those that influence the rate of melting, and models are being developed to link batch makeup and melter operation to the melting rate. Batch melting takes place within the cold cap, i.e., a batch layer floating on the surface of molten glass. The conversion of batch to glass consists of various chemical reactions, phase transitions, and diffusion-controlled processes. These include water evaporation (slurry feed contains as high as 60% water), gas evolution, the melting of salts, the formation of borate melt, reactions of borate melt with molten salts and with amorphous oxides (Fe{sub 2}O{sub 3} and Al{sub 2}O{sub 3}), the formation of intermediate crystalline phases, the formation of a continuous glass-forming melt, the growth and collapse of primary foam, and the dissolution of residual solids. To this list we also need to add the formation of secondary foam that originates from molten glass but accumulates on the bottom of the cold cap. This study presents relevant data obtained for a high-level-waste melter feed and introduces a one-dimensional (1D) mathematical model of the cold cap as a step toward an advanced three-dimensional (3D) version for a complete model of the waste glass melter. The 1D model describes the batch-to-glass conversion within the cold cap as it progresses in a vertical direction. With constitutive equations and key parameters based on measured data, and simplified boundary conditions on the cold-cap interfaces with the glass melt and the plenum space of the melter, the model provides sensitivity analysis of the response of the cold cap to the batch makeup and melter conditions. The model demonstrates that batch foaming has a decisive influence on the rate of melting. Understanding the dynamics of the foam layer at the bottom of the cold cap and the heat transfer through it appears crucial for a reliable prediction of the rate of melting as a function of the melter-feed makeup and melter operation parameters. Although the study is focused on a batch for waste vitrification, the authors expect that the outcome will also be relevant for commercial glass melting.

KRUGER AA; HRMA PR; POKORNY R

2011-07-29T23:59:59.000Z

139

Nuclear waste vitrification efficiency: cold cap reactions  

SciTech Connect (OSTI)

The cost and schedule of nuclear waste treatment and immobilization are greatly affected by the rate of glass production. Various factors influence the performance of a waste-glass melter. One of the most significant, and also one of the least understood, is the process of batch melting. Studies are being conducted to gain fundamental understanding of the batch reactions, particularly those that influence the rate of melting, and models are being developed to link batch makeup and melter operation to the melting rate. Batch melting takes place within the cold cap, i.e., a batch layer floating on the surface of molten glass. The conversion of batch to glass consists of various chemical reactions, phase transitions, and diffusion-controlled processes. These include water evaporation (slurry feed contains as high as 60% water), gas evolution, the melting of salts, the formation of borate melt, reactions of borate melt with molten salts and with amorphous oxides (Fe2O3 and Al2O3), the formation of intermediate crystalline phases, the formation of a continuous glass-forming melt, the growth and collapse of primary foam, and the dissolution of residual solids. To this list we also need to add the formation of secondary foam that originates from molten glass but accumulates on the bottom of the cold cap. This study presents relevant data obtained for a high-level-waste melter feed and introduces a one-dimensional (1D) mathematical model of the cold cap as a step toward an advanced three-dimensional (3D) version for a complete model of the waste glass melter. The 1D model describes the batch-to-glass conversion within the cold cap as it progresses in a vertical direction. With constitutive equations and key parameters based on measured data, and simplified boundary conditions on the cold-cap interfaces with the glass melt and the plenum space of the melter, the model provides sensitivity analysis of the response of the cold cap to the batch makeup and melter conditions. The model demonstrates that batch foaming has a decisive influence on the rate of melting. Understanding the dynamics of the foam layer at the bottom of the cold cap and the heat transfer through it appears crucial for a reliable prediction of the rate of melting as a function of the melter-feed makeup and melter operation parameters. Although the study is focused on a batch for waste vitrification, the authors expect that the outcome will also be relevant for commercial glass melting.

Hrma, Pavel R.; Kruger, Albert A.; Pokorny, Richard

2012-12-15T23:59:59.000Z

140

Nuclear waste management. Quarterly progress report, April-June 1980  

SciTech Connect (OSTI)

The status of the following programs is reported: high-level waste immobilization; alternative waste forms; Nuclear Waste Materials Characterization Center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; mobility of organic complexes of fission products in soils; waste management system studies; waste management safety studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology; systems study on engineered barriers; criteria for defining waste isolation; spent fuel and fuel pool component integrity program; analysis of spent fuel policy implementation; asphalt emulsion sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and development of backfill material.

Platt, A.M.; Powell, J.A. (comps.)

1980-09-01T23:59:59.000Z

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


141

Removing nuclear waste, one shipment at a time  

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

Stories » Stories » Removing nuclear waste, one shipment at a time Removing nuclear waste, one shipment at a time The Lab's 1,000th shipment of transuranic waste recently left Los Alamos, on its way to a permanent repository near Carlsbad, NM. June 26, 2012 Governor Martinez applauding the 1014th TRU waste shipment New Mexico Governor Susana Martinez and other dignitaries applaud as the 1,014th shipment of transuranic waste leaves Los Alamos National Laboratory. Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email "The milestone we're celebrating is one that has been a long-term environmental commitment." Removing nuclear waste, one shipment at a time Elected officials and other dignitaries recently gathered at Los Alamos

142

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents [OSTI]

A method for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package.

Forsberg, Charles W. (Oak Ridge, TN)

1998-01-01T23:59:59.000Z

143

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents [OSTI]

A method is described for packaging spent nuclear fuel for long-term disposal in a geological repository. At least one spent nuclear fuel assembly is first placed in an unsealed waste package and a depleted uranium fill material is added to the waste package. The depleted uranium fill material comprises flowable particles having a size sufficient to substantially fill any voids in and around the assembly and contains isotopically-depleted uranium in the +4 valence state in an amount sufficient to inhibit dissolution of the spent nuclear fuel from the assembly into a surrounding medium and to lessen the potential for nuclear criticality inside the repository in the event of failure of the waste package. Last, the waste package is sealed, thereby substantially reducing the release of radionuclides into the surrounding medium, while simultaneously providing radiation shielding and increased structural integrity of the waste package. 6 figs.

Forsberg, C.W.

1998-11-03T23:59:59.000Z

144

Nuclear Energy Research Advisory Committee Meeting April 15-16, 2002, Marriott Crystal City Hotel, Arlington, Virginia  

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

15-16, 2002, Marriott Crystal City Hotel, Arlington, Virginia 15-16, 2002, Marriott Crystal City Hotel, Arlington, Virginia NERAC members present: John Ahearne (Monday only) Robert Long Thomas Cochran Warren F. Miller, Jr. Joseph Comfort Benjamin F. Montoya Michael L. Corradini Sekazi Mtingwa Jose Luis Cortez Lura Powell Maureen S. Crandall Richard Reba (Tuesday only) Allen Croff Joy Rempe James Duderstadt (Chair) Daniel C. Sullivan (Monday morning only) Steve Fetter John Taylor Beverly Hartline Ashok Thadani (ad hoc; Monday only) Leslie Hartz Charles E. Till Andrew Klein Neil Todreas (Tuesday only) Dale Klein (Monday only) NERAC members absent: Marvin Fertel Allen Sessoms J. Bennett Johnston C. Bruce Tarter Linda C. Knight Joan Woodard Also present: Ralph Bennett, Director for Advanced Nuclear Energy, Idaho National Engineering and

145

Accelerated chemical aging of crystalline nuclear waste forms  

Science Journals Connector (OSTI)

Nuclear waste disposal is a significant technological issue, and the solution of this problem (or lack thereof) will ultimately determine whether nuclear energy is deemed environmentally friendly, despite significantly lower carbon emissions than fossil fuel energy sources. A critical component of any waste disposal strategy is the selection of the waste form that is tasked with preventing radionuclides from entering the environment. The design of robust nuclear waste forms requires consideration of several criteria, including: radiation tolerance, geological interaction and chemical durability; all of these criteria ensure that the radionuclides do not escape from the waste form. Over the past 30 years, there have been numerous and thorough studies of these criteria on candidate waste forms, including radiation damage and leaching. However, most of these efforts have focused on the performance of the candidate waste form at t = 0, with far less attention paid to the phase stability, and subsequent durability, of candidate waste forms during the course of daughter product formation; that is, the chemical aging of the material. Systematic understanding of phase evolution as a function of chemistry is important for predictions of waste form performance as well as informing waste form design. In this paper, we highlight the research challenges associated with understanding waste form stability when attempting to systematically study the effects of dynamic composition variation due to in situ radionuclide daughter production formation.

C.R. Stanek; B.P. Uberuaga; B.L. Scott; R.K. Feller; N.A. Marks

2012-01-01T23:59:59.000Z

146

Systems and Components Development Expertise [Nuclear Waste Management  

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

Systems and Components Systems and Components Development Expertise Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Systems and Components Development Expertise Bookmark and Share Electrorefiner The electrorefiner: an apparatus used for electrometallurgical treatment of spent nuclear fuel to facilitate storage and ultimate disposal. Click on

147

Spallation reactions for nuclear waste transmutation and production of radioactive nuclear beams  

Science Journals Connector (OSTI)

Spallation reactions are considered an optimum neutron source for nuclear waste transmutation in accelerator-driven systems (ADS). ... They are also used to produce intense radioactive nuclear beams in ISOL facil...

J. Benlliure

2005-09-01T23:59:59.000Z

148

Spallation reactions for nuclear waste transmutation and production of radioactive nuclear beams  

Science Journals Connector (OSTI)

Spallation reactions are considered an optimum neutron source for nuclear waste transmutation in accelerator-driven systems (ADS). ... They are also used to produce intense radioactive nuclear beams in ISOL facil...

J. Benlliurea

2005-01-01T23:59:59.000Z

149

Design of the Prototypical Cryomodule for the EUROTRANS Superconducting Linac for Nuclear Waste Transmutation  

E-Print Network [OSTI]

Design of the Prototypical Cryomodule for the EUROTRANS Superconducting Linac for Nuclear Waste Transmutation

Barbanotti, S; Blache, P; Commeaux, C; Duthil, P; Panzeri, N; Pierini, P; Rampnoux, E; Souli, M

2008-01-01T23:59:59.000Z

150

The Measurement of Thermal Diffusivity of Simulated Glass Forming Nuclear Waste Melts  

Science Journals Connector (OSTI)

High-level nuclear waste is generated during reprocessing of nuclear reactor fuels. At present, these wastes are stored at various locations in the United States until a final waste form (i.e., glass, SYNROC, ......

James U. Derby; L. David Pye; M. J. Plodinec

1983-01-01T23:59:59.000Z

151

Iron Phosphate Glasses: An Alternative for Vitrifying Certain Nuclear Wastes  

SciTech Connect (OSTI)

Vitrification of nuclear waste in a glass is currently the preferred process for waste disposal. DOE currently approves only borosilicate (BS) type glasses for such purposes. However, many nuclear wastes, presently awaiting disposal, have complex and diverse chemical compositions, and often contain components that are poorly soluble or chemically incompatible in BS glasses. Such problematic wastes can be pre-processed and/or diluted to compensate for their incompatibility with a BS glass matrix, but both of these solutions increases the wasteform volume and the overall cost for vitrification. Direct vitrification using alternative glasses that utilize the major components already present in the waste is preferable, since it avoids pre-treating or diluting the waste, and, thus, minimizes the wasteform volume and overall cost.

Delbert E. Day; Chandra S. Ray; Cheol-Woon Kim

2004-12-28T23:59:59.000Z

152

Mortgaging the future: Dumping ethics with nuclear waste  

Science Journals Connector (OSTI)

On August 22, 2005 the U.S. Environmental Protection Agency issued proposed new regulations for radiation releases from the planned permanent U.S. nuclear-waste repository in Yucca Mountain, Nevada. The ... — eve...

Kristin Shrader-Frechette

2005-01-01T23:59:59.000Z

153

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

154

Department of Energy's Nuclear Waste Fund's Fiscal Year 2014...  

Office of Environmental Management (EM)

Nuclear Waste Fund's Fiscal Year 2014 Financial Statement Audit OAS-FS-15-03 November 2014 U.S. Department of Energy Office of Inspector General Office of Audits and Inspections...

155

Nuclear Waste Management in the United States—Starting Over  

Science Journals Connector (OSTI)

...selection of Yucca Mountain prevented the...Unreliable funding source...The Yucca Mountain program will...nuclear waste disposal” (17...Underground—Yucca Mountain and the Nation's...Sweden, SNF disposal site , www...

Rodney C. Ewing; Frank N. von Hippel

2009-07-10T23:59:59.000Z

156

Process to separate transuranic elements from nuclear waste  

DOE Patents [OSTI]

A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR).

Johnson, Terry R. (Wheaton, IL); Ackerman, John P. (Downers Grove, IL); Tomczuk, Zygmunt (Orland Park, IL); Fischer, Donald F. (Glen Ellyn, IL)

1989-01-01T23:59:59.000Z

157

Nuclear Waste: Public Perception and Siting Policy  

Science Journals Connector (OSTI)

The siting of radioactive wastes poses a significant planning challenge to many countries. The public is generally extremely apprehensive about radioactive waste, and this has led to substantial delays in siti...

Joop Van Der Pligt

1989-01-01T23:59:59.000Z

158

Nuclear waste peer review 'needs more transparency'  

Science Journals Connector (OSTI)

... [LONDON] Scientists advising the UK government on radioactive waste disposal have called on the ... disposal have called on the waste management agency Nirex to open up its peer-review arrangements to independent scrutiny if it ...

Ehsan Masood

1997-01-23T23:59:59.000Z

159

Method for forming microspheres for encapsulation of nuclear waste  

DOE Patents [OSTI]

Microspheres for nuclear waste storage are formed by gelling droplets containing the waste in a gelation fluid, transferring the gelled droplets to a furnace without the washing step previously used, and heating the unwashed gelled droplets in the furnace under temperature or humidity conditions that result in a substantially linear rate of removal of volatile components therefrom.

Angelini, Peter (Oak Ridge, TN); Caputo, Anthony J. (Knoxville, TN); Hutchens, Richard E. (Knoxville, TN); Lackey, Walter J. (Oak Ridge, TN); Stinton, David P. (Knoxville, TN)

1984-01-01T23:59:59.000Z

160

The role of NDE in nuclear waste clean-up  

SciTech Connect (OSTI)

With the end of the cold war, the need for large production capability of nuclear weapons has diminished; but concerns have arisen about the condition of the waste and the waste storage tanks from weapon production. The major concern is the potential for the waste to somehow contaminate the water, soil, and air around a plant. To completely solve the problem associated with the nuclear waste, the waste must be ultimately retrieved from the tanks, treated, separated into low-level and high-level waste streams, and then put into a final disposal form that will encapsulate the waste so that it will not penetrate the environment. Going through the process of safely retrieving, characterizing, treating, and disposing of the waste requires a large amount of nondestructive evaluation (NDE) sensor technology. The purpose of this paper is to provide a brief description of the types of NDE technologies needed to provide a safe and adequate solution to the nuclear-waste storage and disposal issue.

Light, G.M. [Southwest Research Inst., San Antonio, TX (United States)

1995-08-01T23:59:59.000Z

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


161

Safety Analysis, Hazard and Risk Evaluations [Nuclear Waste Management  

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

Safety Analysis, Hazard Safety Analysis, Hazard and Risk Evaluations Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Safety Analysis, Hazard and Risk Evaluations Bookmark and Share NE Division personnel had a key role in the creation of the FCF Final Safety Analysis Report (FSAR), FCF Technical Safety Requirements (TSR)

162

State of Nevada, Agency for Nuclear Projects/Nuclear Waste Project Office narrative report, January 1992  

SciTech Connect (OSTI)

The Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) is the State of Nevada agency designated by State law to monitor and oversee US Department of Energy (DOE) activities relative to the possible siting, construction, operation and closure of a high-level nuclear waste repository at Yucca Mountain and to carry out the State of Nevada`s responsibilities under the Nuclear Waste Policy Act of 1982. During the reporting period the NWPO continued to work toward the five objectives designed to implement the Agency`s oversight responsibilities: (1) Assure that the health and safety of Nevada`s citizens are adequately protected with regard to any federal high-level radioactive waste program within the State; (2) Take the responsibilities and perform the duties of the State of Nevada as described in the Nuclear Waste Policy Act of 1982 (Public Law 97-425) and the Nuclear Waste Policy Amendments Act of 1987; (3) Advise the Governor, the State Commission on Nuclear Projects and the Nevada State Legislature on matters concerning the potential disposal of high-level radioactive waste in the State; (4) Work closely and consult with affected local governments and State agencies; (5) Monitor and evaluate federal planning and activities regarding high-level radioactive waste disposal. Plan and conduct independent State studies regarding the proposed repository.

NONE

1992-12-31T23:59:59.000Z

163

Virginia Energy Plan (Virginia)  

Broader source: Energy.gov [DOE]

The 2010 Virginia Energy Plan affirms the state's support for the development of renewable energy. The Plan assesses the state’s energy picture through an examination of the state’s primary energy...

164

Management of radioactive waste from nuclear power plants: An overview  

SciTech Connect (OSTI)

The nuclear power industry, which accounts for about 20% of the total electricity supply, is a vital part of the nation`s energy resource. While it generates approximately one-third of the commercial low-level radioactive waste produced in the country, it has achieved one of the most successful examples in waste minimization. On the other hand, progress on development of new disposal facilities by the state compacts is currently stalled. The milestones have been repeatedly postponed, and the various Acts passed by Congress on nuclear waste disposal have not accomplished what they were intended to do. With dwindling access to waste disposal sites and with escalating disposal costs, the power plant utilities are forced to store wastes onsite as an interim measure. However, such temporary measures are not a permanent solution. A national will is sorely needed to break out of the current impasse.

Devgun, J.S.

1994-07-01T23:59:59.000Z

165

Nuclear physics information needed for accelerator driven transmutation of nuclear waste  

SciTech Connect (OSTI)

There is renewed interest in using accelerator driven neutron sources to address the problem of high-level long-lived nuclear waste. Several laboratories have developed systems that may have a significant impact on the future use of nuclear power, adding options for dealing with long-lived actinide wastes and fission products, and for power production. This paper describes a new Los Alamos concept using thermal neutrons and examines the nuclear data requirements. 7 refs., 3 figs., 1 tab.

Lisowski, P.W.; Bowman, C.D.; Arthur, E.D.; Young, P.G.

1991-01-01T23:59:59.000Z

166

Commercial Spent Nuclear Fuel Waste Package Misload Analysis  

SciTech Connect (OSTI)

The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package design. An example of this type of misload is a fuel assembly designated for the 21-PWR Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are the only types that are evaluated in this calculation. This calculation utilizes information from ''Frequency of SNF Misload for Uncanistered Fuel Waste Package'' (CRWMS M&O 1998) as the starting point. The scope of this calculation is limited to the information available. The information is based on the whole population of fuel assemblies and the whole population of waste packages, because there is no information about the arrival of the waste stream at this time. The scope of this calculation deviates from that specified in ''Technical Work Plan for: Risk and Criticality Department'' (BSC 2002a, Section 2.1.30) in that only waste package misload is evaluated. The remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed elsewhere. The intended use of the calculation is to provide information and inputs to the Preclosure Safety Analysis Department. Before using the results of this calculation, the reader is cautioned to verify that the assumptions made in this calculation regarding the waste stream, the loading process, and the staging of the spent nuclear fuel assemblies are applicable.

A. Alsaed

2005-07-28T23:59:59.000Z

167

Commercial Spent Nuclear Fuel Waste Package Misload Analysis  

SciTech Connect (OSTI)

The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package design. An example of this type of misload is a fuel assembly designated for the 21-PWR Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are the only types that are evaluated in this calculation. This calculation utilizes information from ''Frequency of SNF Misload for Uncanistered Fuel Waste Package'' (CRWMS M&O 1998) as the starting point. The scope of this calculation is limited to the information available. The information is based on the whole population of fuel assemblies and the whole population of waste packages, because there is no information about the arrival of the waste stream at this time. The scope of this calculation deviates from that specified in ''Technical Work Plan for: Risk and Criticality Department'' (BSC 2002a, Section 2.1.30) in that only waste package misload is evaluated. The remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed elsewhere. The intended use of the calculation is to provide information and inputs to the Preclosure Safety Analysis Department. Before using the results of this calculation, the reader is cautioned to verify that the assumptions made in this calculation regarding the waste stream, the loading process, and the staging of the spent nuclear fuel assemblies are applicable.

J.K. Knudson

2003-10-02T23:59:59.000Z

168

Energy Department and Catholic University Improve Safety of Nuclear Waste |  

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

Catholic University Improve Safety of Nuclear Catholic University Improve Safety of Nuclear Waste Energy Department and Catholic University Improve Safety of Nuclear Waste January 30, 2013 - 12:51pm Addthis Secretary of Energy Steven Chu participates in a tour of Catholic University's Vitreous State Laboratory. | Photo courtesy of the Office of Environmental Management. Secretary of Energy Steven Chu participates in a tour of Catholic University's Vitreous State Laboratory. | Photo courtesy of the Office of Environmental Management. David Sheeley David Sheeley Editor/Writer What does this project do? Hanford treats and immobilizes significant quantities of legacy nuclear waste left from the manufacture of plutonium during World War II and the Cold War. Secretary Steven Chu recently visited Catholic University's Vitreous

169

U.S. Nuclear Waste Technical Review Board Strategic Plan: Fiscal Years 20042009  

E-Print Network [OSTI]

Appendix G Appendix G U.S. Nuclear Waste Technical Review Board Strategic Plan: Fiscal Years 2004­2009 (Revised March 2004) Statement of the Board The Nuclear Waste Policy Amendments Act of 1987 directed the U-level radioactive waste. The Act also established the U.S. Nuclear Waste Technical Review Board as an indepen dent

170

Nuclear Energy Research Advisory Committee Meeting November 17-18, 1998, Hyatt Regency Crystal City, Arlington, Virginia  

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

1- 1- Minutes for the Nuclear Energy Research Advisory Committee Meeting November 17-18, 1998, Hyatt Regency Crystal City, Arlington, Virginia NERAC members present: John Ahearne (Tuesday only) Linda Knight Thomas Boulette Thomas Cochran Robert Long Joseph Comfort Warren Miller Jose Luis Cortez Sekazi Mtingwa Maureen S. Crandall (Tuesday only) Richard Reba Allen Croff Joy Rempe James Duderstadt (Chair) Robert Socolow (Tuesday only) Marvin Fertel Daniel C. Sullivan Beverly Hartline Bruce Tarter (Tuesday only) William Kastenberg Charles E. Till Dale Klein Neil Todreas NERAC members absent: J. Bennett Johnston Glenn Seaborg C. Paul Robinson Allen Sessoms Miguel Rios John Taylor Also present: Norton Haberman, Senior Technical Advisor, Office of Nuclear Energy, Science, and Technology, NE, DOE

171

France digs deep for nuclear waste  

Science Journals Connector (OSTI)

... town of Bure in northeast France, the country is preparing to dispose of its radioactive waste. In a €1-billion (US$1.3 billion) underground laboratory, the French ... a €1-billion (US$1.3 billion) underground laboratory, the French National Radioactive Waste Management Agency (ANDRA) is testing the soundness of the rock and the technologies to ...

Declan Butler

2010-08-10T23:59:59.000Z

172

Solid-state NMR characterisation of transition-metal bearing nuclear waste glasses.  

E-Print Network [OSTI]

??Alkali borosilicate glass is used to immobilise high-level radioactive waste generated from the reprocessing of spent nuclear fuel. However, poorly soluble waste products such as… (more)

Greer, Brandon

2012-01-01T23:59:59.000Z

173

An Investigation into the Oxidation State of Molybdenum in Simplified High Level Nuclear Waste Glass Compositions  

E-Print Network [OSTI]

An Investigation into the Oxidation State of Molybdenum in Simplified High Level Nuclear Waste of Mo in glasses containing simplified simulated high level nuclear waste (HLW) streams has been originating from the reprocessing of spent nuclear fuel. Experiments using simulated nuclear waste streams

Sheffield, University of

174

ULTRASONIC ARRAY TECHNIQUE FOR THE INSPECTION OF COPPER LINED CANISTERS FOR NUCLEAR WASTE FUEL  

E-Print Network [OSTI]

ULTRASONIC ARRAY TECHNIQUE FOR THE INSPECTION OF COPPER LINED CANISTERS FOR NUCLEAR WASTE FUEL and Waste Management Co.) for encapsulation of nuclear waste. Due to the radiation emitted by the nuclear, and characterization. The applicability of linear array technique for inspection of copper lined canisters for nuclear

175

Nuclear Waste Imaging and Spent Fuel Verification by Muon Tomography  

E-Print Network [OSTI]

This paper explores the use of cosmic ray muons to image the contents of shielded containers and detect high-Z special nuclear materials inside them. Cosmic ray muons are a naturally occurring form of radiation, are highly penetrating and exhibit large scattering angles on high Z materials. Specifically, we investigated how radiographic and tomographic techniques can be effective for non-invasive nuclear waste characterization and for nuclear material accountancy of spent fuel inside dry storage containers. We show that the tracking of individual muons, as they enter and exit a structure, can potentially improve the accuracy and availability of data on nuclear waste and the contents of Dry Storage Containers (DSC) used for spent fuel storage at CANDU plants. This could be achieved in near real time, with the potential for unattended and remotely monitored operations. We show that the expected sensitivity, in the case of the DSC, exceeds the IAEA detection target for nuclear material accountancy.

Jonkmans, G; Jewett, C; Thompson, M

2012-01-01T23:59:59.000Z

176

Rhenium solubility in borosilicate nuclear waste glass  

E-Print Network [OSTI]

Retention in Hanford LAW Glass - Phase 1 Final Report. VSL-rhenium in borosilicate waste glass as determined by X-rayfor NIST SRM 610–617 Glasses Following ISO Guidelines," 35[

McCloy, John S.

2014-01-01T23:59:59.000Z

177

Nuclear Waste Program Faces Political Burial  

Science Journals Connector (OSTI)

...seeking to halt funding for site work in...United States waste disposal Western U.S...choice ofwaste disposal sites. They just...Washington; Yucca Mountain, Nevada; and...list of proposed disposal sites. Titcomb...

ELIOT MARSHALL

1986-08-22T23:59:59.000Z

178

Public meetings on nuclear waste management: their function and organization  

SciTech Connect (OSTI)

This report focuses on public meetings as a vehicle for public participation in nuclear waste management. The nature of public meetings is reviewed and the functions served by meetings highlighted. The range of participants and their concerns are addressed, including a review of the participants from past nuclear waste management meetings. A sound understanding of the expected participants allows DOE to tailor elements of the meeting, such as notification, format, and agenda to accommodate the attendees. Finally, the report discusses the organization of public meetings on nuclear waste management in order to enhance the DOE's functions for such meetings. Possible structures are suggested for a variety of elements that are relevant prior to, during and after the public meeting. These suggestions are intended to supplement the DOE Public Participation Manual.

Duvernoy, E.G.; Marcus, A.A.; Overcast, T.; Schilling, A.H.

1981-05-01T23:59:59.000Z

179

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

180

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

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


181

Nuclear Physics Information Needed for Accelerator Driven Transmutation of Nuclear Waste  

Science Journals Connector (OSTI)

There is renewed interest in using accelerator driven neutron sources to address the problem of high level long-lived nuclear waste. Several laboratories have developed systems that may ... a significant impact o...

P. W. Lisowski; C. D. Bowman; E. D. Arthur…

1992-01-01T23:59:59.000Z

182

Process to separate transuranic elements from nuclear waste  

DOE Patents [OSTI]

A process is described for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR). 2 figs.

Johnson, T.R.; Ackerman, J.P.; Tomczuk, Z.; Fischer, D.F.

1989-03-21T23:59:59.000Z

183

Process to separate transuranic elements from nuclear waste  

DOE Patents [OSTI]

A process for removing transuranic elements from a waste chloride electrolytic salt containing transuranic elements in addition to rare earth and other fission product elements so the salt waste may be disposed of more easily and the valuable transuranic elements may be recovered for reuse. The salt is contacted with a cadmium-uranium alloy which selectively extracts the transuranic elements from the salt. The waste salt is generated during the reprocessing of nuclear fuel associated with the Integral Fast Reactor (IFR). 2 figs.

Johnson, T.R.; Ackerman, J.P.; Tomczuk, Z.; Fischer, D.F.

1988-07-12T23:59:59.000Z

184

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

185

Funding cut for US nuclear waste dump  

Science Journals Connector (OSTI)

... is expected to propose spending only the estimated US$40 million needed to let the Nuclear Regulatory Commission (NRC) move forwards in evaluating the licence application for Yucca Mountain. ... three to four years. Tom Kauffman, a spokesman for the industry policy group the Nuclear Energy Institute, says that ...

Amanda Leigh Mascarelli

2009-04-29T23:59:59.000Z

186

Nuclear-waste programme criticized by scientists  

Science Journals Connector (OSTI)

... The report underscores many of the criticisms that have been levelled at the Global Nuclear Energy Partnership since it was unveiled by the White House in 2006, namely that ... . The US Department of Energy (DOE) is seeking $405 million for the Global Nuclear Energy Partnership for the 2008 fiscal year, but key Democrats have vowed to put ...

2007-10-31T23:59:59.000Z

187

Siting America's geologic repository for high-level Nuclear Waste: Implications for environmental Policy  

Science Journals Connector (OSTI)

Siting a geologic repository for isolating highlevel nuclear waste up to 10,000 years is ... before attempted in the United States. The Nuclear Waste Policy Act of 1982 exempted repository siting from ... require...

John Lemons; Charles Malone

188

An Evaluation of Our National Policy to Manage Nuclear Waste from Power Plants  

Science Journals Connector (OSTI)

The current national policy to manage nuclear waste from power plants is to dispose ... of the analysis strongly suggest that our national policy to manage nuclear waste should be changed.

Ralph L. Keeney; Detlof von Winterfeldt

1997-01-01T23:59:59.000Z

189

Development of glass vitrification at SRL as a waste treatment technique for nuclear weapon components  

SciTech Connect (OSTI)

This report discusses the development of vitrification for the waste treatment of nuclear weapons components at the Savannah River Site. Preliminary testing of surrogate nuclear weapon electronic waste shows that glass vitrification is a viable, robust treatment method.

Coleman, J.T.; Bickford, D.F.

1991-01-01T23:59:59.000Z

190

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

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

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

191

Locations of Spent Nuclear Fuel and High-Level Radioactive Waste...  

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

Locations of Spent Nuclear Fuel and High-Level Radioactive Waste Locations of Spent Nuclear Fuel and High-Level Radioactive Waste Map of the United States of America showing the...

192

Analysis of Influencing Factor on Fracture Energy of Concrete Containers for Nuclear Waste  

Science Journals Connector (OSTI)

The anti-fracture property of concrete container for nuclear waste was investigated to ensure its long-time ... the materials used to make concrete containers for nuclear waste.

Li Yi; Zhao Wen; Qujie

2012-01-01T23:59:59.000Z

193

DESIGN OF THE PROTOTYPICAL CRYOMODULE FOR THE EUROTRANS SUPERCONDUCTING LINAC FOR NUCLEAR WASTE  

E-Print Network [OSTI]

DESIGN OF THE PROTOTYPICAL CRYOMODULE FOR THE EUROTRANS SUPERCONDUCTING LINAC FOR NUCLEAR WASTE of the accelerator workpackage of the EUROTRANS program for the design of a nuclear waste transmutation system

Boyer, Edmond

194

EA-0896; Research in Alzheimer's Disease Health Sciences Center - West Virginia University Environmental Assessment and (FONSI) Center For Nuclear Medicine Research In Alzheimer's Disease Health Sciences Center - West Virginia University  

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

6; Research in Alzheimer's Disease Health Sciences Center - West 6; Research in Alzheimer's Disease Health Sciences Center - West Virginia University Environmental Assessment and (FONSI) Center for Nuclear Medicine Research in Alzheimer's Disease Health Sciences Center - West Virginia University TABLE OF CONTENTS 1.0 DOCUMENT SUMMARY 1.1. Description 1.2 Alternatives 1.3 Affected Environment 1.4 Construction Impacts 1.5 Operating Impacts 2.0 PURPOSE AND NEED FOR AGENCY ACTION 3.0 DESCRIPTION OF ALTERNATIVES INCLUDING THE PROPOSED ACTION 3.1 Description of the Proposed Action 3.2.1 Construction Activities 3.2.2 Operation Activities 3.3 The No Action Alternative 3.4 Site Alternatives 4.0 THE AFFECTED ENVIRONMENT 5.0 ENVIRONMENTAL CONSEQUENCES OF THE PROPOSED ACTION AND ALTERNATIVES 5.1 Construction Impacts 5.1.1 Sensitive Resources

195

Working Group Report on - Space Nuclear Power Systems and Nuclear Waste  

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

Working Group Report on - Space Nuclear Power Systems and Nuclear Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D "Even though one cannot anticipate the answers in basic research, the return on the public's investment can be maximized through long-range planning of the most promising avenues to explore and the resources needed to explore them." (p. v) "Pursuit of this goal entails developing new technologies and advanced facilities, educating young scientists, training a technical workforce, and contributing to the broader science and technology enterprise?." (p. vi) Ref:: "Nuclear Science: A Long Range Plan", DOE/NSF, Feb. 1996. The purpose of this effort is to develop the first iteration of a

196

Working Group Report on - Space Nuclear Power Systems and Nuclear Waste  

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

Working Group Report on - Space Nuclear Power Systems and Nuclear Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D Working Group Report on - Space Nuclear Power Systems and Nuclear Waste Technology R&D "Even though one cannot anticipate the answers in basic research, the return on the public's investment can be maximized through long-range planning of the most promising avenues to explore and the resources needed to explore them." (p. v) "Pursuit of this goal entails developing new technologies and advanced facilities, educating young scientists, training a technical workforce, and contributing to the broader science and technology enterprise?." (p. vi) Ref:: "Nuclear Science: A Long Range Plan", DOE/NSF, Feb. 1996. The purpose of this effort is to develop the first iteration of a

197

GEOHYDROLOGICAL STUDIES FOR NUCLEAR WASTE ISOLATION AT THE HANFORD RESERVATION -- Vol. I: Executive Summary; Vol. II: Final Report  

E-Print Network [OSTI]

NUCLEAR WASTE ISOLATION AT THE HANFORD RESERVATION Volume I:of Washington state." Rockwell Hanford Operations Topicalmodel evaluation at the Hanford nuclear waste facility."

Apps, J.

2010-01-01T23:59:59.000Z

198

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

to develop a proposed repository for the permanent disposal of such waste at Yucca Mountain in Nevada the DOE's methods of scientific and engineering analysis of the Yucca Mountain site. Those meetings This has been an eventful year for the Yucca Mountain program, during which important changes have been

199

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

) activities related to evaluating the suitability of the Yucca Mountain site and takes a long-term view the DOE's viability assessment (VA) of the Yucca Mountain site, design of the repository and waste package considerable progress in characterizing the Yucca Mountain site. We also appreciate recent efforts by OCRWM

200

UNITED STATES NUCLEAR WASTE TECHNICAL REVIEW BOARD  

E-Print Network [OSTI]

the Board will focus include the technical implications of very long-term dry storage of commercial spent, facility operation and design, and waste storage and disposal. con266vf #12;con266vf 2 The Board to have responsibility under existing law for the long-term management and disposition of DOE-owned spent

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


201

Special report: Nuclear waste - under new management  

SciTech Connect (OSTI)

This article is an overview of the effort to provide a long-term disposal site at Yucca Mountain for high-level wastes. Previous financial and technical problems are discussed, as are current funding initiatives. The final decision on the suitability of the site is scheduled for 1998, and a license application is scheduled for 2001.

NONE

1994-12-31T23:59:59.000Z

202

Economics and policies in nuclear waste disposal  

Science Journals Connector (OSTI)

The controversy over the comparative merits of nuclear energy and fossil fuels has been raging ... important economic, environmental and ethical dimensions puzzling policy-makers as well as the general public...

E. Kula

1994-01-01T23:59:59.000Z

203

Senate poised to act on nuclear waste bills  

Science Journals Connector (OSTI)

On Nov. 30 the Senate committees on Energy & Natural Resources and Environment & Public Works issued a joint report on legislation dealing with the long-term disposal of nuclear waste. But, although the report carries the names of both committees, there ...

1981-12-14T23:59:59.000Z

204

Nuclear Waste Technical Review Board Strategic Plan FY 20082013  

E-Print Network [OSTI]

on compliance activities, in conduct- ing its evaluation, the Board will encourage DOE through its science its review of DOE activities into three technical areas: preclosure operations, including surface-facility design and operations and the transport of spent nuclear fuel and high-level radioactive waste from

205

Backfill composition for secondary barriers in nuclear waste repositories  

DOE Patents [OSTI]

A backfill composition for sorbing and retaining hazardous elements of nuclear wastes comprises 50 to 70% by weight of quartz, 10 to 30% by weight of montmorillonite, 1 to 10% by weight of phosphate mineral, 1 to 10% by weight of ferrous mineral, 1 to 10% by weight of sulfate mineral and 1 to 10% by weight of attapulgite.

Beall, G.W.; Allard, B.M.

1980-05-30T23:59:59.000Z

206

Reproductive Life Events in the Population Living in the Vicinity of a Nuclear Waste Reprocessing Plant  

E-Print Network [OSTI]

Reproductive Life Events in the Population Living in the Vicinity of a Nuclear Waste Reprocessing: There is concern about the health of populations living close to nuclear waste reprocessing plants. We conducted a comparative study on reproductive life events in the general population living near the nuclear waste

Paris-Sud XI, Université de

207

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

E-Print Network [OSTI]

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

Snieder, Roel

208

U.S. Nuclear Waste Technical Review Board Fiscal Year 2002-2007 Strategic Plan  

E-Print Network [OSTI]

Appendix G Appendix G U.S. Nuclear Waste Technical Review Board Fiscal Year 2002-2007 Strategic Plan Statement of the Chairman The U.S. Nuclear Waste Technical Review Board was established of Energy Mission The Board's mission, established in the Nuclear Waste Policy Amendments Act (NWPAA

209

Response to West Cumbria MRWS consultation: Why a deep nuclear waste repository should not be  

E-Print Network [OSTI]

Response to West Cumbria MRWS consultation: Why a deep nuclear waste repository should not be sited geological nuclear waste repository. There a suspicion of predetermination because the only district that has. National and international guidance on how best to select potential sites for deep geological nuclear waste

210

Communication Between the U.S. Nuclear Waste Technical Review Board  

E-Print Network [OSTI]

Appendix F Appendix F Communication Between the U.S. Nuclear Waste Technical Review Board on Energy and Air Quality on March 25, 2004 143 #12;#12;Appendix F UNITED STATES NUCLEAR WASTE TECHNICAL much for your written questions related to my testimony on behalf of the Nuclear Waste Technical Review

211

A ThreeDimensional Finite Element Simulation for Transport of Nuclear Waste Contamination in Porous Media  

E-Print Network [OSTI]

A Three­Dimensional Finite Element Simulation for Transport of Nuclear Waste Contamination of South Carolina, Columbia, South Carolina ABSTRACT: Model equations for transport of nuclear­waste based up on the inherent physics. A three­dimensional finite element method for nuclear waste

Ewing, Richard E.

212

CORROSION OF NUCLEAR WASTE GLASSES IN NON-SATURATED CONDITIONS: TIME-TEMPERATURE BEHAVIOUR  

E-Print Network [OSTI]

CORROSION OF NUCLEAR WASTE GLASSES IN NON-SATURATED CONDITIONS: TIME-TEMPERATURE BEHAVIOUR Michael borosilicate glasses intended for nuclear waste immobilisation based on experimental data obtained during long the corrosion of nuclear waste glasses in terms of time-temperature (t, T) parameters. A linear (non

Sheffield, University of

213

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

E-Print Network [OSTI]

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

Stephens, Larry M.

214

Numerical Zoom for Multiscale Problems with an Application to Nuclear Waste Disposal  

E-Print Network [OSTI]

Numerical Zoom for Multiscale Problems with an Application to Nuclear Waste Disposal Jean of a nuclear waste repository site. Key words: Multiscale, Finite Element, Domain Decomposition, Chimera, Numerical Zoom, Nuclear Waste. PACS: 02.30.Jr, 47.11.Fg, 28.41.Kw, 47.55.P- 1 Introduction The present paper

215

Mass Tracking System Software [Nuclear Waste Management using  

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

Mass Tracking System Mass Tracking System Software Nuclear Fuel Cycle and Waste Management Technologies Overview Modeling and analysis Unit Process Modeling Mass Tracking System Software Waste Form Performance Modeling Safety Analysis, Hazard and Risk Evaluations Development, Design, Operation Overview Systems and Components Development Expertise System Engineering Design Other Major Programs Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE Division on Flickr Nuclear Waste Management using Electrometallurgical Technology Mass Tracking System Software Bookmark and Share The NE Division has developed a computer-based Mass Tracking (MTG) system, which is used at the Idaho National Laboratory Fuel Conditioning Facility (FCF) to maintain a real-time accounting of the inventory of containers and

216

Radioactive Waste Management in Non-Nuclear Countries - 13070  

SciTech Connect (OSTI)

This paper challenges internationally accepted concepts of dissemination of responsibilities between all stakeholders involved in national radioactive waste management infrastructure in the countries without nuclear power program. Mainly it concerns countries classified as class A and potentially B countries according to International Atomic Energy Agency. It will be shown that in such countries long term sustainability of national radioactive waste management infrastructure is very sensitive issue that can be addressed by involving regulatory body in more active way in the infrastructure. In that way countries can mitigate possible consequences on the very sensitive open market of radioactive waste management services, comprised mainly of radioactive waste generators, operators of end-life management facilities and regulatory body. (authors)

Kubelka, Dragan; Trifunovic, Dejan [SORNS, Frankopanska 11, HR-10000 Zagreb (Croatia)] [SORNS, Frankopanska 11, HR-10000 Zagreb (Croatia)

2013-07-01T23:59:59.000Z

217

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

SciTech Connect (OSTI)

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

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

1987-09-01T23:59:59.000Z

218

Microsoft Word - virginia.doc  

Gasoline and Diesel Fuel Update (EIA)

Virginia Virginia NERC Region(s) ....................................................................................................... RFC/SERC Primary Energy Source........................................................................................... Nuclear Net Summer Capacity (megawatts) ....................................................................... 24,109 16 Electric Utilities ...................................................................................................... 19,434 15 Independent Power Producers & Combined Heat and Power ................................ 4,676 21 Net Generation (megawatthours) ........................................................................... 72,966,456 21

219

Microsoft Word - virginia.doc  

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

Virginia Virginia NERC Region(s) ....................................................................................................... RFC/SERC Primary Energy Source........................................................................................... Nuclear Net Summer Capacity (megawatts) ....................................................................... 24,109 16 Electric Utilities ...................................................................................................... 19,434 15 Independent Power Producers & Combined Heat and Power ................................ 4,676 21 Net Generation (megawatthours) ........................................................................... 72,966,456 21

220

"1. Bath County","Pumped Storage","Virginia Electric & Power Co",3003  

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

Virginia" Virginia" "1. Bath County","Pumped Storage","Virginia Electric & Power Co",3003 "2. North Anna","Nuclear","Virginia Electric & Power Co",1864 "3. Possum Point","Gas","Virginia Electric & Power Co",1733 "4. Chesterfield","Coal","Virginia Electric & Power Co",1639 "5. Surry","Nuclear","Virginia Electric & Power Co",1638 "6. Yorktown","Coal","Virginia Electric & Power Co",1141 "7. Tenaska Virginia Generating Station","Gas","Tenaska Virginia Partners LP",927 "8. Clover","Coal","Virginia Electric & Power Co",865

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


221

Process for recovery of palladium from nuclear fuel reprocessing wastes  

DOE Patents [OSTI]

Palladium is selectively removed from spent nuclear fuel reprocessing waste by adding sugar to a strong nitric acid solution of the waste to partially denitrate the solution and cause formation of an insoluble palladium compound. The process includes the steps of: (a) adjusting the nitric acid content of the starting solution to about 10 M; (b) adding 50% sucrose solution in an amount sufficient to effect the precipitation of the palladium compound; (c) heating the solution at reflux temperature until precipitation is complete; and (d) centrifuging the solution to separate the precipitated palladium compound from the supernatant liquid.

Campbell, D.O.; Buxton, S.R.

1980-06-16T23:59:59.000Z

222

Coincidence counter design for the assay of vitrified nuclear waste  

SciTech Connect (OSTI)

For the termination of nuclear safeguards and transfers to waste storage, the verification of the plutonium content in vitrified nuclear waste is required by international safeguards agreements. A novel design has been used to develop a coincidence counter for measuring vitrified nuclear waste. The authors have devised a method to measure the {sup 244}Cm content and to calculate the plutonium content from the curium-to-plutonium ratio. In order to provide unattended inspection, the counter is designed for continuous operation in the presence of highly radioactive samples: 3.0 {times} 10{sup 7} Rad/h gamma and 9.0 {times} 10{sup 7}/s neutron fluence. Operability under these conditions has been obtained by designing a heavily shielded detector with radiation hard components subtending a limited solid angle. A counting technique, Localized Source Term Coincidence Counting, has been developed to allow neutron assay of this type of sample. The system will be installed at the Power Nuclear Corporation Tokai Vitrification Facility in the later part of 1998.

Beddingfield, D.H.; Menlove, H.O. [Los Alamos National Lab., NM (United States); Iwamoto, T.; Tomikawa, H. [Power Nuclear Corp. (Japan)

1998-12-31T23:59:59.000Z

223

The U.S. Nuclear Waste Technical Review Board Status Update  

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

NWTRB NWTRB www.nwtrb.gov U.S. Nuclear Waste Technical Review Board The U S Nuclear Waste Technical Review Board The U.S. Nuclear Waste Technical Review Board Status Update Presented to: National Transportation Stakeholders Forum Presented By: National Transportation Stakeholders Forum Mark Abkowitz May 11, 2011 The Board's Statutory Mandate * The 1987 amendments to the Nuclear Waste Policy Act (NWPA) established the U S Nuclear Waste Technical Review Board established the U.S. Nuclear Waste Technical Review Board. * The Board evaluates the technical and scientific validity of DOE activities related to: - transportation, packaging and storage of spent nuclear fuel (SNF) and high-level radioactive waste (HLW) - site characterization, design, development, and operations of facilities for

224

Summary: Workshop Recommendations—Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management  

Science Journals Connector (OSTI)

Technical Paper / Argonne National Laboratory Specialists’ Workshop on Basic Research Needs for Nuclear Waste Management

A. M. Friedman; D. J. Lam; M. G. Seitz

225

Drainage, Sanitation, and Public Facilities Districts (Virginia) |  

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

Drainage, Sanitation, and Public Facilities Districts (Virginia) Drainage, Sanitation, and Public Facilities Districts (Virginia) Drainage, Sanitation, and Public Facilities Districts (Virginia) < Back Eligibility Agricultural Commercial Construction Developer Industrial Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative Systems Integrator Tribal Government Utility Savings Category Water Buying & Making Electricity Home Weatherization Program Info State Virginia Program Type Siting and Permitting Provider Local Governments and Districts This legislation provides for the establishment of sanitary, sanitation, drainage, and public facilities districts in Virginia. Designated districts are public bodies, and have the authority to regulate the construction and development of sanitation and waste disposal projects in their

226

Innovative systems for sustainable nuclear energy generation and waste management  

Science Journals Connector (OSTI)

The limited amount of fossil resources, the impact of green-house gas emissions on the world climate, the rising demand of primary energy projected to 2050, lead to a potentially critical situation for the world energy supply. The need for alternative (to fossil energies) massive energy production is evaluated to 10 Gtoe. The potential of Nuclear Energy generation at the level of 5 Gtoe is examined. Such a sustainable production can only be met by a breeder reactor fleet for which a deployment scenario is described with the associated constraints. Waste management is discussed in connection with different nuclear energy development scenarios according to the point in time when breeder reactors are started. At the world level, it appears that the optimal handling of today's wastes rests on an early decision to develop tomorrow's breeder reactors.

Jm Loiseaux; S David

2006-01-01T23:59:59.000Z

227

Alcohol-free alkoxide process for containing nuclear waste  

DOE Patents [OSTI]

Disclosed is a method of containing nuclear waste. A composition is first prepared of about 25 to about 80%, calculated as SiO.sub.2, of a partially hydrolyzed silicon compound, up to about 30%, calculated as metal oxide, of a partially hydrolyzed aluminum or calcium compound, about 5 to about 20%, calculated as metal oxide, of a partially hydrolyzed boron or calcium compound, about 3 to about 25%, calculated as metal oxide, of a partially hydrolyzed sodium, potassium or lithium compound, an alcohol in a weight ratio to hydrolyzed alkoxide of about 1.5 to about 3% and sufficient water to remove at least 99% of the alcohol as an azeotrope. The azeotrope is boiled off and up to about 40%, based on solids in the product, of the nuclear waste, is mixed into the composition. The mixture is evaporated to about 25 to about 45% solids and is melted and cooled.

Pope, James M. (Monroeville, PA); Lahoda, Edward J. (Edgewood, PA)

1984-01-01T23:59:59.000Z

228

USED NUCLEAR MATERIALS AT SAVANNAH RIVER SITE: ASSET OR WASTE?  

SciTech Connect (OSTI)

The nuclear industry, both in the commercial and the government sectors, has generated large quantities of material that span the spectrum of usefulness, from highly valuable (“assets”) to worthless (“wastes”). In many cases, the decision parameters are clear. Transuranic waste and high level waste, for example, have no value, and is either in a final disposition path today, or – in the case of high level waste – awaiting a policy decision about final disposition. Other materials, though discardable, have intrinsic scientific or market value that may be hidden by the complexity, hazard, or cost of recovery. An informed decision process should acknowledge the asset value, or lack of value, of the complete inventory of materials, and the structure necessary to implement the range of possible options. It is important that informed decisions are made about the asset value for the variety of nuclear materials available. For example, there is a significant quantity of spent fuel available for recycle (an estimated $4 billion value in the Savannah River Site’s (SRS) L area alone); in fact, SRS has already blended down more than 300 metric tons of uranium for commercial reactor use. Over 34 metric tons of surplus plutonium is also on a path to be used as commercial fuel. There are other radiological materials that are routinely handled at the site in large quantities that should be viewed as strategically important and / or commercially viable. In some cases, these materials are irreplaceable domestically, and failure to consider their recovery could jeopardize our technological leadership or national defense. The inventories of nuclear materials at SRS that have been characterized as “waste” include isotopes of plutonium, uranium, americium, and helium. Although planning has been performed to establish the technical and regulatory bases for their discard and disposal, recovery of these materials is both economically attractive and in the national interest.

Magoulas, V.

2013-06-03T23:59:59.000Z

229

Transmutation of nuclear waste in accelerator-driven systems  

E-Print Network [OSTI]

Today more than ever energy is not only a cornerstone of human development, but also a key to the environmental sustainability of economic activity. In this context, the role of nuclear power may be emphasized in the years to come. Nevertheless, the problems of nuclear waste, safety and proliferation still remain to be solved. It is believed that the use of accelerator-driven systems (ADSs) for nuclear waste transmutation and energy production would address these problems in a simple, clean and economically viable, and therefore sustainable, manner. This thesis covers the major nuclear physics aspects of ADSs, in particular the spallation process and the core neutronics specific to this type of systems. The need for accurate nuclear data is described, together with a detailed analysis of the specific isotopes and energy ranges in which this data needs to be improved and the impact of their uncertainty. Preliminary experimental results for some of these isotopes, produced by the Neutron Time-of-Flight (n_TOF) ...

Herrera-Martínez, A

2004-01-01T23:59:59.000Z

230

Potential applications of nanostructured materials in nuclear waste management.  

SciTech Connect (OSTI)

This report summarizes the results obtained from a Laboratory Directed Research & Development (LDRD) project entitled 'Investigation of Potential Applications of Self-Assembled Nanostructured Materials in Nuclear Waste Management'. The objectives of this project are to (1) provide a mechanistic understanding of the control of nanometer-scale structures on the ion sorption capability of materials and (2) develop appropriate engineering approaches to improving material properties based on such an understanding.

Braterman, Paul S. (The University of North Texas, Denton, TX); Phol, Phillip Isabio; Xu, Zhi-Ping (The University of North Texas, Denton, TX); Brinker, C. Jeffrey; Yang, Yi (University of New Mexico, Albuquerque, NM); Bryan, Charles R.; Yu, Kui; Xu, Huifang (University of New Mexico, Albuquerque, NM); Wang, Yifeng; Gao, Huizhen

2003-09-01T23:59:59.000Z

231

Method of determining a content of a nuclear waste container  

DOE Patents [OSTI]

A method and apparatus are provided for identifying contents of a nuclear waste container. The method includes the steps of forming an image of the contents of the container using digital radiography, visually comparing contents of the image with expected contents of the container and performing computer tomography on the container when the visual inspection reveals an inconsistency between the contents of the image and the expected contents of the container.

Bernardi, Richard T. (Prospect Heights, IL); Entwistle, David (Buffalo Grove, IL)

2003-04-22T23:59:59.000Z

232

Accelerator-driven transmutation of plutonium and nuclear waste  

SciTech Connect (OSTI)

The ultimate disposition of spent reactor fuel and processed high-level nuclear waste (HLW) has been a subject of much concern and little progress since the dawn of the nuclear era. In the United States today, the spent fuel from more than 110 commercial light water reactors continues to be stored onsite while highly toxic liquid HLW continues to be stored in tanks at several U.S. Department of Energy sites. The management policy that has been followed in the United States for the past 12 yr is defined by the Nuclear Waste Policy Act (NWPA) of 1982 and its subsequent amendment of 1987. The NWPA requires the disposal of spent fuel assemblies in geologic waste repositories, the first of which will presumably be located at Yucca Mountain, Nevada. The pace of the process for implementing the Yucca Mountain repository discussed in a recent General Accounting Office (GAO) assessment, remains frustratingly slow. By GAO estimation, an operational permanent waste repository at Yucca Mountain could be delayed beyond the 2020 time frame. The approach to formulating an acceptable HLW disposal strategy has always involved serious consideration of nonproliferation issues. Most recently, the nuclear weapon build-down following the Cold War has stimulated the need for the United States and Russia to dispose of surplus plutonium. Consideration of this has motivated (a) a recognition that all plutonium is a proliferation hazard and (b) a renewed debate on the best approach to dispose of plutonium in general. From an international perspective, there is little agreement on the best strategy for the ultimate disposition of HLW and plutonium. This paper discusses the concept of transmutation of plutonium.

Berwald, D.H. [Grumman Aerospace Corp., Bethpage, NY (United States)

1995-12-31T23:59:59.000Z

233

Nuclear Waste Technical Review Board Correspondence with the Department of Energy  

E-Print Network [OSTI]

85 Appendix E Nuclear Waste Technical Review Board Correspondence with the Department of Energy #12;#12;Appendix E 87 Nuclear Waste Technical Review Board Correspondence with the Department of Energy I n of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The letters typically provide

234

HEAT TRANSFER ANALYSIS FOR NUCLEAR WASTE SOLIDIFICATION CONTAINER  

SciTech Connect (OSTI)

The Nuclear Nonproliferation Programs Design Authority is in the design stage of the Waste Solidification Building (WSB) for the treatment and solidification of the radioactive liquid waste streams generated by the Pit Disassembly and Conversion Facility (PDCF) and Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The waste streams will be mixed with a cementitious dry mix in a 55-gallon waste container. Savannah River National Laboratory (SRNL) has been performing the testing and evaluations to support technical decisions for the WSB. Engineering Modeling & Simulation Group was requested to evaluate the thermal performance of the 55-gallon drum containing hydration heat source associated with the current baseline cement waste form. A transient axi-symmetric heat transfer model for the drum partially filled with waste form cement has been developed and heat transfer calculations performed for the baseline design configurations. For this case, 65 percent of the drum volume was assumed to be filled with the waste form, which has transient hydration heat source, as one of the baseline conditions. A series of modeling calculations has been performed using a computational heat transfer approach. The baseline modeling results show that the time to reach the maximum temperature of the 65 percent filled drum is about 32 hours when a 43 C initial cement temperature is assumed to be cooled by natural convection with 27 C external air. In addition, the results computed by the present model were compared with analytical solutions. The modeling results will be benchmarked against the prototypic test results. The verified model will be used for the evaluation of the thermal performance for the WSB drum. Detailed results and the cases considered in the calculations will be discussed here.

Lee, S.

2009-06-01T23:59:59.000Z

235

Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC).  

SciTech Connect (OSTI)

The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. Achieving the objective of modeling the performance of a disposal scenario requires describing processes involved in waste form degradation and radionuclide release at the subcontinuum scale, beginning with mechanistic descriptions of chemical reactions and chemical kinetics at the atomic scale, and upscaling into effective, validated constitutive models for input to high-fidelity continuum scale codes for coupled multiphysics simulations of release and transport. Verification and validation (V&V) is required throughout the system to establish evidence-based metrics for the level of confidence in M&S codes and capabilities, including at the subcontiunuum scale and the constitutive models they inform or generate. This Report outlines the nature of the V&V challenge at the subcontinuum scale, an approach to incorporate V&V concepts into subcontinuum scale modeling and simulation (M&S), and a plan to incrementally incorporate effective V&V into subcontinuum scale M&S destined for use in the NEAMS Waste IPSC work flow to meet requirements of quantitative confidence in the constitutive models informed by subcontinuum scale phenomena.

Schultz, Peter Andrew

2011-12-01T23:59:59.000Z

236

Removal of Pertechnetate from Simulated Nuclear Waste Streams Using Supported Zerovalent Iron  

E-Print Network [OSTI]

Removal of Pertechnetate from Simulated Nuclear Waste Streams Using Supported Zerovalent Iron John and reduction of pertechnetate anions (TcO4 -) from complex waste mixtures was investigated as an alternative approach to current waste-processing schemes. Although applicable to pertechnetate-containing waste streams

237

Conceivable new recycling of nuclear waste by nuclear power companies in their plants  

E-Print Network [OSTI]

We outline the basic principles and the needed experiments for a conceivable new recycling of nuclear waste by the power plants themselves to avoid its transportation and storage to a (yet unknown) dumping area. Details are provided in an adjoining paper and in patents pending.

Ruggero Maria Santilli

1997-04-09T23:59:59.000Z

238

Stainless steel-zirconium waste forms from the treatment of spent nuclear fuel  

Science Journals Connector (OSTI)

Stainless steel-zirconium waste-form alloys have been developed for the disposal of metallic wastes recovered from spent nuclear fuel using the electrometallurgical process developed by Argonne National Laborator...

S. M. McDeavitt; D. P. Abraham; J. Y. Park; D. D. Keiser

1997-07-01T23:59:59.000Z

239

Idaho Site Taps Old World Process to Treat Nuclear Waste | Department of  

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

Idaho Site Taps Old World Process to Treat Nuclear Waste Idaho Site Taps Old World Process to Treat Nuclear Waste Idaho Site Taps Old World Process to Treat Nuclear Waste September 9, 2013 - 12:00pm Addthis The Idaho site's sodium distillation system. The Idaho site's sodium distillation system. The top of a sodium distillation vessel, where waste enters the system. The top of a sodium distillation vessel, where waste enters the system. The Idaho site's sodium distillation system. The top of a sodium distillation vessel, where waste enters the system. IDAHO FALLS, Idaho - The EM program at the Idaho site is using an age-old process to treat transuranic (TRU) waste left over from nuclear reactor experiments. Developed in the first century and perfected by moonshiners in the 19th century, distillation will be used at the Idaho Nuclear Technology and

240

Radioactive waste isolation in salt: peer review of Office of Nuclear Waste Isolation's Socioeconomic Program Plan  

SciTech Connect (OSTI)

The following recommendations have been abstracted from the body of this report. The Office of Nuclear Waste Isolation's Socioeconomic Program Plan for the Establishment of Mined Geologic Repositories to Isolate Nuclear Waste should be modified to: (1) encourage active public participation in the decision-making processes leading to repository site selection; (2) clearly define mechanisms for incorporating the concerns of local residents, state and local governments, and other potentially interested parties into the early stages of the site selection process. In addition, the Office of Nuclear Waste Isolation should carefully review the overall role that these persons and groups, including local pressure groups organized in the face of potential repository development, will play in the siting process; (3) place significantly greater emphasis on using primary socioeconomic data during the site selection process, reversing the current overemphasis on secondary data collection, description of socioeconomic conditions at potential locations, and development of analytical methodologies; (4) include additional approaches to solving socioeconomic problems. For example, a reluctance to acknowledge that solutions to socioeconomic problems need to be found jointly with interested parties is evident in the plan; (5) recognize that mitigation mechanisms other than compensation and incentives may be effective; (6) as soon as potential sites are identified, the US Department of Energy (DOE) should begin discussing impact mitigation agreements with local officials and other interested parties; and (7) comply fully with the pertinent provisions of NWPA.

Winter, R.; Fenster, D.; O'Hare, M.; Zillman, D.; Harrison, W.; Tisue, M.

1984-07-01T23:59:59.000Z

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


241

2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND  

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

2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE 2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND FEE 2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND FEE As required by the Nuclear Waste Policy Act of 1982 (NWPA), DOE has completed its annual review of the adequacy of the Nuclear Waste Fund fee. Based on that review, the Office of Standard Contract Management has determined that there is no basis to propose an adjustment to the fee to Congress. The Secretary of Energy has adopted and approved this determination. As a result, the fee will remain at the amount specified in the NWPA pending the next annual review. The Secretary's determination is available here. 2011 Secretarial Fee Adequacy Determination.PDF More Documents & Publications Secretarial Determination of the Adequacy of the Nuclear Waste Fund Fee

242

2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND  

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

2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE 2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND FEE 2011 SECRETARIAL DETERMINATION OF THE ADEQUACY OF THE NUCLEAR WASTE FUND FEE As required by the Nuclear Waste Policy Act of 1982 (NWPA), DOE has completed its annual review of the adequacy of the Nuclear Waste Fund fee. Based on that review, the Office of Standard Contract Management has determined that there is no basis to propose an adjustment to the fee to Congress. The Secretary of Energy has adopted and approved this determination. As a result, the fee will remain at the amount specified in the NWPA pending the next annual review. The Secretary's determination is available here. 2011 Secretarial Fee Adequacy Determination.PDF More Documents & Publications Secretarial Determination of the Adequacy of the Nuclear Waste Fund Fee

243

Feasibility of very deep borehole disposal of US nuclear defense wastes .  

E-Print Network [OSTI]

??This thesis analyzes the feasibility of emplacing DOE-owned defense nuclear waste from weapons production into a permanent borehole repository drilled ~4 km into granite basement… (more)

Dozier, Frances Elizabeth

2011-01-01T23:59:59.000Z

244

E-Print Network 3.0 - automated nuclear waste Sample Search Results  

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

Powered by Explorit Topic List Advanced Search Sample search results for: automated nuclear waste Page: << < 1 2 3 4 5 > >> 1 Marc Bachman Amanda Lawing Summary: begins 1982...

245

E-Print Network 3.0 - active nuclear wastes Sample Search Results  

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

Powered by Explorit Topic List Advanced Search Sample search results for: active nuclear wastes Page: << < 1 2 3 4 5 > >> 1 THE UNIVERSITY OF WESTERN ONTARIO RADIATION SAFETY...

246

Synthesis of a triblock polymer system for separation of actinides for nuclear waste remediation.  

E-Print Network [OSTI]

??Nuclear power waste contains radioactive isotopes with long half lives and the problem lies in the fact that the lanthanides and actinides must be separated… (more)

Hamilton, Doris Finley

2011-01-01T23:59:59.000Z

247

Public Participation in Nuclear Waste Management : a Comparative Analysis of the Swedish and Canadian Processes.  

E-Print Network [OSTI]

??This thesis addresses the issue of public participation in the implementation of nuclear waste management (NWM) strategies by comparing the NWM programs of Sweden and… (more)

Camacho, Rosanne

2005-01-01T23:59:59.000Z

248

Feasibility of lateral emplacement in very deep borehole disposal of high level nuclear waste .  

E-Print Network [OSTI]

??The U.S. Department of Energy recently filed a motion to withdraw the Nuclear Regulatory Commission license application for the High Level Waste Repository at Yucca… (more)

Gibbs, Jonathan Sutton

2010-01-01T23:59:59.000Z

249

Cesium and Strontium Specific Exchangers for Nuclear Waste Effluent Remediation  

SciTech Connect (OSTI)

During the past 50 years, nuclear defense activities have produced large quantities of nuclear waste that now require safe and permanent disposal. The general procedure to be implemented involves the removal of cesium and strontium from the waste solutions for disposal in permanently vitrified media. This requires highly selective sorbents or ion exchangers. Further, at the high radiation doses present in the solution, organic exchangers or sequestrants are likely to decompose over time. Inorganic ion exchangers are resistant to radiation damage and can exhibit remarkably high selectivities. We have synthesized three families of tunnel-type ion exchangers. The crystal structures of these compounds as well as their protonated phases, coupled with ion exchange titrations, were determined and this information was used to develop an understanding of their ion exchange behavior. The ion exchange selectivities of these phases could be regulated by isomorphous replacement of the framework metals by larger or smaller radius metals. In the realm of layered compounds, we prepared alumina, silica, and zirconia pillared clays and sodium micas. The pillared clays yielded very high Kd values for Cs+ and were very effective in removing Cs+ from groundwaters. The sodium micas also had a high affinity for Cs+ but an even greater attraction for S42+. They also possess the property of trapping these ions permanently as the layers slowly decrease their interlayer distance as loading occurs. Sodium nonatitanate exhibited extremely high Kd values for Sr2+ in alkaline tank wastes and should be considered for removal of Sr2+ in such cases. For tank wastes containing complexing agents, we have found that adding Ca2+ to the solution releases the complexed Sr2+ which may then be removed with the CST exchanger.

A. Clearfield; A. I. Bortun; L. A. Bortun; E. A. Bhlume; P. Sylvester; G. M. Graziano

2000-09-01T23:59:59.000Z

250

State of Nevada, Agency for Nuclear Projects/Nuclear Waste Project Office narrative report, October 1--December 31, 1991  

SciTech Connect (OSTI)

The Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) is the State of Nevada agency designated by State law to monitor and oversee US Department of Energy (DOE) activities relative to the possible siting, construction, operation and closure of a high-level nuclear waste repository at Yucca Mountain and to carry out the State of Nevada`s responsibilities under the Nuclear Waste Policy Act of 1982. During the reporting period the NWPO continued to work toward the five objectives designed to implement the Agency`s oversight responsibilities. (1) Assure that the health and safety of Nevada`s citizens are adequately protected with regard to any federal high-level radioactive waste program within the State. (2) Take the responsibilities and perform the duties of the State of Nevada as described in the Nuclear Waste Policy Act of 1982 (Public Law 97-425) and the Nuclear Waste Policy Amendments Act of 1987. (3) Advise the Governor, the State Commission on Nuclear Projects and the Nevada State Legislature on matters concerning the potential disposal of high-level radioactive waste in the State. (4) Work closely and consult with affected local governments and State agencies. (5) Monitor and evaluate federal planning and activities regarding high-level radioactive waste disposal. Plan and conduct independent State studies regarding the proposed repository.

NONE

1991-12-31T23:59:59.000Z

251

Thermodynamic data management system for nuclear waste disposal performance assessment  

SciTech Connect (OSTI)

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

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

1988-04-01T23:59:59.000Z

252

THERMODYNAMIC TABLES FOR NUCLEAR WASTE ISOLATION, V.1: AQUEOUSSOLUTIONS DATABASE  

SciTech Connect (OSTI)

Tables of consistent thermodynamic property values for nuclear waste isolation are given. The tables include critically assessed values for Gibbs energy of formation. enthalpy of formation, entropy and heat capacity for minerals; solids; aqueous ions; ion pairs and complex ions of selected actinide and fission decay products at 25{sup o}C and zero ionic strength. These intrinsic data are used to calculate equilibrium constants and standard potentials which are compared with typical experimental measurements and other work. Recommendations for additional research are given.

Phillips, S.L.; Hale, F.V.; Silvester, L.F.

1988-05-01T23:59:59.000Z

253

Long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF)  

Broader source: Energy.gov [DOE]

GC-52 provides legal advice to DOE regarding the long-term management of high-level radioactive waste (HLW) and spent nuclear fuel (SNF). SNF is nuclear fuel that has been used as fuel in a reactor...

254

Characterising encapsulated nuclear waste using cosmic-ray muon tomography  

E-Print Network [OSTI]

Tomographic imaging techniques using the Coulomb scattering of cosmic-ray muons have been shown previously to successfully identify and characterise low- and high-Z materials within an air matrix using a prototype scintillating-fibre tracker system. Those studies were performed as the first in a series to assess the feasibility of this technology and image reconstruction techniques in characterising the potential high-Z contents of legacy nuclear waste containers for the UK Nuclear Industry. The present work continues the feasibility study and presents the first images reconstructed from experimental data collected using this small-scale prototype system of low- and high-Z materials encapsulated within a concrete-filled stainless-steel container. Clear discrimination is observed between the thick steel casing, the concrete matrix and the sample materials assayed. These reconstructed objects are presented and discussed in detail alongside the implications for future industrial scenarios.

Anthony Clarkson; David J. Hamilton; Matthias Hoek; David G. Ireland; John R. Johnstone; Ralf Kaiser; Tibor Keri; Scott Lumsden; David F. Mahon; Bryan McKinnon; Morgan Murray; Siân Nutbeam-Tuffs; Craig Shearer; Guangliang Yang; Colin Zimmerman

2014-10-27T23:59:59.000Z

255

Characterising encapsulated nuclear waste using cosmic-ray muon tomography  

E-Print Network [OSTI]

Tomographic imaging techniques using the Coulomb scattering of cosmic-ray muons have been shown previously to successfully identify and characterise low- and high-Z materials within an air matrix using a prototype scintillating-fibre tracker system. Those studies were performed as the first in a series to assess the feasibility of this technology and image reconstruction techniques in characterising the potential high-Z contents of legacy nuclear waste containers for the UK Nuclear Industry. The present work continues the feasibility study and presents the first images reconstructed from experimental data collected using this small-scale prototype system of low- and high-Z materials encapsulated within a concrete-filled stainless-steel container. Clear discrimination is observed between the thick steel casing, the concrete matrix and the sample materials assayed. These reconstructed objects are presented and discussed in detail alongside the implications for future industrial scenarios.

Clarkson, Anthony; Hoek, Matthias; Ireland, David G; Johnstone, John R; Kaiser, Ralf; Keri, Tibor; Lumsden, Scott; Mahon, David F; McKinnon, Bryan; Murray, Morgan; Nutbeam-Tuffs, Siân; Shearer, Craig; Yang, Guangliang; Zimmerman, Colin

2014-01-01T23:59:59.000Z

256

Destruction of Plutonium and Other Nuclear Waste Materials Using the Accelerator-Driven Transmutation of Waste Concept  

Science Journals Connector (OSTI)

Each large nuclear power plant produces about 300 kilograms of ... about 120 kilograms of long-lived fission product wastes per year, with major constituents in terms ... humans either directly or by clandestine ...

F. Venneri

1997-01-01T23:59:59.000Z

257

Virginia Coalfield Economic Development Authority (Virginia) | Department  

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

Virginia Coalfield Economic Development Authority (Virginia) Virginia Coalfield Economic Development Authority (Virginia) Virginia Coalfield Economic Development Authority (Virginia) < Back Eligibility Commercial Construction Industrial Program Info Start Date 1990 State Virginia Program Type Industry Recruitment/Support Loan Program Public Benefits Fund Provider Virginia Coalfield Economic Development Authority The Virginia Coalfield Economic Development Authority (VACEDA) was created in 1988 to encourage economic development in the western section of the state. The Authority administers incentive and financing programs designed to encourage new job creation and economic diversification, specifically in the electronic information technology, energy, education, and emerging technology sectors. VCEDA provides financial support for fixed assets,

258

Myth of nuclear explosions at waste disposal sites  

SciTech Connect (OSTI)

Approximately 25 years ago, an event is said to have occurred in the plains immediately west of the southern Ural mountains of the Soviet Union that is being disputed to this very day. One person says it was an explosion of nuclear wastes buried in a waste disposal site; other people say it was an above-ground test of an atomic weapon; still others suspect that an alleged contaminated area (of unknown size or even existence) is the result of a series of careless procedures. Since the event, a number of articles about the disposal-site explosion hypothesis written by a Soviet exile living in the United Kingdom have been published. Although the Soviet scientist's training and background are in the biological sciences and his knowledge of nuclear physics or chemistry is limited, people who oppose the use of nuclear energy seem to want to believe what he says without question. The work of this Soviet biologist has received wide exposure both in the United Kingdom and the United States. This report presents arguments against the disposal-site explosion hypothesis. Included are discussions of the amounts of plutonium that would be in a disposal site, the amounts of plutonium that would be needed to reach criticality in a soil-water-plutonium mixture, and experiments and theoretical calculations on the behavior of such mixtures. Our quantitative analyses show that the postulated nuclear explosion is so improbable that it is essentially impossible and can be found only in the never-never land of an active imagination. 24 references, 14 figures, 5 tables.

Stratton, W.R.

1983-10-01T23:59:59.000Z

259

DOE Completes Annual Determination of the Adequacy of the Nuclear Waste  

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

Completes Annual Determination of the Adequacy of the Nuclear Completes Annual Determination of the Adequacy of the Nuclear Waste Fund Fee DOE Completes Annual Determination of the Adequacy of the Nuclear Waste Fund Fee November 2, 2010 - 7:41pm Addthis As required by the Nuclear Waste Policy Act of 1982 (NWPA), DOE has completed its annual review of the adequacy of the Nuclear Waste Fund fee. Based on that review, the Office of Standard Contract Management has determined that there is no basis to propose an adjustment to the fee to Congress. The Secretary of Energy has adopted and approved this determination. As a result, the fee will remain at the amount specified in the NWPA pending the next annual review. The Secretary's determination is available here. Addthis Related Articles GC Commits to Transparency on Nuclear Waste Fund Fee Adequacy Decisions

260

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

SciTech Connect (OSTI)

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

Amoroso, J.; Marra, J.

2014-10-02T23:59:59.000Z

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


261

Separation of technetium from nuclear waste stream simulants. Final report  

SciTech Connect (OSTI)

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

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

1995-09-11T23:59:59.000Z

262

West Virginia | Department of Energy  

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

Qualifying RPS State Export Markets (West Virginia) Qualifying RPS State Export Markets (West Virginia) This entry lists the states with Renewable Portfolio Standard (RPS) policies that accept generation located in West Virginia as eligible sources towards their RPS targets or goals. For specific information with regard to eligible technologies or other restrictions which may vary by state, see the RPS policy entries for the individual states, shown below in the Authority listings. Typically energy must be delivered to an in-state utility or Load Serving Entity, and often only a portion of compliance targets may be met by out-of-state generation. October 16, 2013 Proof of Proper Solid Waste Disposal (West Virginia) This rule provides guidance to persons occupying a residence or operating a business establishment in this state regarding the approved method of

263

Precipitation-adsorption process for the decontamination of nuclear waste supernates  

DOE Patents [OSTI]

High-level nuclear waste supernate is decontaminated of cesium by precipitation of the cesium and potassium with sodium tetraphenyl boron. Simultaneously, strontium-90 is removed from the waste supernate sorption of insoluble sodium titanate. The waste solution is then filtered to separate the solution decontaminated of cesium and strontium.

Lee, Lien-Mow (North Augusta, SC); Kilpatrick, Lester L. (Aiken, SC)

1984-01-01T23:59:59.000Z

264

Precipitation-adsorption process for the decontamination of nuclear waste supernates  

DOE Patents [OSTI]

High-level nuclear waste supernate is decontaminated of cesium by precipitation of the cesium and potassium with sodium tetraphenyl boron. Simultaneously, strontium-90 is removed from the waste supernate sorption of insoluble sodium titanate. The waste solution is then filtered to separate the solution decontaminated of cesium and strontium.

Lee, L.M.; Kilpatrick, L.L.

1982-05-19T23:59:59.000Z

265

The Economic Benefits of Recycling in Virginia  

E-Print Network [OSTI]

The Economic Benefits of Recycling in Virginia Alexander P. Miller Hang T. Nguyen Samantha D, and the recycling contacts from the participating Solid Waste Planning Units discussed in this study. #12;3 Table Determinants of Recycling_______________________________ 12 State Reports

Lewis, Robert Michael

266

Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project  

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

Oversight Assessment of Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project

267

Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project  

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

Oversight Assessment of Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project May 2011 January 2013 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project

268

Calcined Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect (OSTI)

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

M. D. Staiger

2007-06-01T23:59:59.000Z

269

The U.S. Congress and The Secretary of Energy U.S. NUCLEAR WASTE TECHNICAL  

E-Print Network [OSTI]

Report t The U.S. Congress and The Secretary of Energy U.S. NUCLEAR WASTE TECHNICAL REVIEW BOARD Web site. #12;NUCLEAR WASTE TECHNICAL REVIEW BOARD Dr. Jared L. Cohon, Chairman Carnegie Mellon. Debra S. Knopman Progressive Policy Institute Washington, D.C. Dr. Priscilla P. Nelson National Science

270

Comparison of carbon dioxide and nuclear waste storage costs in Lithuania  

Science Journals Connector (OSTI)

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

Dalia Streimikiene

2012-01-01T23:59:59.000Z

271

GC Commits to Transparency on Nuclear Waste Fund Fee Adequacy Decisions |  

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

GC Commits to Transparency on Nuclear Waste Fund Fee Adequacy GC Commits to Transparency on Nuclear Waste Fund Fee Adequacy Decisions GC Commits to Transparency on Nuclear Waste Fund Fee Adequacy Decisions February 26, 2010 - 3:17pm Addthis Consistent with the Administration's commitment to transparency, DOE General Counsel Scott Blake Harris has decided that all future determinations as to the adequacy of the Nuclear Waste Fund fee will be made available to the public on DOE's website shortly after DOE makes a determination. The report relied upon in determining fee adequacy for 2008, the most recent year for which DOE has made a determination, is available here: (2008 Fee Adequacy Letter Report). Addthis Related Articles DOE Completes Annual Determination of the Adequacy of the Nuclear Waste Fund Fee Department of Energy Files Motion to Withdraw Yucca Mountain License

272

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010  

Broader source: Energy.gov [DOE]

Review of Nuclear Safety Culture at the Hanford Site Waste Treatment and Immobilization Plant Project, October 2010

273

A ThreeDimensional Finite Element Simulation for Transport of Nuclear Waste Contamination in Porous Media \\Lambda  

E-Print Network [OSTI]

A Three­Dimensional Finite Element Simulation for Transport of Nuclear Waste Contamination for transport of nuclear­waste contamination in three­dimensional porous media are presented with a description of contamination of groundwater by high­level nuclear waste and a wide variety of other sources makes a proper

Ewing, Richard E.

274

Burying democracy along with UK nuclear waste Stuart Haszeldine 3 May 2012 s.haszeldine@ed.ac.uk  

E-Print Network [OSTI]

Burying democracy along with UK nuclear waste Stuart Haszeldine 3 May 2012 s up to accept. The UK was first to deploy civil nuclear power in 1956, but waste disposal has experienced serial inertia amongst technocrats and politicians, so that problem of nuclear waste accumulating

275

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

SciTech Connect (OSTI)

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

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

2008-05-30T23:59:59.000Z

276

Annual report on the development and characterization of solidified forms for nuclear wastes, 1979  

SciTech Connect (OSTI)

Development and characterization of solidified nuclear waste forms is a major continuing effort at Pacific Northwest Laboratory. Contributions from seven programs directed at understanding chemical composition, process conditions, and long-term behaviors of various nuclear waste forms are included in this report. The major findings of the report are included in extended figure captions that can be read as brief technical summaries of the research, with additional information included in a traditional narrative format. Waste form development proceeded on crystalline and glass materials for high-level and transuranic (TRU) wastes. Leaching studies emphasized new areas of research aimed at more basic understanding of waste form/aqueous solution interactions. Phase behavior and thermal effects research included studies on crystal phases in defense and TRU waste glasses and on liquid-liquid phase separation in borosilicate waste glasses. Radiation damage effects in crystals and glasses from alpha decay and from transmutation are reported.

Chick, L.A.; McVay, G.L.; Mellinger, G.B.; Roberts, F.P.

1980-12-01T23:59:59.000Z

277

Nuclear waste management. Semiannual progress report, October 1982-March 1983  

SciTech Connect (OSTI)

This document is one of a series of technical progress reports designed to report radioactive waste management programs at the Pacific Northwest Laboratory. Accomplishments in the following programs are reported: waste stabilization; Materials Characterization Center; waste isolation; low-level waste management; remedial action; and supporting studies.

Chikalla, T.D.; Powell, J.A. (comps.)

1983-06-01T23:59:59.000Z

278

Nuclear waste management using alpha particle physical phenomena by nanoscale investigations  

Science Journals Connector (OSTI)

Nuclear waste is investigated from the aspect of its nanoscale behaviour. Four materials are selected as the nuclear waste container. Using the irradiation-induced amorphisation, some characteristics are examined. The Displacement Per Atom (dpa) is affected by the ion dose using the Stopping and Range of Ions in Matter 2008 (SRIM 2008) code system, which is a computer package of molecular dynamic simulations. The dpa is changed completely and kinetic energy is transferred to the target by the nuclear collision. The length of the material is a function of the ion collisions. It is concluded that a thickness of 204 nm is the optimised length of a waste drum by crystalline silicotitanate.

Taeho Woo; Taewoo Kim

2011-01-01T23:59:59.000Z

279

Waste-to-Energy Roadmapping Workshop Agenda | Department of Energy  

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

Waste-to-Energy Roadmapping Workshop Agenda Waste-to-Energy Roadmapping Workshop Agenda Waste-to-Energy Roadmapping Workshop Agenda, November 5-6, 2014, Arlington, Virginia....

280

Strategic Minimization of High Level Waste from Pyroprocessing of Spent Nuclear Fuel  

SciTech Connect (OSTI)

The pyroprocessing of spent nuclear fuel results in two high-level waste streams--ceramic and metal waste. Ceramic waste contains active metal fission product-loaded salt from the electrorefining, while the metal waste contains cladding hulls and undissolved noble metals. While pyroprocessing was successfully demonstrated for treatment of spent fuel from Experimental Breeder Reactor-II in 1999, it was done so without a specific objective to minimize high-level waste generation. The ceramic waste process uses “throw-away” technology that is not optimized with respect to volume of waste generated. In looking past treatment of EBR-II fuel, it is critical to minimize waste generation for technology developed under the Global Nuclear Energy Partnership (GNEP). While the metal waste cannot be readily reduced, there are viable routes towards minimizing the ceramic waste. Fission products that generate high amounts of heat, such as Cs and Sr, can be separated from other active metal fission products and placed into short-term, shallow disposal. The remaining active metal fission products can be concentrated into the ceramic waste form using an ion exchange process. It has been estimated that ion exchange can reduce ceramic high-level waste quantities by as much as a factor of 3 relative to throw-away technology.

Simpson, Michael F.; Benedict, Robert W.

2007-09-01T23:59:59.000Z

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


281

Shale Rocks as Nuclear Waste Repositories: Hydrothermal Reactions with Glass, Ceramic and Spent Fuel Waste Forms  

Science Journals Connector (OSTI)

The objectives of various contributions from this laboratory have been to simulate “worst case” situations, given a proposed choice of waste form, repository rock, and waste loading/waste age. The “worst case”...

W. Phelps Freeborn; Michael Zolensky…

1980-01-01T23:59:59.000Z

282

Nuclear Safety R&D in the Waste Processing Technology Development & Deployment Program  

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

R&D in the Waste Processing R&D in the Waste Processing Technology Development & Deployment Program Presentation to the DOE High Level Waste Corporate Board July 29, 2009 Al Baione Office of Waste Processing DOE-EM Office of Engineering & Technology 2 Outline Nuclear Safety Research & Development Overview Summary of EM- NSR&D Presentations from February 2009 Evaluating Performance of Nuclear Grade HEPA Filters under Fire/Smoke Challenge Conditions Structural Integrity Initiative for HLW Tanks Pipeline Plugging and Prevention Advanced Mixing Models Basic Science Opportunities in HLW Storage and Processing Safety Cementitious Barriers Partnership 3 Nuclear Safety Research & Development Overview DNFSB 2004-1 identified need for renewed DOE attention to nuclear safety R&D

283

Remarks About Department of Energy Policy on High-Level Nuclear Waste Management  

Science Journals Connector (OSTI)

At the request of Dr. C. Northrup, it is a pleasure to make a few impromptu remarks about the Department of Energy’s (DOE’s) policy on nuclear waste management and about this meeting.

G. K. Oertel

1980-01-01T23:59:59.000Z

284

Environmental justice of nuclear waste policy in Taiwan: Taipower, government, and local community  

Science Journals Connector (OSTI)

This paper is an investigation into Taiwan’s policy on nuclear waste disposal, concentrating on the ways in ... The central aim was to examine whether this policy breached the distributive and procedural principl...

Gillan Chi-Lun Huang; Tim Gray; Derek Bell

2013-12-01T23:59:59.000Z

285

Engineering of Deinococcus radiodurans R1 for Bioprecipitation of Uranium from Dilute Nuclear Waste  

Science Journals Connector (OSTI)

...February 15, 2007 ERRATUM ERRATUM Engineering of Deinococcus radiodurans R1 for Bioprecipitation of Uranium from Dilute Nuclear Waste Deepti Appukuttan Amara Sambasiva Rao Shree Kumar Apte Molecular Biology Division, Bhabha Atomic Research Centre...

Deepti Appukuttan; Amara Sambasiva Rao; Shree Kumar Apte

2007-02-15T23:59:59.000Z

286

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

Science Journals Connector (OSTI)

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

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

1985-01-01T23:59:59.000Z

287

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

288

Extractive spectrophotometric determination of palladium from acidic high activity nuclear waste  

Science Journals Connector (OSTI)

A simple and rapid method for spectrophotometric determination of palladium from highly acidic and highly radioactive nuclear waste using ?-benzoin oxime (ABO) as...?5M to 4·10?4M in the organic phase. The molar ...

A. Dakshinamoorthy; R. K. Singh; R. H. Iyer

1994-01-01T23:59:59.000Z

289

Nuclear-waste facility on high alert over risk of new explosions  

Science Journals Connector (OSTI)

... The Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, is mined out of a ... of a salt bed 655 metres underground, and stores low- and medium-level military nuclear ...

Declan Butler

2014-05-27T23:59:59.000Z

290

Treatment of Nuclear Waste Solutions Using a New Class of Extractants: Pentaalkyl Propane Diamides  

Science Journals Connector (OSTI)

A new class of bifunctional extractants pentaalkyl propane diamides is studied in order to extract trivalent cations (Am3+, Cm3+…) and other actinides contained in waste solutions of nuclear industry. These solve...

C. Cuillerdier; C. Musikas; P. Hoel

1991-01-01T23:59:59.000Z

291

Engineered barrier development for a nuclear waste repository in basalt: an integration of current knowledge  

SciTech Connect (OSTI)

This document represents a compilation of data and interpretive studies conducted as part of the engineered barriers program of the Basalt Waste Isolation Project. The overall objective of these studies is to provide information on barrier system designs, emplacement and isolation techniques, and chemical reactions expected in a nuclear waste repository located in the basalts underlying the Hanford Site within the state of Washington. Backfills, waste-basalt interactions, sorption, borehole plugging, etc., are among the topics discussed.

Smith, M.J.

1980-05-01T23:59:59.000Z

292

The Nuclear Waste Policy Act, as amended, with appropriations acts appended. Revision 1  

SciTech Connect (OSTI)

This act provides for the development of repositories for the disposal of high-level radioactive wastes, low-level radioactive wastes, and spent nuclear fuels. In addition, it establishes research and development programs, as well as demonstration programs regarding the disposal of these wastes. This Act consists of the Act of Jan. 7, 1983 (Public Law 97-425; 96 Stat. 2201), as amended by Public Law 100-203 and Public Law 102-486.

NONE

1995-02-01T23:59:59.000Z

293

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

E-Print Network [OSTI]

released by the buried wastes and heat remain­ ing in theOF 10-YEAR-OLD WASTES Waste Heat Source C h a r a c t e r ia t e r s e c t i o n s . WASTE HEAT SOURCE CHARACTERIZATION

Wang, J.S.Y.

2010-01-01T23:59:59.000Z

294

Nuclear Waste Disposal: Can the Geologist Guarantee Isolation?  

Science Journals Connector (OSTI)

...to check whether waste disposal really does need an almost...been reported recently at Maxey Flats (Kentucky) (26...radioactive waste burial site, inside a fractured rock...effect of the geological disposal is to con-centrate 3530...

G. de Marsily; E. Ledoux; A. Barbreau; J. Margat

1977-08-05T23:59:59.000Z

295

State-of-the-art review of materials properties of nuclear waste forms.  

SciTech Connect (OSTI)

The Materials Characterization Center (MCC) was established at the Pacific Northwest Laboratory to assemble a standardized nuclear waste materials data base for use in research, systems and facility design, safety analyses, and waste management decisions. This centralized data base will be provided through the means of a Nuclear Waste Materials Handbook. The first issue of the Handbook will be published in the fall of 1981 in looseleaf format so that it can be updated as additional information becomes available. To ensure utmost reliability, all materials data appearing in the Handbook will be obtained by standard procedures defined in the Handbook and approved by an independent Materials Review Board (MRB) comprised of materials experts from Department of Energy laboratories and from universities and industry. In the interim before publication of the Handbook there is need for a report summarizing the existing materials data on nuclear waste forms. This review summarizes materials property data for the nuclear waste forms that are being developed for immobilization of high-level radioactive waste. It is intended to be a good representation of the knowledge concerning the properties of HLW forms as of March 1981. The table of contents lists the following topics: introduction which covers waste-form categories, and important waste-form materials properties; physical properties; mechanical properties; chemical durability; vaporization; radiation effects; and thermal phase stability.

Mendel, J. E.; Nelson, R. D.; Turcotte, R. P.; Gray, W. J.; Merz, M. D.; Roberts, F. P.; Weber, W. J.; Westsik, Jr., J. H.; Clark, D. E.

1981-04-01T23:59:59.000Z

296

Requirements Governing Water Quality Standards (West Virginia) | Department  

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

Requirements Governing Water Quality Standards (West Virginia) Requirements Governing Water Quality Standards (West Virginia) Requirements Governing Water Quality Standards (West Virginia) < Back Eligibility Utility Fed. Government Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Tribal Government Low-Income Residential Schools Retail Supplier Institutional Multi-Family Residential Systems Integrator Fuel Distributor Nonprofit General Public/Consumer Transportation Program Info State West Virginia Program Type Siting and Permitting This rule establishes the requirements governing the discharge or deposit of sewage, industrial wastes and other wastes into waters and establishes water quality standards.

297

Helium solubility in SON68 nuclear waste glass  

SciTech Connect (OSTI)

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

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

2012-12-15T23:59:59.000Z

298

Iron Phosphate Glasses for Vitrifying DOE High Priority Nuclear Wastes  

SciTech Connect (OSTI)

Iron phosphate glasses have been studied as an alternative glass for vitrifying Department of Energy (DOE) high priority wastes. The high priority wastes were the Low Activity Waste (LAW) and the High Level Waste (HLW) with high chrome content stored at Hanford, WA, and the Sodium Bearing Waste (SBW) stored at the Idaho National Engineering and Environmental Laboratory. These wastes were recommended by Tanks Focus Area since they were expected to require special attention when vitrified in borosilicate glasses. All three of these wastes have been successfully vitrified in iron phosphate glasses at waste loadings ranging from a low of 32 wt% for the high sulfate LAW to 40 wt% for the SBW to a high of 75 wt% for the high chrome HLW. In addition to these desirable high waste loadings, the iron phosphate glasses were easily melted, typically between 950 and 1200 C, in less than 4 hours in commercial refractory oxide containers. It is noteworthy that the chemical durability of both glassy and deliberately crystallized iron phosphate wasteforms not only met, but significantly exceeded, all current DOE chemical durability requirements as measured by the Product Consistency Test (PCT) and Vapor Hydration Test (VHT). The high waste loading, low melting temperature, rapid furnace throughput (short melting time) and their outstanding chemical durability could significantly accelerate the clean up effort and reduce the time and cost of vitrifying these high priority wastes.

Kim, C.W.; Day, D.E.

2004-03-29T23:59:59.000Z

299

Na, Mg, Ni and Cs distribution and speciation after long-term alteration of a simulated nuclear waste glass  

E-Print Network [OSTI]

distribution and speciation of Na, Mg, Ni and Cs in a simulated (inactive) nuclear waste glass were studied and Cs represent dose determining long-lived radionuclides (59 Ni, 135 Cs) in vitrified nuclear wasteNa, Mg, Ni and Cs distribution and speciation after long-term alteration of a simulated nuclear

300

Two Approaches to the Geologic Disposal of Long-Lived Nuclear Waste: Yucca Mountain, Nevada and the Waste Isolation Pilot Plant, Carlsbad, New Mexico  

SciTech Connect (OSTI)

A key component of the US energy program is to provide for the safe and permanent isolation of spent nuclear fuel and long-lived radioactive waste produced through programs related to national defense and the generation of electric power by nuclear utilities. To meet this challenge, the US Department of Energy (DOE) has developed a multi-faceted approach to the geologic disposal of long-lived nuclear wastes. Two sites are being developed or studied as current or potential deep geologic repositories for long lived radioactive wastes, the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico and Yucca Mountain, Nevada.

Levich, R. A.; Patterson, R. L.; Linden, R. M.

2002-02-26T23:59:59.000Z

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


301

Role of fast reactor and its cycle to reduce nuclear waste burden  

SciTech Connect (OSTI)

The role of the metal fuel fast reactor with recycling of actinides and the five long-lived fission products based on the concept of the Self-Consistent Nuclear Energy System has been examined by evaluating the reduction of nuclear wastes during the transition period to this reactor system. The evaluation was done in comparison to an LWR once-through case and a conventional actinide recycling oxide fast reactor. As a result, it is quantitatively clarified that a metal fuel fast reactor with actinide and the five long-lived fission products (I{sup 129}, Tc{sup 99}, Zr{sup 93}, Cs{sup 135} and Sn{sup 126}) recycling could play a significant role in reducing the nuclear waste burden including the current LWR wastes. This can be achieved by using a fast neutron spectrum reactor enhanced with metal fuel that brings high capability as a 'waste burner'. (authors)

Arie, Kazuo; Oomori, Takashi; Okita, Takeshi [Toshiba Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama 235-8523 (Japan); Kawashima, Masatoshi [Toshiba Nuclear Engineering Services Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan); Kotake, Shoji [The Japan Atomic Power Company, 1-1, Kanda-Mitoshiro-cho, Chiyoda-ku, Tokyo 101-0053 (Japan); Fuji-ie, Yoichi [Nuclear Salon Fuji-ie, 1-11-10, Yushima, Bunkyo-ku, Tokyo 113-0034 (Japan)

2013-07-01T23:59:59.000Z

302

Nuclear Waste Technical Review Board Thermal-Response Evaluation of Yucca Mountain  

E-Print Network [OSTI]

Nuclear Waste Technical Review Board Thermal-Response Evaluation of Yucca Mountain During the Preclosure and Postclosure Phases July 2008 #12;Thermal Response Evaluation of Yucca Mountain July 2008 Page of the thermal response of the proposed Yucca Mountain repository for various thermal loadings. The U. S. Nuclear

303

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

E-Print Network [OSTI]

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

Wang, J.S.Y.

2010-01-01T23:59:59.000Z

304

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

305

Nuclear waste, public information and residential property values  

SciTech Connect (OSTI)

This document presents details about how increased public knowledge of high-level radioactive waste storage facilities effects the price of near-by residential properties.

Clark, E.E. [Marquette Univ., Milwaukee, WI (United States). Dept. of Economics]|[Argonne National Lab., IL (United States); Allison, T. [Argonne National Lab., IL (United States)

1995-10-10T23:59:59.000Z

306

Private nuclear waste plan faces critics in Australia  

Science Journals Connector (OSTI)

... now based in Seattle, Washington State, and is backed by two organizations active in nuclear ...

Peter Pockley

1999-04-22T23:59:59.000Z

307

The Initial Environmental Assessments for the Nuclear Waste Repository under Section 112 of the Nuclear Waste Policy Act  

E-Print Network [OSTI]

Pollak. J ) Se.e also Vermont Yankee Nuclear Power Corp. %,.requirement). 53. See Vermont Yankee Nuclear Power Corp. v.8th Cir. 1977). 77. Vermont Yankee Nuclear Power Corp. v.

Montange, Charles H.

1985-01-01T23:59:59.000Z

308

The Department of Energy's Nuclear Waste Fund's Fiscal Year 2011 Financial Statements  

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

The Department of Energy's Nuclear The Department of Energy's Nuclear Waste Fund's Fiscal Year 2011 Financial Statements OAS-FS-12-03 November 2011 Department of Energy Washington, DC 20585 November 21, 2011 MEMORANDUM FOR THE DIRECTOR, OFFICE OF STANDARD CONTRACT MANAGEMENT, OFFICE OF GENERAL COUNSEL FROM: Rickey R. Hass Deputy Inspector General for Audits and Inspections Office of Inspector General SUBJECT: INFORMATION: Report on "The Department of Energy's Nuclear Waste Fund's Fiscal Year 2011 Financial Statements" The attached report presents the results of the independent certified public accountants' audit of the Department of Energy's Nuclear Waste Fund's (Fund) Fiscal Year 2011 balance sheet and the related statements of net cost, changes in net position, and budgetary resources.

309

Department of Energy's Nuclear Waste Fund's Fiscal Year 2012 Financial Statement Audit  

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

Nuclear Nuclear Waste Fund's Fiscal Year 2012 Financial Statements OAS-FS-13-05 November 2012 U.S. Department of Energy Office of Inspector General Office of Audits & Inspections Department of Energy Washington, DC 20585 November 28, 2012 MEMORANDUM FOR THE DIRECTOR, OFFICE OF STANDARD CONTRACT MANAGEMENT, OFFICE OF GENERAL COUNSEL FROM: Rickey R. Hass Deputy Inspector General for Audits and Inspections Office of Inspector General SUBJECT: INFORMATION: Audit Report on "Department of Energy's Nuclear Waste Fund's Fiscal Year 2012 Financial Statement Audit" The attached report presents the results of the independent certified public accountants' audit of the Department of Energy's Nuclear Waste Fund's (Fund) Fiscal Year 2012 balance sheet and the

310

Regulatory standards for permanent disposal of spent nuclear fuel and high-level radioactive waste.  

SciTech Connect (OSTI)

This paper provides a summary of observations drawn from twenty years of personal experience in working with regulatory criteria for the permanent disposal of radioactive waste for both the Waste Isolation Pilot Plant repository for transuranic defense waste and the proposed Yucca Mountain repository for spent nuclear fuel and high-level wastes. Rather than providing specific recommendations for regulatory criteria, my goal here is to provide a perspective on topics that are fundamental to how high-level radioactive waste disposal regulations have been implemented in the past. What are the main questions raised relevant to long-term disposal regulations? What has proven effective in the past? Where have regulatory requirements perhaps had unintended consequences? New regulations for radioactive waste disposal may prove necessary, but the drafting of these regulations may be premature until a broad range of policy issues are better addressed. In the interim, the perspective offered here may be helpful for framing policy discussions.

Swift, Peter N.

2010-08-01T23:59:59.000Z

311

Solid radioactive waste management facility design for managing CANDU{sup R} 600 MW nuclear generating station re-tube/refurbishment Waste Streams  

SciTech Connect (OSTI)

The main design features of the re-tube canisters, waste handling equipment and waste containers designed by Atomic Energy of Canada Limited (AECL{sup R}) and implemented in support of the re-tube/refurbishment activities for Candu 600 MW nuclear generating stations are described in this paper. The re-tube/refurbishment waste characterization and the waste management principles, which form the basis of the design activities, are also briefly outlined. (authors)

Pontikakis, N.; Hopkins, J.; Scott, D.; Bajaj, V.; Nosella, L. [AECL, 2251 Speakman Drive, Mississauga, Ontario, L5K 1B2 (Canada)

2007-07-01T23:59:59.000Z

312

WEST VIRGINIA ECONOMIC OUTLOOK  

E-Print Network [OSTI]

WEST VIRGINIA ECONOMIC OUTLOOK 2009 BUREAU OF BUSINESS AND ECONOMIC RESEARCH College of Business and Economics West Virginia University #12;West Virginia Economic Outlook 2009 George W. Hammond, Associate Director, BBER, and Associate Professor of Economics West Virginia Economic Outlook 2009 is published

Mohaghegh, Shahab

313

The Virginia Wetlands Report  

E-Print Network [OSTI]

=palustrine forested wetlands PEM=palustrine emergent wetlands PUB=palustrine unconsolidated wetlands #12;The Virginia

314

The Virginia Wetlands Report  

E-Print Network [OSTI]

VWR -- 1 The Virginia Wetlands Report The Virginia Wetlands Report Spring 2002 Vol. 17, No. 1 Update On Virginia's New and Improved Nontidal Wetlands Program By Ellen Gilinsky, Ph.D. PWS Virginia wetlands program. Key changes included the provi- sion of additional jurisdic- tion over: excavation in all

315

Constructing a Risk Controversy: The Case of a Proposed High-Level Nuclear Waste Repository on the Skull Valley Goshute.  

E-Print Network [OSTI]

?? This thesis is a qualitative case study of a risk controversy generated by a proposal to construct a high-level nuclear waste repository on the… (more)

Jones, Taunya J.

2005-01-01T23:59:59.000Z

316

Can we talk? Communications management for the Waste Isolation Pilot Plant, a complex nuclear waste management project  

SciTech Connect (OSTI)

Sandia Nuclear Waste Management Program is pursuing for DOE an option for permanently disposing radioactive waste in deep geologic repositories. Included in the Program are the Waste Isolation Pilot Plant (WIPP) Project for US defense program mixed waste the Yucca Mountain Project (YMP) for spent power reactor fuel and vitrified high-level waste, projects for other waste types, and development efforts in environmental decision support technologies. WIPP and YMP are in the public arena, of a controversial nature, and provide significant management challenges. Both projects have large project teams, multiple organization participants, large budgets, long durations, are very complex, have a high degree of programmatic risk, and operate in an extremely regulated environment requiring legal defensibility. For environmental projects like these to succeed, SNL`s Program is utilizing nearly all areas in PMI`s Project Management Body of Knowledge (PMBOK) to manage along multiple project dimensions such as the physical sciences (e.g., geophysics and geochemistry; performance assessment; decision analysis) management sciences (controlling the triple constraint of performance, cost and schedule), and social sciences (belief systems; public participation; institutional politics). This discussion focuses primarily on communication challenges active on WIPP. How is the WIPP team meeting the challenges of managing communications?`` and ``How are you approaching similar challenges?`` will be questions for a dialog with the audience.

Goldstein, S.A.; Pullen, G.M.; Brewer, D.R.

1995-07-01T23:59:59.000Z

317

Design of Nanosensors for Fissile Materials in Nuclear Waste Water  

Science Journals Connector (OSTI)

Uranium and plutonium ions and their complexes play an important role in nuclear fuel reprocessing, and their trace characterization is important in nuclear forensics. In this work, we perform ab initio density functional theory calculations of U and Pu ...

Narendra Kumar; Jorge M. Seminario

2013-10-16T23:59:59.000Z

318

British groups organise against transport of nuclear waste  

Science Journals Connector (OSTI)

... THE London Regional Anti-Nuclear Alliance has announced a campaign to prevent the weekly shipment of three tons of ... Alliance has announced a campaign to prevent the weekly shipment of three tons of nuclear ...

1980-01-17T23:59:59.000Z

319

Nuclear waste management technical support in the development of nuclear waste form criteria for the NRC. Task 1. Waste package overview  

SciTech Connect (OSTI)

In this report the current state of waste package development for high level waste, transuranic waste, and spent fuel in the US and abroad has been assessed. Specifically, reviewed are recent and on-going research on various waste forms, container materials and backfills and tentatively identified those which are likely to perform most satisfactorily in the repository environment. Radiation effects on the waste package components have been reviewed and the magnitude of these effects has been identified. Areas requiring further research have been identified. The important variables affecting radionuclide release from the waste package have been described and an evaluation of regulatory criteria for high level waste and spent fuel is presented. Finally, for spent fuel, high level, and TRU waste, components which could be used to construct a waste package having potential to meet NRC performance requirements have been described and identified.

Dayal, R.; Lee, B.S.; Wilke, R.J.; Swyler, K.J.; Soo, P.; Ahn, T.M.; McIntyre, N.S.; Veakis, E.

1982-02-01T23:59:59.000Z

320

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

E-Print Network [OSTI]

waste repository design AERE-R--9343 Atomic Energy Researchof the thermal s t r e s s field. AERE R-8999, Atomic Energy

Wang, J.S.Y.

2010-01-01T23:59:59.000Z

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


321

State of the art review of radioactive waste volume reduction techniques for commercial nuclear power plants  

SciTech Connect (OSTI)

A review is made of the state of the art of volume reduction techniques for low level liquid and solid radioactive wastes produced as a result of: (1) operation of commercial nuclear power plants, (2) storage of spent fuel in away-from-reactor facilities, and (3) decontamination/decommissioning of commercial nuclear power plants. The types of wastes and their chemical, physical, and radiological characteristics are identified. Methods used by industry for processing radioactive wastes are reviewed and compared to the new techniques for processing and reducing the volume of radioactive wastes. A detailed system description and report on operating experiences follow for each of the new volume reduction techniques. In addition, descriptions of volume reduction methods presently under development are provided. The Appendix records data collected during site surveys of vendor facilities and operating power plants. A Bibliography is provided for each of the various volume reduction techniques discussed in the report.

Not Available

1980-04-01T23:59:59.000Z

322

Perceived Risk, Trust, and the Politics of Nuclear Waste  

Science Journals Connector (OSTI)

...repro-cessing reduces but does not eliminate high-level wastes, and the record of managing reprocessing residues at West Valley, Hanford, and other sites is hardly encouraging (27, 39, 47). Rhodes concludes, and we concur, that the only...

PAUL SLOVIC; JAMES H. FLYNN; MARK LAYMAN

1991-12-13T23:59:59.000Z

323

Environmental review and regulation for siting a nuclear waste repository at Yucca Mountain, Nevada  

Science Journals Connector (OSTI)

The U.S. Department of Energy (DOE) has proposed that the first geologic repository for high-level nuclear waste in the United States be sited at Yucca Mountain, Nevada. Repository sitting was exempted by the Nuclear Waste Policy Act from the requirements for an environmental impact statement under the National Environmental Policy Act (NEPA) and, additionally, the DOE was prohibited by law from acquiring new empirical information for environmental assessment. Thus, no systematic, interdisciplinary evaluation of impacts based on site-specific data will occur before the Yucca Mountain environment is irreparably altered by site characterization. Exemption of siting activities for the nation's first geologic repository for high-level nuclear wastes from NEPA review is further evidence of the eclipse of NEPA in decision making, a trend that may foretell how controversial, technologically complex projects will be carried out in the future.

Charles R. Malone

1989-01-01T23:59:59.000Z

324

Virginia State Regulations  

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

Virginia Virginia State Regulations: Virginia State of Virginia The Division of Gas and Oil in the Virginia Department of Mines, Minerals and Energy (DMME) regulates the effects of gas and oil operations both on and below the surface. The Virginia Gas and Oil Board is to foster, encourage, and promote the safe and efficient exploration for and development, production, and utilization of gas and oil resources. Otherwise, three regulatory citizen boards are responsible for adopting Virginia 's environmental regulations. The Virginia Department of Environmental Quality (DEQ) staff administers the regulations as approved by the boards. Finally, the U.S. Environmental Protection Agency (EPA) Region 3, through its Water Protection Division, administers Class II underground injection control (UIC) programs in Virginia in direct implementation.

325

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

SciTech Connect (OSTI)

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

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

2013-07-01T23:59:59.000Z

326

Precipitate hydrolysis process for the removal of organic compounds from nuclear waste slurries  

DOE Patents [OSTI]

A process for removing organic compounds from a nuclear waste slurry comprising reacting a mixture of radioactive waste precipitate slurry and an acid in the presence of a catalytically effective amount of a copper (II) catalyst whereby the organic compounds in the precipitate slurry are hydrolyzed to form volatile organic compounds which are separated from the reacting mixture. The resulting waste slurry, containing less than 10 percent of the orginal organic compounds, is subsequently blended with high level radioactive sludge and transferred to a virtrification facility for processing into borosilicate glass for long-term storage.

Doherty, Joseph P. (Elkton, MD); Marek, James C. (Augusta, GA)

1989-01-01T23:59:59.000Z

327

Precipitate hydrolysis process for the removal of organic compounds from nuclear waste slurries  

DOE Patents [OSTI]

A process for removing organic compounds from a nuclear waste slurry comprising reacting a mixture of radioactive waste precipitate slurry and an acid in the presence of a catalytically effective amount of a copper(II) catalyst whereby the organic compounds in the precipitate slurry are hydrolyzed to form volatile organic compounds which are separated from the reacting mixture. The resulting waste slurry, containing less than 10 percent of the original organic compounds, is subsequently blended with high level radioactive sludge land transferred to a vitrification facility for processing into borosilicate glass for long-term storage. 2 figs., 3 tabs.

Doherty, J.P.; Marek, J.C.

1987-02-25T23:59:59.000Z

328

Glass former composition and method for immobilizing nuclear waste using the same  

DOE Patents [OSTI]

An alkoxide glass former composition has silica-containing constituents present as solid particulates of a particle size of 0.1 to 0.7 micrometers in diameter in a liquid carrier phase substantially free of dissolved silica. The glass former slurry is resistant to coagulation and may contain other glass former metal constituents. The immobilization of nuclear waste employs the described glass former by heating the same to reduce the volume, mixing the same with the waste, and melting the resultant mixture to encapsulate the waste in the resultant glass.

Cadoff, Laurence H. (Wilkins Township, Allegheny County, PA); Smith-Magowan, David B. (Washington, DC)

1988-01-01T23:59:59.000Z

329

Actinides in metallic waste from electrometallurgical treatment of spent nuclear fuel.  

SciTech Connect (OSTI)

Argonne National Laboratory has developed a pyroprocessing-based technique for conditioning spent sodium-bonded nuclear-reactor fuel in preparation for long-term disposal. The technique produces a metallic waste form whose nominal composition is stainless steel with 15 wt.% Zr (SS-15Zr), up to {approx} 11 wt.% actinide elements (primarily uranium), and a few percent metallic fission products. Actual and simulated waste forms show similar eutectic microstructures with approximately equal proportions of iron solid solution phases and Fe-Zr intermetallics. This article reports on an analysis of simulated waste forms containing uranium, neptunium, and plutonium.

Janney, D. E.; Keiser, D. D., Jr.; Engineering Technology

2003-09-01T23:59:59.000Z

330

UK nuclear waste company gets extended lease of life  

Science Journals Connector (OSTI)

... been mounting before the meeting that Nirex was to merge with its largest shareholder, British Nuclear Fuels (BNFL), which owns 40 per cent of Nirex. ...

Ehsan Masood

1997-10-02T23:59:59.000Z

331

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

SciTech Connect (OSTI)

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

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

1993-10-01T23:59:59.000Z

332

NEAMS Nuclear Waste Management IPSC : evaluation and selection of tools for the quality environment.  

SciTech Connect (OSTI)

The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Nuclear Waste Management Integrated Performance and Safety Codes (NEAMS Nuclear Waste Management IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. These M&S capabilities are to be managed, verified, and validated within the NEAMS Nuclear Waste Management IPSC quality environment. M&S capabilities and the supporting analysis workflow and simulation data management tools will be distributed to end-users from this same quality environment. The same analysis workflow and simulation data management tools that are to be distributed to end-users will be used for verification and validation (V&V) activities within the quality environment. This strategic decision reduces the number of tools to be supported, and increases the quality of tools distributed to end users due to rigorous use by V&V activities. This report documents an evaluation of the needs, options, and tools selected for the NEAMS Nuclear Waste Management IPSC quality environment. The objective of the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation Nuclear Waste Management Integrated Performance and Safety Codes (NEAMS Nuclear Waste Management IPSC) program element is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to assess quantitatively the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. This objective will be fulfilled by acquiring and developing M&S capabilities, and establishing a defensible level of confidence in these M&S capabilities. The foundation for assessing the level of confidence is based upon the rigor and results from verification, validation, and uncertainty quantification (V&V and UQ) activities. M&S capabilities are to be managed, verified, and validated within the NEAMS Nuclear Waste Management IPSC quality environment. M&S capabilities and the supporting analysis workflow and simulation data management tools will be distributed to end-users from this same quality environment. The same analysis workflow and simulation data management tools that are to be distributed to end-users will be used for verification and validation (V&V) activities within the quality environment. This strategic decision reduces the number of tools to be supported, and increases the quality of tools distributed to end users due to rigorous use by V&V activities. NEAMS Nuclear Waste Management IPSC V&V and UQ practices and evidence management goals are documented in the V&V Plan. This V&V plan includes a description of the quality environment into which M&S capabilities are imported and V&V and UQ activities are managed. The first phase of implementing the V&V plan is to deploy an initial quality environment through the acquisition and integration of a set of software tools. An evaluation of the needs, options, and tools selected for the quality environment is given in this report.

Bouchard, Julie F.; Stubblefield, William Anthony; Vigil, Dena M.; Edwards, Harold Carter (Org. 1444 : Multiphysics Simulation Technology)

2011-05-01T23:59:59.000Z

333

Nuclear waste: Chernobyl and the future: Forward planning  

Science Journals Connector (OSTI)

... . But other citizenry of Nevada, many of whom remember the consequences of above-ground nuclear-weapons testing in the 1950s and 60s, are deeply sceptical. And so are their ... Frishman, a geologist and the technical policy coordinator for the state government's Agency for Nuclear Projects. The views of local communities will not be determined only by local issues, ...

Geoff Brumfiel

2006-04-19T23:59:59.000Z

334

Supplemnental Volume - Independent Oversight Assessment of the Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant, January 2012  

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

Volume Volume Independent Oversight Assessment of Nuclear Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant January 2012 Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Office of Health, Safety and Security HSS i Independent Oversight Assessment of Safety Culture and Management of Nuclear Safety Concerns at the Hanford Site Waste Treatment and Immobilization Plant Supplemental Volume Table of Contents Foreword ...................................................................................................................................................... iii Acronyms ...................................................................................................................................................... v

335

A compilation of reports of the Advisory Committee on nuclear waste, July 1995 -- June 1996  

SciTech Connect (OSTI)

This compilation contains 8 reports issued by the Advisory Committee on Nuclear Waste (ACNW) during the eighth year of its operation. The reports were submitted to the Chairman and Commissioners of the U.S. Nuclear Regulatory Commission. All reports prepared by the Committee have been made available to the public through the NRC Public Document Room, the U.S. Library of Congress, and the internet at http://www.nrc.gov/ACRSACNW.

NONE

1996-08-01T23:59:59.000Z

336

Virginia Economic Development Incentive Grant (Virginia)  

Broader source: Energy.gov [DOE]

The Virginia Economic Development Incentive Grant is a discretionary cash grant, designed to assist and encourage companies to invest and create new employment opportunities by locating significant...

337

Management of salt waste from electrochemical processing of used nuclear fuel  

SciTech Connect (OSTI)

Electrochemical processing of used nuclear fuel involves operation of one or more cells containing molten salt electrolyte. Processing of the fuel results in contamination of the salt via accumulation of fission products and transuranic (TRU) actinides. Upon reaching contamination limits, the salt must be removed and either disposed or treated to remove the contaminants and recycled back to the process. During development of the Experimental Breeder Reactor-II spent fuel treatment process, waste salt from the electro-refiner was to be stabilized in a ceramic waste form and disposed of in a high-level waste repository. With the cancellation of the Yucca Mountain high-level waste repository, other options are now being considered. One approach that involves direct disposal of the salt in a geologic salt formation has been evaluated. While waste forms such as the ceramic provide near-term resistance to corrosion, they may not be necessary to ensure adequate performance of the repository. To improve the feasibility of direct disposal, recycling a substantial fraction of the useful salt back to the process equipment could minimize the volume of the waste. Experiments have been run in which a cold finger is used for this purpose to crystallize LiCl from LiCl/CsCl. If it is found to be unsuitable for transportation, the salt waste could also be immobilized in zeolite without conversion to the ceramic waste form. (authors)

Simpson, M.F.; Patterson, M.N. [Idaho National Laboratory, P.O. Box 1625, Idaho Falls, Idaho 83415 (United States); Lee, J.; Wang, Y. [Sandia National Laboratory, Albuquerque, NM (United States); Versey, J.; Phongikaroon, S. [University of Idaho, Idaho Falls, ID (United States)

2013-07-01T23:59:59.000Z

338

Terminating Safeguards on Excess Special Nuclear Material: Defense TRU Waste Clean-up and Nonproliferation - 12426  

SciTech Connect (OSTI)

The Department of Energy (DOE) and the National Nuclear Security Administration (NNSA) manages defense nuclear material that has been determined to be excess to programmatic needs and declared waste. When these wastes contain plutonium, they almost always meet the definition of defense transuranic (TRU) waste and are thus eligible for disposal at the Waste Isolation Pilot Plant (WIPP). The DOE operates the WIPP in a manner that physical protections for attractiveness level D or higher special nuclear material (SNM) are not the normal operating condition. Therefore, there is currently a requirement to terminate safeguards before disposal of these wastes at the WIPP. Presented are the processes used to terminate safeguards, lessons learned during the termination process, and how these approaches might be useful for future defense TRU waste needing safeguards termination prior to shipment and disposal at the WIPP. Also described is a new criticality control container, which will increase the amount of fissile material that can be loaded per container, and how it will save significant taxpayer dollars. Retrieval, compliant packaging and shipment of retrievably stored legacy TRU waste has dominated disposal operations at WIPP since it began operations 12 years ago. But because most of this legacy waste has successfully been emplaced in WIPP, the TRU waste clean-up focus is turning to newly-generated TRU materials. A major component will be transuranic SNM, currently managed in safeguards-protected vaults around the weapons complex. As DOE and NNSA continue to consolidate and shrink the weapons complex footprint, it is expected that significant quantities of transuranic SNM will be declared surplus to the nation's needs. Safeguards termination of SNM varies due to the wide range of attractiveness level of the potential material that may be directly discarded as waste. To enhance the efficiency of shipping waste with high TRU fissile content to WIPP, DOE designed an over-pack container, similar to the pipe component, called the criticality control over-pack, which will significantly enhance the efficiency of disposal. Hundreds of shipments of transuranic SNM, suitably packaged to meet WIPP waste acceptance criteria and with safeguards terminated have been successfully emplaced at WIPP (primarily from the Rocky Flats site clean-up) since WIPP opened. DOE expects that thousands more may eventually result from SNM consolidation efforts throughout the weapons complex. (authors)

Hayes, Timothy [Los Alamos National Laboratory, Carlsbad Operations Group (United States); Nelson, Roger [Department Of Energy, Carlsbad Operations Office (United States)

2012-07-01T23:59:59.000Z

339

Vitrification of High-Level Alumina Nuclear Waste  

Science Journals Connector (OSTI)

Borophosphate glass compositions have been developed for the vitrification of a high alumina calcined defense waste. The effect of substituting SiO2 and P2O5 for B2O3 on the viscosity and leach resistance was mea...

J. R. Brotzman

1980-01-01T23:59:59.000Z

340

Nuclear waste ban threatens research at Brookhaven laboratory  

Science Journals Connector (OSTI)

... has been simmering since 1976, when the city placed a ban on the transport of waste material which could, if unresolved, eventually impinge directly on research activities at the laboratory ... could, if unresolved, eventually impinge directly on research activities at the laboratory.

David Dickson

1978-08-24T23:59:59.000Z

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


342

,"Virginia Natural Gas Summary"  

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

1: Prices" "Sourcekey","N3050VA3","N3010VA3","N3020VA3","N3035VA3","N3045VA3" "Date","Natural Gas Citygate Price in Virginia (Dollars per Thousand Cubic Feet)","Virginia Price...

343

Seismic Response of a Deep Underground Geologic Repository for Nuclear Waste at the Waste Isolation Pilot Plant in New Mexico  

SciTech Connect (OSTI)

The Waste Isolation Pilot Plant (WIPP) is a deep underground nuclear waste repository certified by the U.S. Environmental Protection Agency ,(EPA) to store transuranic defense-related waste contaminated by small amounts of radioactive materials. Located at a depth of about 655 meters below the surface, the facility is sited in southeastern New Mexico, about 40 Department of Energy underground facilities, waste disposal. kilometers east of the city of Carlsbad, New Mexico. The U.S. (DOE) managed the design and construction of the surface and and remains responsible for operation and closure following The managing and operating contractor for the DOE at the WIPP, Westinghouse Electric Corporation, maintains two rechmiant seismic monitoring systems located at the surface and in the underground. This report discusses two earthquakes detected by the seismic monitoring system, one a duratior magnitude 5.0 (Md) event located approximately 60 km east-southeast of the facility, and another a body-wave magnitude 5.6 (rob) event that occurred approximately 260 kilometers to the south-southeast.

Sanchez, P.E.

1998-11-02T23:59:59.000Z

344

Integrated data base report--1996: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics  

SciTech Connect (OSTI)

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel (SNF) and commercial and U.S. government-owned radioactive wastes. Inventories of most of these materials are reported as of the end of fiscal year (FY) 1996, which is September 30, 1996. Commercial SNF and commercial uranium mill tailings inventories are reported on an end-of-calendar year (CY) basis. All SNF and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are SNF, high-level waste, transuranic waste, low-level waste, uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, naturally occurring and accelerator-produced radioactive material, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through FY 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

NONE

1997-12-01T23:59:59.000Z

345

Nuclear Waste Management: Building a Foundation to Enhance Trust  

Science Journals Connector (OSTI)

Reading and listening to journalists’ and advocacy group questioning of nuclear experts post-Fukushima, watching news shows, and reading articles ... the grounds that they have failed to move forward on a permane...

Michael R. Greenberg

2013-01-01T23:59:59.000Z

346

Russia fuels fury with scheme for importing nuclear waste  

Science Journals Connector (OSTI)

... The Minatom proposal is a guaranteed non-starter,” says Tom Cochran, director of the Nuclear Program of the Natural Resources Defense Council, a US-based environmental organization. ...

Quirin Schiermeier

2001-05-24T23:59:59.000Z

347

Design of a nuclear-waste package for emplacement in tuff  

SciTech Connect (OSTI)

Design, modeling, and testing activities are under way at LLNL in the development of high level nuclear waste package designs. We discuss the geological characteristics affecting design, the 10CFR60 design requirements, conceptual designs, metals for containment barriers, economic analysis, thermal modeling, and performance modeling.

O`Neal, W.C.; Rothman, A.J.; Gregg, D.W.; Hockman, J.N.; Revelli, M.A.; Russell, E.W.; Schornhorst, J.R.

1983-02-01T23:59:59.000Z

348

Introduction This paper provides the perspective of the members of the Nuclear Waste Tech-  

E-Print Network [OSTI]

the Nuclear Waste Policy Act and designated Yucca Mountain, Nevada, as the sole site to be characterized Vegas. Yucca Mountain is a very dry, arid region with mountain ranges and valleys, sparse vegetation Management Program Within the OCRWM, site-characterization activities are directed by the Yucca Mountain Site

349

Geological Constraints on High-Level Nuclear Waste Disposal and their Relationship to Possible  

E-Print Network [OSTI]

to Possible Long Term Storage Solutions- A Case Study of the Yucca Mountain Project Teresa Dunn 2013 #12;Dunn systems and geologic composition in the selection and development of a secure, long-term storage facilityDunn 1 Geological Constraints on High-Level Nuclear Waste Disposal and their Relationship

Polly, David

350

Nuclear waste store could be built within 25 years, say Lords  

Science Journals Connector (OSTI)

... comes in the form of a blueprint for a new policy structure for managing radioactive waste. The committee calls for the establishment of a new statutory body, the ... . The committee calls for the establishment of a new statutory body, the Nuclear ...

Ehsan Masood

1999-03-25T23:59:59.000Z

351

West Virginia | Department of Energy  

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

April 18, 2013 April 18, 2013 LM Discusses Management of LTS&M Records The U.S. Department of Energy Office of Legacy Management's (LM) efforts to maintain long-term surveillance and maintenance (LTS&M) records were highlighted during the 2013 Waste Management Symposia held February 24 through 28, in Phoenix, Arizona. April 18, 2013 Legacy Management Business Center January 25, 2013 AVESTAR provides high-quality, hands-on, simulator-based workforce training delivered by an experienced team of power industry training professionals for West Virginia students. | Photo courtesy of the Office of Fossil Energy. National Lab Helping to Train Operators for Next Generation of Power Plants Students in West Virginia are receiving hands-on experience for careers at cleaner-burning coal-fired power plants.

352

Molybdenum in Nuclear Waste Glasses -Incorporation and Redox state R.J. Short, R.J. Hand, N.C. Hyatt,  

E-Print Network [OSTI]

Molybdenum in Nuclear Waste Glasses - Incorporation and Redox state R.J. Short, R.J. Hand, N form in simulated high level nuclear waste (HLW) glass melts have been studied. It was found less attention has been paid to the effects of redox on nuclear waste glasses. One particular element

Sheffield, University of

353

THE STRUCTURAL CHEMISTRY OF MOLYBDENUM IN MODEL HIGH LEVEL NUCLEAR WASTE GLASSES, INVESTIGATED BY MO K-EDGE X-RAY ABSORPTION  

E-Print Network [OSTI]

THE STRUCTURAL CHEMISTRY OF MOLYBDENUM IN MODEL HIGH LEVEL NUCLEAR WASTE GLASSES, INVESTIGATED of molybdenum in model UK high level nuclear waste glasses was investigated by X-ray Absorption Spectroscopy (XAS). Molybdenum K-edge XAS data were acquired from several inactive simulant high level nuclear waste

Sheffield, University of

354

A Plan for Nuclear Waste http://www.washingtonpost.com/wp-dyn/content/article/2006/01/29/AR2006012900719_pf.html  

E-Print Network [OSTI]

A Plan for Nuclear Waste http://www.washingtonpost.com/wp-dyn/content/article/2006/01/29/AR2006012900719_pf.html A Plan for Nuclear Waste By John Deutch and Ernest J. Moniz U.S. policy for managing of radioactive waste and heighten rather than reduce public concerns about expanded nuclear power. We agree

Deutch, John

355

Volcanoes in Virginia!  

SciTech Connect (OSTI)

The recent earthquake may have you wondering what other surprises Virginia's geology may hold. Could there be a volcanic eruption in Virginia? Probably not today, but during the Eocene, about 35-48 million years ago, a number of mysterious eruptions occurred in western Virginia. This talk investigates the possible origins of these eruptions, and what they can tell us about the crust and mantle underneath Virginia.

Johnson, Elizabeth Baedke [James Madison University

2012-01-24T23:59:59.000Z

356

Volcanoes in Virginia!  

ScienceCinema (OSTI)

The recent earthquake may have you wondering what other surprises Virginia's geology may hold. Could there be a volcanic eruption in Virginia? Probably not today, but during the Eocene, about 35-48 million years ago, a number of mysterious eruptions occurred in western Virginia. This talk investigates the possible origins of these eruptions, and what they can tell us about the crust and mantle underneath Virginia.

Johnson, Elizabeth Baedke [James Madison University

2014-06-25T23:59:59.000Z

357

The Virginia Wetlands Report  

E-Print Network [OSTI]

VWR -- 1 The Virginia Wetlands Report The Virginia Wetlands Report Winter/Spring 2000 Vol. 15, No. 1 Virginia Debates Nontidal Wetlands Regulation Carl Hershner Wetland regulation is once again- trolling impacts on existing wetlands, as well as creating new wetlands. There is general agreement

358

The Virginia Wetlands Report  

E-Print Network [OSTI]

VWR -- 1 The Virginia Wetlands Report The Virginia Wetlands Report Fall 2005 Vol. 20, No. 2 VMRC Adopts Wetland Mitigation/ Compensation Policy Changes By Tom Barnard When the Virginia Wetlands Act went into effect on July 1, thirty- three years ago, no one had ever heard of compensatory mitigation, wetland

359

Process for the recovery of curium-244 from nuclear waste  

SciTech Connect (OSTI)

A process has been designed for the recovery of curium from purex waste. Curium and americium are separated from the lanthanides by a TALSPEAK extraction process using differential extraction. Equations were derived for the estimation of the economically optimum conditions for the extraction using laboratory batch extraction data. The preparation of feed for the extraction involves the removal of nitric acid from the Purex waste by vaporization under reduced pressure, the leaching of soluble nitrates from the resulting cake, and the oxalate precipitation of a pure lanthanide-actinide fraction. Final separation of the curium from americium is done by ion-exchange. The steps of the process, except ion-exchange, were tested on a laboratory scale and workable conditions were determined.

Posey, J.C.

1980-10-01T23:59:59.000Z

360

Calcine Waste Storage at the Idaho Nuclear Technology and Engineering Center  

SciTech Connect (OSTI)

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

M. D. Staiger

1999-06-01T23:59:59.000Z

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


361

A Novel Fuel/Reactor Cycle to Implement the 300 Years Nuclear Waste Policy Approach - 12377  

SciTech Connect (OSTI)

A thorium-based fuel cycle system can effectively burn the currently accumulated commercial used nuclear fuel and move to a sustainable equilibrium where the actinide levels in the high level waste are low enough to yield a radiotoxicity after 300 years lower than that of the equivalent uranium ore. The second step of the Westinghouse approach to solving the waste 'problem' has been completed. The thorium fuel cycle has indeed the potential of burning the legacy TRU and achieve the waste objective proposed. Initial evaluations have been started for the third step, development and selection of appropriate reactors. Indications are that the probability of show-stoppers is rather remote. It is, therefore, believed that development of the thorium cycle and associated technologies will provide a permanent solution to the waste management. Westinghouse is open to the widest collaboration to make this a reality. (authors)

Carelli, M.D.; Franceschini, F.; Lahoda, E.J. [Westinghouse Electric Company LLC., Cranberry Township, PA (United States); Petrovic, B. [Georgia Institute of Technology, Atlanta, GA (United States)

2012-07-01T23:59:59.000Z

362

A new DOE standard for transuranic waste nuclear safety analysis  

SciTech Connect (OSTI)

The DOE Office of Environmental Management (EM) observed through onsite assessments and a review of site-specific lessons learned that transuranic (TRU) waste operations could benefit from standardization of assumptions and approaches used to analyze hazards and select controls. EM collected and compared safety analysis information from DOE sites, including a comparison of the type of TRU waste accidents evaluated and controls selected, as well as specific Airborne Release Fractions (ARFs), Respirable Fractions (RFs), and Damage Ratios (DRs) assumed in accident analyses. This paper recounts the efforts by the DOE and its contractors to bring consistency to the safety analysis process supporting TRU waste operations through an integrated re-engineering effort. EM embarked on a process to re-engineer and standardize TRU safety analysis activities complex-wide. The effort involved DOE headquarters, field offices, and contractors. Five teams were formed to analyze and develop the necessary technical basis for a DOE Technical Standard. The teams looked at general issues including Safety Basis (SB), drum integrity and inspection criteria, hazard controls and analysis, safety analysis review and approval process, and implementation of hazard controls. (authors)

Triay, I.; Chung, D. [U.S. Department of Energy, Washington, D.C. (United States); Woody, J. [Atlas Consulting, Knoxville, TN (United States); Foppe, T. [Carlsbad Technical Assistance Contractor, Carlsbad, NM (United States); Mewhinney, C. [Sandia National Laboratories, Carlsbad, NM (United States); Jennings, S. [Los Alamos National Laboratories, Carlsbad, NM (United States)

2007-07-01T23:59:59.000Z

363

RADIOACTIVE WASTE MANAGEMENT IN THE CHERNOBYL EXCLUSION ZONE - 25 YEARS SINCE THE CHERNOBYL NUCLEAR POWER PLANT ACCIDENT  

SciTech Connect (OSTI)

Radioactive waste management is an important component of the Chernobyl Nuclear Power Plant accident mitigation and remediation activities of the so-called Chernobyl Exclusion Zone. This article describes the localization and characteristics of the radioactive waste present in the Chernobyl Exclusion Zone and summarizes the pathways and strategy for handling the radioactive waste related problems in Ukraine and the Chernobyl Exclusion Zone, and in particular, the pathways and strategies stipulated by the National Radioactive Waste Management Program. The brief overview of the radioactive waste issues in the ChEZ presented in this article demonstrates that management of radioactive waste resulting from a beyond-designbasis accident at a nuclear power plant becomes the most challenging and the costliest effort during the mitigation and remediation activities. The costs of these activities are so high that the provision of radioactive waste final disposal facilities compliant with existing radiation safety requirements becomes an intolerable burden for the current generation of a single country, Ukraine. The nuclear accident at the Fukushima-1 NPP strongly indicates that accidents at nuclear sites may occur in any, even in a most technologically advanced country, and the Chernobyl experience shows that the scope of the radioactive waste management activities associated with the mitigation of such accidents may exceed the capabilities of a single country. Development of a special international program for broad international cooperation in accident related radioactive waste management activities is required to handle these issues. It would also be reasonable to consider establishment of a dedicated international fund for mitigation of accidents at nuclear sites, specifically, for handling radioactive waste problems in the ChEZ. The experience of handling Chernobyl radioactive waste management issues, including large volumes of radioactive soils and complex structures of fuel containing materials can be fairly useful for the entire world's nuclear community and can help make nuclear energy safer.

Farfan, E.; Jannik, T.

2011-10-01T23:59:59.000Z

364

Proceedings of the 17th Annual North American Waste-to-Energy Conference May 18-20, 2009, Chantilly, Virginia, USA  

E-Print Network [OSTI]

WASTE (MSW) GASIFICATION UNDER VARIOUS PRESSURES AND CO2 CONCENTRATION ATMOSPHERES Eilhann Kwon, Kelly J, New York, NY 10027 ABSTRACT The Municipal Solid Waste (MSW) gasification process is a promisingProceedings of the 17th Annual North American Waste-to-Energy Conference NAWTEC17 May 18-20, 2009

Columbia University

365

Virginia Offshore Wind Development Authority (Virginia) | Department of  

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

Virginia Offshore Wind Development Authority (Virginia) Virginia Offshore Wind Development Authority (Virginia) Virginia Offshore Wind Development Authority (Virginia) < Back Eligibility Commercial Construction Developer Industrial Installer/Contractor Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative Systems Integrator Tribal Government Utility Savings Category Wind Buying & Making Electricity Program Info State Virginia Program Type Industry Recruitment/Support Provider Virginia Offshore Wind Development Authority The Virginia Offshore Wind Development Authority is a public body, established for the purposes of facilitating, coordinating, and supporting the development, either by the Authority or by other qualified entities, of the offshore wind energy industry, offshore wind energy projects, and

366

The utility of system-level RAM analysis and standards for the US nuclear waste management system  

SciTech Connect (OSTI)

The Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is responsible for developing a system to manage spent nuclear fuel and high-level radioactive waste in accordance with the Nuclear Waste Policy Act of 1982 and its subsequent amendments. Pacific Northwest Laboratory (PNL) is assisting OCRWM in its investigation of whether system-level reliability, availability, and maintainability (RAM) requirements are appropriate for the waste management system and, if they are, what appropriate form should be for such requirements. Results and recommendations are presented.

Rod, S.R.; Adickes, M.D.; Paul, B.K.

1992-03-01T23:59:59.000Z

367

Waste component recycle, treatment, and disposal integrated demonstration (WeDID) nuclear weapon dismantlement activities  

SciTech Connect (OSTI)

One of the drivers in the dismantlement and disposal of nuclear weapon components is Envirorunental Protection Agency (EPA) guidelines. The primary regulatory driver for these components is the Resource Conservation Recovery Act (RCRA). Nuclear weapon components are heterogeneous and contain a number of hazardous materials including heavy metals, PCB`S, selfcontained explosives, radioactive materials, gas-filled tubes, etc. The Waste Component Recycle, Treatment, Disposal and Integrated Demonstration (WeDID) is a Department of Energy (DOE) Environmental Restoration and Waste Management (ERWM) sponsored program. It also supports DOE Defense Program (DP) dismantlement activities. The goal of WeDID is to demonstrate the end-to-end disposal process for Sandia National Laboratories designed nuclear weapon components. One of the primary objectives of WeDID is to develop and demonstrate advanced system treatment technologies that will allow DOE to continue dismantlement and disposal unhindered even as environmental regulations become more stringent. WeDID is also demonstrating waste minimization techniques by recycling a significant weight percentage of the bulk/precious metals found in weapon components and by destroying the organic materials typically found in these components. WeDID is concentrating on demonstrating technologies that are regulatory compliant, are cost effective, technologically robust, and are near-term to ensure the support of DOE dismantlement time lines. The waste minimization technologies being demonstrated by WeDID are cross cutting and should be able to support a number of ERWM programs.

Wheelis, W.T.

1993-04-12T23:59:59.000Z

368

Waste component recycle, treatment, and disposal integrated demonstration (WeDID) nuclear weapon dismantlement activities  

SciTech Connect (OSTI)

One of the drivers in the dismantlement and disposal of nuclear weapon components is Envirorunental Protection Agency (EPA) guidelines. The primary regulatory driver for these components is the Resource Conservation Recovery Act (RCRA). Nuclear weapon components are heterogeneous and contain a number of hazardous materials including heavy metals, PCB'S, selfcontained explosives, radioactive materials, gas-filled tubes, etc. The Waste Component Recycle, Treatment, Disposal and Integrated Demonstration (WeDID) is a Department of Energy (DOE) Environmental Restoration and Waste Management (ERWM) sponsored program. It also supports DOE Defense Program (DP) dismantlement activities. The goal of WeDID is to demonstrate the end-to-end disposal process for Sandia National Laboratories designed nuclear weapon components. One of the primary objectives of WeDID is to develop and demonstrate advanced system treatment technologies that will allow DOE to continue dismantlement and disposal unhindered even as environmental regulations become more stringent. WeDID is also demonstrating waste minimization techniques by recycling a significant weight percentage of the bulk/precious metals found in weapon components and by destroying the organic materials typically found in these components. WeDID is concentrating on demonstrating technologies that are regulatory compliant, are cost effective, technologically robust, and are near-term to ensure the support of DOE dismantlement time lines. The waste minimization technologies being demonstrated by WeDID are cross cutting and should be able to support a number of ERWM programs.

Wheelis, W.T.

1993-04-12T23:59:59.000Z

369

Apparatus and method for quantitative assay of generic transuranic wastes from nuclear reactors  

DOE Patents [OSTI]

A combination of passive and active neutron measurements which yields quantitative information about the isotopic composition of transuranic wastes from nuclear power or weapons material manufacture reactors is described. From the measurement of prompt and delayed neutron emission and the incidence of two coincidentally emitted neutrons from induced fission of fissile material in the sample, one can quantify /sup 233/U, /sup 235/U and /sup 239/Pu isotopes in waste samples. Passive coincidence counting, including neutron multiplicity measurement and determination of the overall passive neutron flux additionally enables the separate quantitative evaluation of spontaneous fission isotopes such as /sup 240/Pu, /sup 244/Cm and /sup 252/Cf, and the spontaneous alpha particle emitter /sup 241/Am. These seven isotopes are the most important constituents of wastes from nuclear power reactors and once the mass of each isotope present is determined by the apparatus and method of the instant invention, the overall alpha particle activity can be determined to better than 1 nCi/g from known radioactivity data. Therefore, in addition to the quantitative analysis of the waste sample useful for later reclamation purposes, the alpha particle activity can be determined to decide whether permanent low-level burial is appropriate for the waste sample.

Caldwell, J.T.; Kunz, W.E.; Atencio, J.D.

1982-03-31T23:59:59.000Z

370

Environmental Statements, Availability, Etc., Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs  

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

8679 8679 Thursday June 1, 1995 Part III Department of Energy Environmental Statements, Availability, Etc.; Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs: Notice 28680 Federal Register / Vol. 60, No. 105 / Thursday, June 1, 1995 / Notices DEPARTMENT OF ENERGY Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs AGENCY: Department of Energy. ACTION: Record of decision. SUMMARY: The Department of Energy has issued a Record of Decision on Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs. The Record of Decision includes a Department-wide decision to

371

Assessment of National Nuclear Fuel Cycle for Transmutations of High Level Nuclear Waste  

Science Journals Connector (OSTI)

The advanced fuel cycle initiative (AFCI) has been investigated for the safe processing of the spent nuclear fuels (SNFs), which has focused mainly ... of the SNFs considering the characteristics of the nuclear m...

Taeho Woo

2012-01-01T23:59:59.000Z

372

Nuclear weapons in Ukraine: Hollow threat, wasting asset  

SciTech Connect (OSTI)

When Ukrainian Prime Minister Leonid Kuchma declared on June 3 at a closed session of the Ukrainian parliament (Rada) that it should ratify START I and the May 1992 Lisbon Protocol, but temporarily retain some of the nuclear weapons on Ukrainian territory, concern increased over Kiev`s delay in carrying out its commitments to become a non-nuclear-weapon state. These continuing delays threaten an arms control process codified in START I and START II with far broader security implications. The delays and constant mixed signals from Kiev can be explained two ways, but a closer examination of each of the alternative security options Ukrainians are discussing shows they are built on false premises and would ultimately be counterproductive to genuine Ukrainian security.

Kincade, W.H.

1993-07-01T23:59:59.000Z

373

Decontamination of Nuclear Liquid Wastes Status of CEA and AREVA R and D: Application to Fukushima Waste Waters - 12312  

SciTech Connect (OSTI)

Liquid wastes decontamination processes are mainly based on two techniques: Bulk processes and the so called Cartridges processes. The first technique has been developed for the French nuclear fuel reprocessing industry since the 60's in Marcoule and La Hague. It is a proven and mature technology which has been successfully and quickly implemented by AREVA at Fukushima site for the processing of contaminated waters. The second technique, involving cartridges processes, offers new opportunities for the use of innovative adsorbents. The AREVA process developed for Fukushima and some results obtained on site will be presented as well as laboratory scale results obtained in CEA laboratories. Examples of new adsorbents development for liquid wastes decontamination are also given. A chemical process unit based on co-precipitation technique has been successfully and quickly implemented by AREVA at Fukushima site for the processing of contaminated waters. The asset of this technique is its ability to process large volumes in a continuous mode. Several chemical products can be used to address specific radioelements such as: Cs, Sr, Ru. Its drawback is the production of sludge (about 1% in volume of initial liquid volume). CEA developed strategies to model the co-precipitation phenomena in order to firstly minimize the quantity of added chemical reactants and secondly, minimize the size of co-precipitation units. We are on the way to design compact units that could be mobilized very quickly and efficiently in case of an accidental situation. Addressing the problem of sludge conditioning, cementation appears to be a very attractive solution. Fukushima accident has focused attention on optimizations that should be taken into account in future studies: - To better take account for non-typical aqueous matrixes like seawater; - To enlarge the spectrum of radioelements that can be efficiently processed and especially short lives radioelements that are usually less present in standard effluents resulting from nuclear activities; - To develop reversible solid adsorbents for cartridge-type applications in order to minimize wastes. (authors)

Fournel, B.; Barre, Y.; Lepeytre, C.; Peycelon, H. [CEA Marcoule, DTCD, BP17171, 30207 Bagnols sur Ceze (France); Grandjean, A. [Institut de Chimie Separative de Marcoule, UMR5257 CEA-CNRS-UM2-ENSCM, BP17171, 30207 Bagnols sur Ceze (France); Prevost, T.; Valery, J.F. [AREVA NC, Paris La Defense (France); Shilova, E.; Viel, P. [CEA Saclay, DSM/IRAMIS/SPCSI, 91191 Gif sur Yvette (France)

2012-07-01T23:59:59.000Z

374

Epsilon Metal Waste Form for Immobilization of Noble Metals from Used Nuclear Fuel  

SciTech Connect (OSTI)

Epsilon metal (?-metal), an alloy of Mo, Pd, Rh, Ru, and Tc, is being developed as a waste form to treat and immobilize the undissolved solids and dissolved noble metals from aqueous reprocessing of commercial used nuclear fuel. Epsilon metal is an attractive waste form for several reasons: increased durability relative to borosilicate glass, it can be fabricated without additives (100% waste loading), and in addition it also benefits borosilicate glass waste loading by eliminating noble metals from the glass and thus the processing problems related there insolubility in glass. This work focused on the processing aspects of the epsilon metal waste form development. Epsilon metal is comprised of refractory metals resulting in high reaction temperatures to form the alloy, expected to be 1500 - 2000°C making it a non-trivial phase to fabricate by traditional methods. Three commercially available advanced technologies were identified: spark-plasma sintering, microwave sintering, and hot isostatic pressing, and investigated as potential methods to fabricate this waste form. Results of these investigations are reported and compared in terms of bulk density, phase assemblage (X-ray diffraction and elemental analysis), and microstructure (scanning electron microscopy).

Crum, Jarrod V.; Strachan, Denis M.; Rohatgi, Aashish; Zumhoff, Mac R.

2013-02-01T23:59:59.000Z

375

Epsilon metal waste form for immobilization of noble metals from used nuclear fuel  

Science Journals Connector (OSTI)

Abstract Epsilon metal (?-metal), an alloy of Mo, Pd, Rh, Ru, and Tc, is being developed as a waste form to treat and immobilize the undissolved solids and dissolved noble metals from aqueous reprocessing of commercial used nuclear fuel. Epsilon metal is an attractive waste form for several reasons: increased durability relative to borosilicate glass, it can be fabricated without additives (100% waste loading), and in addition it also benefits borosilicate glass waste loading by eliminating noble metals from the glass, thus the processing problems related to their insolubility in glass. This work focused on the processing aspects of the epsilon metal waste form development. Epsilon metal is comprised of refractory metals resulting in high alloying temperatures, expected to be 1500–2000 °C, making it a non-trivial phase to fabricate by traditional methods. Three commercially available advanced technologies were identified: spark-plasma sintering, microwave sintering, and hot isostatic pressing, and investigated as potential methods to fabricate this waste form. Results of these investigations are reported and compared in terms of bulk density, phase assemblage (X-ray diffraction and elemental analysis), and microstructure (scanning electron microscopy).

Jarrod V. Crum; Denis Strachan; Aashish Rohatgi; Mac Zumhoff

2013-01-01T23:59:59.000Z

376

7 - Assessing and modelling the performance of nuclear waste and associated packages for long-term management  

Science Journals Connector (OSTI)

Abstract: Examples of analytical approaches and methodologies for modelling the behaviour of waste forms and waste package metals in long-term management of spent nuclear fuel (SNF) and high level waste (HLW) are presented. Two cases, long-term geological disposal and interim extended dry storage, are considered. The integrity of the waste package (or canister) that serves as a barrier is dependent upon the performance of construction metals. Corrosion degradation modes of the construction metals are evaluated. The waste behaviour during SNF degradation is also evaluated. In each mode of corrosion or degradation, the associated risk insights are discussed in the system performance of disposal or storage.

T.M. Ahn

2013-01-01T23:59:59.000Z

377

Neutronics analysis for an accelerator-based nuclear waste transmuter  

SciTech Connect (OSTI)

The neutronic analysis for a target/blanket design that is capable of supporting the high level waste stream from 2.5 LWR`s is described. The target consists of a set of solid tungsten and lead plates, cooled by heavy water and surrounded by a lead annulus. The annular blanket, which surrounds the target, consists of a set of AcO{sub 2} slurry bearing tubes, each 3 meters long, surrounded by heavy water moderator. Heat removal from the slurry tubes is by passing the rapidly moving slurry through an external heat exchanger. There are separate regions for long-lived fission product burning. Using the Monte Carlo codes LAHET and MCNP we have optimized the design for a minimum beam current of 62.5 mA of 1.6 GeV protons.

Sailor, W.C.; Beard, C.A.

1993-07-01T23:59:59.000Z

378

A Case for Molecular Recognition in Nuclear Separations: Sulfate Separation from Nuclear Wastes  

Science Journals Connector (OSTI)

In this paper, we present the case for molecular-recognition approaches for sulfate removal from radioactive wastes via the use of anion-sequestering systems selective for sulfate, using either liquid–liquid extraction or crystallization. Potential ...

Bruce A. Moyer; Radu Custelcean; Benjamin P. Hay; Jonathan L. Sessler; Kristin Bowman-James; Victor W. Day; Sung-Ok Kang

2012-11-07T23:59:59.000Z

379

Minimization of formation of wastes from the operation of Czechoslovak nuclear power plants  

SciTech Connect (OSTI)

The problem of generation of liquid radioactive wastes at VVER 440 reactor type nuclear power plants at Jaslovske Bohunice, and Dukovany is discussed. Treatment processes at the NPPs are described. The process during which the operating liquid radioactive wastes emerge is analyzed and the major contributors are identified. The technical approaches to the optimization of the performance of the purification stations that have been implemented at the NPPs with the aim to reduce the generation of radioactive wastes are outlined. The basic results of investigation into the potential of membrane processes are given, as are the results of pilot scale experiments concerned with the use of reverse osmosis in the purification of selected water streams. Attention is also devoted to technical solutions that have been introduced in the design of the Temelin NPP. These solutions are based on the acquired experience and recommendations of foreign experts.

Stepanek, J.; Mohyla, O. [DIAMO, Prague (Czech Republic); Kniz, I.; Zboray, L. [Nuclear Power Plant, Jaslovske Bohunice (Slovakia); Cada, K.; Wild, J. [Nuclear Power Plant, Dukovany (Czech Republic); Seifert, P. [Nuclear Power Plant, Temelin (Czech Republic); Lastovicka, Z. [Energoproject Prague (Czech Republic)

1993-12-31T23:59:59.000Z

380

STRONTIUM AND ACTINIDE SEPARATIONS FROM HIGH LEVEL NUCLEAR WASTE SOLUTIONS USING MONOSODIUM TITANATE 1. SIMULANT TESTING  

SciTech Connect (OSTI)

High-level nuclear waste produced from fuel reprocessing operations at the Savannah River Site (SRS) requires pretreatment to remove {sup 137}Cs, {sup 90}Sr and alpha-emitting radionuclides (i.e., actinides) prior to disposal. Separation processes planned at SRS include caustic side solvent extraction, for {sup 137}Cs removal, and ion exchange/sorption of {sup 90}Sr and alpha-emitting radionuclides with an inorganic material, monosodium titanate (MST). The predominant alpha-emitting radionuclides in the highly alkaline waste solutions include plutonium isotopes {sup 238}Pu, {sup 239}Pu and {sup 240}Pu. This paper provides a summary of data acquired to measure the performance of MST to remove strontium and actinides from simulated waste solutions. These tests evaluated the influence of ionic strength, temperature, solution composition and the oxidation state of plutonium.

HOBBS, D. T.; BARNES, M. J.; PULMANO, R. L.; MARSHALL, K. M.; EDWARDS, T. B.; BRONIKOWSKI, M. G.; FINK, S. D.

2005-04-14T23:59:59.000Z

Note: This page contains sample records for the topic "virginia nuclear waste" from the National Library of EnergyBeta (NLEBeta).
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381

Analysis of heat and mass transfer in sub-seabed disposal of nuclear waste  

SciTech Connect (OSTI)

A mathematical basis is developed for the prediction of thermal and radionuclide transport in marine sediments. The theory is applied to the study of radioactive waste disposal by emplacement, in specially designed containers, well below the sediment/water interface. Numerical results are obtained for a specified model problem through use of two computer programs designed primarily for the analysis of waste disposal problems. One program (MARIAH) provides descriptions of the temperature and velocity fields induced by the presence of a container of thermally active nuclear waste. A second program (IONMIG), which utilizes the results of the thermal analysis, is used to provide predictions for the migration of four representative radionuclides: /sup 239/Pu, /sup 137/Cs, /sup 129/I, and /sup 99/Tc.

Hickox, C. E.; Gartling, D. K.; McVey, D. F.; Russo, A. J.; Nuttall, H. E.

1980-01-01T23:59:59.000Z

382

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

E-Print Network [OSTI]

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

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

2014-01-01T23:59:59.000Z

383

United States Program on Spent Nuclear Fuel and High-Level Radioactive Waste Management  

SciTech Connect (OSTI)

The President signed the Congressional Joint Resolution on July 23, 2002, that designated the Yucca Mountain site for a proposed geologic repository to dispose of the nation's spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The United States (U.S.) Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM) is currently focusing its efforts on submitting a license application to the U.S. Nuclear Regulatory Commission (NRC) in December 2004 for construction of the proposed repository. The legislative framework underpinning the U.S. repository program is the basis for its continuity and success. The repository development program has significantly benefited from international collaborations with other nations in the Americas.

Stewart, L.

2004-10-03T23:59:59.000Z

384

Use of radiometric emanation method in the characterization of anthropogenic glass analogue for vitrification of nuclear waste  

Science Journals Connector (OSTI)

Anthropogenic analogues can serve as a valuable source of information about long-term behaviour of materials to be used in the nuclear waste repositories. The use of anthropogenic analogues can ... cement, concre...

V. Balek; Š. Palágyi; V. Havlová

2013-03-01T23:59:59.000Z

385

What are Spent Nuclear Fuel and High-Level Radioactive Waste ?  

SciTech Connect (OSTI)

Spent nuclear fuel and high-level radioactive waste are materials from nuclear power plants and government defense programs. These materials contain highly radioactive elements, such as cesium, strontium, technetium, and neptunium. Some of these elements will remain radioactive for a few years, while others will be radioactive for millions of years. Exposure to such radioactive materials can cause human health problems. Scientists worldwide agree that the safest way to manage these materials is to dispose of them deep underground in what is called a geologic repository.

DOE

2002-12-01T23:59:59.000Z

386

Nuclear Waste Disposal and Strategies for Predicting Long-Term Performance of Material  

SciTech Connect (OSTI)

Ceramics have been an important part of the nuclear community for many years. On December 2, 1942, an historic event occurred under the West Stands of Stagg Field, at the University of Chicago. Man initiated his first self-sustaining nuclear chain reaction and controlled it. The impact of this event on civilization is considered by many as monumental and compared by some to other significant events in history, such as the invention of the steam engine and the manufacturing of the first automobile. Making this event possible and the successful operation of this first man-made nuclear reactor, was the use of forty tons of UO2. The use of natural or enriched UO2 is still used today as a nuclear fuel in many nuclear power plants operating world-wide. Other ceramic materials, such as 238Pu, are used for other important purposes, such as ceramic fuels for space exploration to provide electrical power to operate instruments on board spacecrafts. Radioisotopic Thermoelectric Generators (RTGs) are used to supply electrical power and consist of a nuclear heat source and converter to transform heat energy from radioactive decay into electrical power, thus providing reliable and relatively uniform power over the very long lifetime of a mission. These sources have been used in the Galileo spacecraft orbiting Jupiter and for scientific investigations of Saturn with the Cassini spacecraft. Still another very important series of applications using the unique properties of ceramics in the nuclear field, are as immobilization matrices for management of some of the most hazardous wastes known to man. For example, in long-term management of radioactive and hazardous wastes, glass matrices are currently in production immobilizing high-level radioactive materials, and cementious forms have also been produced to incorporate low level wastes. Also, as part of nuclear disarmament activities, assemblages of crystalline phases are being developed for immobilizing weapons grade plutonium, to not only produce environmentally friendly products, but also forms that are proliferation resistant. All of these waste forms as well as others, are designed to take advantage of the unique properties of the ceramic systems.

Wicks, G.G.

2001-03-28T23:59:59.000Z

387

Using Single-Camera 3-D Imaging to Guide Material Handling Robots in a Nuclear Waste Package Closure System  

SciTech Connect (OSTI)

Nuclear reactors for generating energy and conducting research have been in operation for more than 50 years, and spent nuclear fuel and associated high-level waste have accumulated in temporary storage. Preparing this spent fuel and nuclear waste for safe and permanent storage in a geological repository involves developing a robotic packaging system—a system that can accommodate waste packages of various sizes and high levels of nuclear radiation. During repository operation, commercial and government-owned spent nuclear fuel and high-level waste will be loaded into casks and shipped to the repository, where these materials will be transferred from the casks into a waste package, sealed, and placed into an underground facility. The waste packages range from 12 to 20 feet in height and four and a half to seven feet in diameter. Closure operations include sealing the waste package and all its associated functions, such as welding lids onto the container, filling the inner container with an inert gas, performing nondestructive examinations on welds, and conducting stress mitigation. The Idaho National Laboratory is designing and constructing a prototype Waste Package Closure System (WPCS). Control of the automated material handling is an important part of the overall design. Waste package lids, welding equipment, and other tools must be moved in and around the closure cell during the closure process. These objects are typically moved from tool racks to a specific position on the waste package to perform a specific function. Periodically, these objects are moved from a tool rack or the waste package to the adjacent glovebox for repair or maintenance. Locating and attaching to these objects with the remote handling system, a gantry robot, in a loosely fixtured environment is necessary for the operation of the closure cell. Reliably directing the remote handling system to pick and place the closure cell equipment within the cell is the major challenge.

Rodney M. Shurtliff

2005-09-01T23:59:59.000Z

388

Long-Term Environmental Monitoring of an Operating Deep Geologic Nuclear Waste Repository  

SciTech Connect (OSTI)

In the present energy dilemma in which we find ourselves, the magnitude of humanity's energy needs requires that we embrace a multitude of various energy sources and applications. Nuclear energy must be a major portion of the distribution. One often-cited strategic hurdle to the commercial production of nuclear energy is the apparent lack of an acceptable nuclear waste repository. This issue has been quietly addressed at the U. S. Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP; see http://www.wipp.energy.gov), the closest population center of significant size being Carlsbad, New Mexico. WIPP has been operating for about nine years, disposing of over 250,000 drum-equivalents of nuclear waste. From the standpoint of addressing operational and environmental risk, as well as public fear, WIPP has had extensive human health and environmental monitoring. The Carlsbad Environmental Monitoring and Research Center is in the Institute for Energy and the Environment, in the College of Engineering at New Mexico State University. Located in Carlsbad, NM, CEMRC has been the independent monitoring facility for the area around WIPP from 1993 to the present, i.e., from six years before disposal operations began to nine years of waste disposal operations (www.cemcr.org). Based on the radiological analyses of monitoring samples completed to date for area residents and site workers, and for selected aerosols, soils, sediments, drinking water and surface waters, there is no evidence of increases in radiological contaminants in the region of WIPP that could be attributed to releases from WIPP. Levels of radiological and non-radiological analytes measured since operations began in 1999 have been within the range of baseline levels measured previously, and are within the ranges measured by other entities at the State and local levels since well before disposal phase operations began in 1999. (authors)

Conca, J.; Kirchner, Th.; Monk, J.; Sage, S. [Carlsbad Environmental Monitoring and Research Center, IEE NMSU, 1400 University Drive, Carlsbad, NM (United States)

2008-07-01T23:59:59.000Z

389

STABILIZING GLASS BONDED WASTE FORMS CONTAINING FISSION PRODUCTS SEPARATED FROM SPENT NUCLEAR FUEL  

SciTech Connect (OSTI)

A model has been developed to represent the stresses developed when a molten, glass-bonded brittle cylinder (used to store nuclear material) is cooled from high temperature to working temperature. Large diameter solid cylinders are formed by heating glass or glass-bonded mixtures (mixed with nuclear waste) to high temperature (915°C). These cylinders must be cooled as the final step in preparing them for storage. Fast cooling time is desirable for production; however, if cooling is too fast, the cylinder can crack into many pieces. To demonstrate the capability of the model, cooling rate cracking data were obtained on small diameter (7.8 cm diameter) glass-only cylinders. The model and experimental data were combined to determine the critical cooling rate which separates the non-cracking stable glass region from the cracked, non-stable glass regime. Although the data have been obtained so far only on small glass-only cylinders, the data and model were used to extrapolate the critical-cooling rates for large diameter ceramic waste form (CWF) cylinders. The extrapolation estimates long term cooling requirements. While a 52-cm diameter cylinder (EBR-II-waste size) can be cooled to 100°C in 70 hours without cracking, a 181.5-cm diameter cylinder (LWR waste size) requires 35 days to cool to 100°C. These cooling times are long enough that verification of these estimates are required so additional experiments are planned on both glass only and CWF material.

Kenneth J. Bateman; Charles W. Solbrig

2008-07-01T23:59:59.000Z

390

Model evaluation of geochemically induced swelling/shrinkage in argillaceous formations for nuclear waste disposal  

Science Journals Connector (OSTI)

Abstract Argillaceous formations are being considered as host rocks for geologic disposal of nuclear waste in a number of countries. One advantage of emplacing nuclear waste in such formations is the potential self-sealing capability of clay due to swelling, which is of particular importance for the sealing and healing of disturbed rock zones (DRZ). It is therefore necessary to understand and be able to predict the changes in swelling properties within clay rock near the waste-emplacement tunnel. In this paper, considering that the clay rock formation is mostly under saturated conditions and the swelling property changes are mostly due to geochemical changes, we propose a modeling method that links a THC simulator with a swelling module that is based on diffuse double layer theory. Simulations were conducted to evaluate the geochemically induced changes in the swelling properties of the clay rock. Our findings are as follows: (1) geochemically induced swelling/shrinkage occurs exclusively in the EBS–clay formation interface, within a few meters from the waste-emplacement tunnels; (2) swelling/shrinkage-induced porosity changes are generally much smaller than those caused by mineral precipitation/dissolution processes; (3) geochemically induced swelling/shrinkage of the host clay rock is affected by variations in the pore water chemistry, exchangeable cations, and smectite abundance. Neglecting any of these three factors might lead to a miscalculation of the geochemically induced swelling pressure.

Liange Zheng; Jonny Rutqvist; Hui-Hai Liu; Jens T. Birkholzer; Eric Sonnenthal

2014-01-01T23:59:59.000Z

391

Virginia Electric Utility Regulation Act (Virginia) | Department of Energy  

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

Electric Utility Regulation Act (Virginia) Electric Utility Regulation Act (Virginia) Virginia Electric Utility Regulation Act (Virginia) < Back Eligibility Commercial Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Systems Integrator Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Virginia Program Type Safety and Operational Guidelines Provider Virginia State Corporation Commission The Virginia Electric Utility Regulation Act constitutes the main legislation in Virginia that pertains to the regulation of the state's electric utilities. The Act directs the State Corporation Commission to construct regulations for electric utilities, and contains information on

392

UNIVERSITY OF VIRGINIA ENGINEERING FOUNDATION  

E-Print Network [OSTI]

UNIVERSITY OF VIRGINIA ENGINEERING FOUNDATION I __________________________________________ pledge to contribute or make possible a gift to the University of Virginia Engineering Foundation for the University: ________________________________________________________ ________________________________________________________________ Please make check payable to the Engineering Foundation and return to the University of Virginia

Acton, Scott

393

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

Science Journals Connector (OSTI)

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

E-an Zen

1980-01-01T23:59:59.000Z

394

MODELING SOLIDIFICATION-INDUCED STRESSES IN CERAMIC WASTE FORMS CONTAINING NUCLEAR WASTES  

SciTech Connect (OSTI)

The goal of this work is to produce a ceramic waste form (CWF) that permanently occludes radioactive waste. This is accomplished by absorbing radioactive salts into zeolite, mixing with glass frit, heating to a molten state 915 C to form a sodalite glass matrix, and solidifying for long-term storage. Less long term leaching is expected if the solidifying cooling rate doesn’t cause cracking. In addition to thermal stress, this paper proposes that a stress is formed during solidification which is very large for fast cooling rates during solidification and can cause severe cracking. A solidifying glass or ceramic cylinder forms a dome on the cylinder top end. The temperature distribution at the time of solidification causes the stress and the dome. The dome height, “the length deficit,” produces an axial stress when the solid returns to room temperature with the inherent outer region in compression, the inner in tension. Large tensions will cause cracking of the specimen. The temperature deficit, derived by dividing the length deficit by the coefficient of thermal expansion, allows solidification stress theory to be extended to the circumferential stress. This paper derives the solidification stress theory, gives examples, explains how to induce beneficial stresses, and compares theory to experimental data.

Charles W. Solbrig; Kenneth J. Bateman

2010-11-01T23:59:59.000Z

395

Memorandum of Understanding between the Department of Energy of the United States of America and the National Company of Radioactive Waste of Spain Concerning Cooperation in the Field of Used Nuclear Fuel and Radioactive Waste Management  

Broader source: Energy.gov [DOE]

Memorandum of Understanding between the Department of Energy of the United States of America and the National Company of Radioactive Waste of Spain Concerning Cooperation in the Field of Used Nuclear Fuel and Radioactive Waste Management

396

Development of an Integrated Raman and Turbidity Fiber Optic Sensor for the In-Situ Analysis of High Level Nuclear Waste - 13532  

SciTech Connect (OSTI)

Stored nuclear waste must be retrieved from storage, treated, separated into low- and high-level waste streams, and finally put into a disposal form that effectively encapsulates the waste and isolates it from the environment for a long period of time. Before waste retrieval can be done, waste composition needs to be characterized so that proper safety precautions can be implemented during the retrieval process. In addition, there is a need for active monitoring of the dynamic chemistry of the waste during storage since the waste composition can become highly corrosive. This work describes the development of a novel, integrated fiber optic Raman and light scattering probe for in situ use in nuclear waste solutions. The dual Raman and turbidity sensor provides simultaneous chemical identification of nuclear waste as well as information concerning the suspended particles in the waste using a common laser excitation source. (authors)

Gasbarro, Christina; Bello, Job [EIC Laboratories, Inc., 111 Downey St., Norwood, MA, 02062 (United States)] [EIC Laboratories, Inc., 111 Downey St., Norwood, MA, 02062 (United States); Bryan, Samuel; Lines, Amanda; Levitskaia, Tatiana [Pacific Northwest National Laboratory, PO Box 999, Richland, WA, 99352 (United States)] [Pacific Northwest National Laboratory, PO Box 999, Richland, WA, 99352 (United States)

2013-07-01T23:59:59.000Z

397

A Characteristics-Based Approach to Radioactive Waste Classification in Advanced Nuclear Fuel Cycles  

E-Print Network [OSTI]

on   the   impact   of   waste   heat   load   on   waste  involve   coupling   waste   heat   load   with   metrics  radionuclides   in   the   waste,   heat   generated   by  

Djokic, Denia

2013-01-01T23:59:59.000Z

398

Modeling Building Thermal Response to HVAC Zoning Virginia Smith  

E-Print Network [OSTI]

Modeling Building Thermal Response to HVAC Zoning Virginia Smith Department of Computer Science HVAC systems account for 38% of building energy usage. Studies have indicated at least 5-15% waste due to unoccu- pied spaces being conditioned. Our goal is to minimize this waste by retrofitting HVAC systems

Whitehouse, Kamin

399

Scenic Rivers Act (Virginia)  

Broader source: Energy.gov [DOE]

Virginia Scenic Rivers Program’s intent is to identify, designate and help protect rivers and streams that possess outstanding scenic, recreational, historic and natural characteristics of...

400

Clean Coal Projects (Virginia)  

Broader source: Energy.gov [DOE]

This legislation directs the Virginia Air Pollution Control Board to facilitate the construction and implementation of clean coal projects by expediting the permitting process for such projects.

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


401

Radiation Control (Virginia)  

Broader source: Energy.gov [DOE]

The Department of Health is responsible for regulating radiation and radioactive materials in the Commonwealth of Virginia. Although the Department's Radiation Control Program primarily focuses on...

402

Virginia - SEP | Department of Energy  

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

- SEP Virginia - SEP Virginia's Multi-state Model for Catalyzing the National Home Energy Retrofit Market Location: Charlottesville, Richmond, Arlington County, City of...

403

Radioactive waste isolation in salt: peer review of Office of Nuclear Waste Isolation's Socioeconomic Program Plan  

SciTech Connect (OSTI)

The ONWI Socioeconomic Program Plan spells out DOE's approach to analyzing the socioeconomic impacts from siting, constructing, and operating radioactive waste repositories and discusses mitigation strategies. The peer review indicated the following modifications should be made to the Plan: encourage active public participation in the decision-making processes leading to repository site selection; clearly define mechanisms for incorporating the concerns of local residents, state and local governments, and other potentially interested parties into the early stages of the site selection process; place significantly greater emphasis on using primary socioeconomic data during the site selection process, reversing the current overemphasis on secondary data collection, description of socioeconomic conditions at potential locations, and development of analytical methodologies; recognize that mitigation mechanisms other than compensation and incentives may be effective; as soon as potential sites are identified, the US Department of Energy (DOE) should begin discussing impact mitigation agreements with local officials and other interested parties; and comply fully with the pertinent provisions of NWPA.

Winter, R.; Fenster, D.; O'Hare, M.; Zillman, D.; Harrison, W.; Tisue, M.

1984-02-01T23:59:59.000Z

404

Nuclear waste transmutation performance assessment of an accelerator driven subcritical reactor for waste transmutation (ADS-NWT)  

Science Journals Connector (OSTI)

Abstract As a concept of lead–bismuth cooled accelerator driven sub-critical reactor, ADS-NWT was proposed for nuclear waste transmutation by FDS Team. In this paper, preliminary transmutation performance assessment on ADS-NWT was performed by using metallic dispersion fuel and metal alloy fuel. The studies were committed to improving the Discharge Transmutation Support Ratio (DTSR) under three key design constraints. Subject to the design constraints on the effective multiplication factor, the peak linear power and the peak fast neutron fluence, the design studies had been performed for ADS-NWT blanket. From these studies, the results showed that the maximum DTSR was primarily related to the MA/Pu ratio, the peak fast neutron fluence and fuel design under imposed design constraints. The maximum DTSR could be ?47 in one refueling cycle time when the thermal power was fixed to 1000 MW and the effective multiplication factor was 0.98 based on the specific design.

Zhong Chen; Yican Wu; Baoxin Yuan; Dongmei Pan

2015-01-01T23:59:59.000Z

405

West Virginia University 1 School of Pharmacy  

E-Print Network [OSTI]

, the pharmaceutical industry, long-term care, nuclear pharmacy, and home health-care organizations. Pharmacists.S., Ph.D. in Pharmaceutical and Pharmacological Sciences Introduction The mission of the West Virginia by educating students and practitioners to provide optimal pharmaceutical care; conducting vital research

Mohaghegh, Shahab

406

EIA - State Nuclear Profiles  

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

Virginia profile Virginia profile Virginia total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 3,501 14.5 26,572 36.4 Coal 5,868 24.3 25,459 34.9 Hydro and Pumped Storage 4,107 17.0 10 * Natural Gas 7,581 31.4 16,999 23.3 Other 1 - - 414 0.6 Other Renewable1 621 2.6 2,220 3.0 Petroleum 2,432 10.1 1,293 1.8 Total 24,109 100.0 72,966 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable. * = Absolute percentage less than 0.05.

407

EIA - State Nuclear Profiles  

Gasoline and Diesel Fuel Update (EIA)

Virginia profile Virginia profile Virginia total electric power industry, summer capacity and net generation, by energy source, 2010 Primary energy source Summer capacity (mw) Share of State total (percent) Net generation (thousand mwh) Share of State total (percent) Nuclear 3,501 14.5 26,572 36.4 Coal 5,868 24.3 25,459 34.9 Hydro and Pumped Storage 4,107 17.0 10 * Natural Gas 7,581 31.4 16,999 23.3 Other 1 - - 414 0.6 Other Renewable1 621 2.6 2,220 3.0 Petroleum 2,432 10.1 1,293 1.8 Total 24,109 100.0 72,966 100.0 1Municipal Solid Waste net generation is allocated according to the biogenic and non-biogenic components of the fuel; however, all Municipal Solid Waste summer capacity is classified as Renewable. * = Absolute percentage less than 0.05.

408

Evaluation of Options for Permanent Geologic Disposal of Spent NuclearFuel and High-Level Radioactive Waste  

Broader source: Energy.gov [DOE]

[In Support of a Comprehensive National Nuclear Fuel Cycle Strategy, Volumes I and II (Appendices)] This study provides a technical basis for informing 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 geologic isolation.

409

The Virginia Wetlands Report  

E-Print Network [OSTI]

VWR -- 1 The Virginia Wetlands Report The Virginia Wetlands Report Summer 2000 Vol. 15, No. 2 Department of Environmental Quality (DEQ) Implementing Nontidal Wetlands Protection Mandate Ellen Gilinsky wetland resources, but which occur outside of federal regulation. The General Assembly was motivated

410

The Virginia Wetlands Report  

E-Print Network [OSTI]

The Virginia Wetlands Report Summer 1997 Vol. 12, No. 2The Virginia Wetlands Report Wetlands mitigation banking is a relatively new tool for wetlands managers. It is finding increasing application in the struggle to achieve a "no net loss" goal for our remaining wetland resources. The concept of creating

411

The Virginia Wetlands Report  

E-Print Network [OSTI]

The Virginia Wetlands Report Fall 1997 Vol. 12, No. 3The Virginia Wetlands Report Almost everyone their actions. It is this com- mon sense notion which is motivating a new Wetlands Initiative under the auspices of the Chesapeake Bay Program Wetlands Workgroup. State and federal wet- lands program man- agers are working

412

The Virginia Wetlands Report  

E-Print Network [OSTI]

VWR -- 1 The Virginia Wetlands Report The Virginia Wetlands Report Fall 2001 Vol. 16, No. 3 A GIS Approach for Targeting Potential Wetlands Mitigation or Restoration Sites By Marcia Berman and Tamia vegeta- tion, islands, and wetlands. Most activi- ties enhance habitat for living resources, but also

413

The Virginia Wetlands Report  

E-Print Network [OSTI]

The Virginia Wetlands Report Continued on page 2 Spring 1996 Vol. 11, No. 2The Virginia Wetlands Report Completely Updated The Wetlands Program of the Vir- ginia Institute of Marine Science has completed its update of the Vir- ginia Wetlands Management Hand- book, and with the aid of the Marine

414

The Virginia Wetlands Report  

E-Print Network [OSTI]

VWR 1 The Virginia Wetlands Report The Virginia Wetlands Report Summer 1999 Vol. 14, No. 2 Historic Wetland Loss in the Elizabeth River Walter I. Priest, III Introduction Since earliest colonial consumed many of the natural resources of the river basin, including its wetlands, forests, water quality

415

The Virginia Wetlands Report  

E-Print Network [OSTI]

VWR -- 1 The Virginia Wetlands Report The Virginia Wetlands Report Spring 2005 Vol. 20, No. 1 Annual Summary of Permitted Tidal Wetland Impacts - 2004 By Karen Duhring The Wetlands Program has main impact areas based on a site visit and information provided in the permit documents. The Wetlands Program

416

The Virginia Wetlands Report  

E-Print Network [OSTI]

VWR -- 1 The Virginia Wetlands Report The Virginia Wetlands Report Winter/Spring 2001 Vol. 16, No. 1 The VIMS Teaching Marsh: A Tidal Wetland Restoration and Education Project Karen Duhring Purpose wetlands education opportunities, including field lessons. Due to the vari- ety and geographic distribution

417

Scale-up considerations relevant to experimental studies of nuclear waste-package behavior  

SciTech Connect (OSTI)

Results from a study that investigated whether testing large-scale nuclear waste-package assemblages was technically warranted are reported. It was recognized that the majority of the investigations for predicting waste-package performance to date have relied primarily on laboratory-scale experimentation. However, methods for the successful extrapolation of the results from such experiments, both geometrically and over time, to actual repository conditions have not been well defined. Because a well-developed scaling technology exists in the chemical-engineering discipline, it was presupposed that much of this technology could be applicable to the prediction of waste-package performance. A review of existing literature documented numerous examples where a consideration of scaling technology was important. It was concluded that much of the existing scale-up technology is applicable to the prediction of waste-package performance for both size and time extrapolations and that conducting scale-up studies may be technically merited. However, the applicability for investigating the complex chemical interactions needs further development. It was recognized that the complexity of the system, and the long time periods involved, renders a completely theoretical approach to performance prediction almost hopeless. However, a theoretical and experimental study was defined for investigating heat and fluid flow. It was concluded that conducting scale-up modeling and experimentation for waste-package performance predictions is possible using existing technology. A sequential series of scaling studies, both theoretical and experimental, will be required to formulate size and time extrapolations of waste-package performance.

Coles, D.G.; Peters, R.D.

1986-04-01T23:59:59.000Z

418

Technologies for destruction of long-lived radionuclides in high-level nuclear waste - overview and requirements  

SciTech Connect (OSTI)

A major issue surrounding current nuclear power generation is the management and disposal of long-lived, high-level waste (HLW). The planned and scientifically acceptable destination for this waste is in deep underground, geologically stable, repositories. However, public concerns surrounding such disposal of long-lived nuclear wastes and other issues such as proliferation and safety negatively affect the potential role that nuclear power can play in meeting current and future national energy needs. This paper and this topical session on nuclear waste minimization, management, and remediation focus on two nuclear systems and their associated technologies that have the potential to address concerns surrounding long-lived radionuclides in HLW. Both systems offer technology applicable to HLW from current light water reactors (LWRs). In addition, these systems represent advanced nuclear power concepts that have important features associated with integrated management of wastes long-term fuel supplies, and enhanced safety. The first system is the integral fast reactor (IFR) concept. This system incorporates a metal-fueled fast reactor coupled with chemical separations based on pyroprocessing to produce power while burning long-lived actinide waste. The IFR applications include the burning of actinides from current LWR spent fuel and energy production in a breeder environment. The second concept, accelerator transmutation of waste (ATW), is based on an accelerator-induced intense source of thermal neutrons and is aimed at the destruction of long-lived actinides and fission products. This concept can be applied to long-lived radionuclides in spent-fuel HLW as well as a future fission power source built around use of natural thorium or uranium as fuels coupled with concurrent waste destruction.

Arthur, E.D. (Los Alamos National Lab., NM (United States))

1993-01-01T23:59:59.000Z

419

Improving the Estimates of Waste from the Recycling of Used Nuclear Fuel - 13410  

SciTech Connect (OSTI)

Estimates are presented of wastes arising from the reprocessing of 50 GWD/tonne, 5 year and 50 year cooled used nuclear fuel (UNF) from Light Water Reactors (LWRs), using the 'NUEX' solvent extraction process. NUEX is a fourth generation aqueous based reprocessing system, comprising shearing and dissolution in nitric acid of the UNF, separation of uranium and mixed uranium-plutonium using solvent extraction in a development of the PUREX process using tri-n-butyl phosphate in a kerosene diluent, purification of the plutonium and uranium-plutonium products, and conversion of them to uranium trioxide and mixed uranium-plutonium dioxides respectively. These products are suitable for use as new LWR uranium oxide and mixed oxide fuel, respectively. Each unit process is described and the wastes that it produces are identified and quantified. Quantification of the process wastes was achieved by use of a detailed process model developed using the Aspen Custom Modeler suite of software and based on both first principles equilibrium and rate data, plus practical experience and data from the industrial scale Thermal Oxide Reprocessing Plant (THORP) at the Sellafield nuclear site in the United Kingdom. By feeding this model with the known concentrations of all species in the incoming UNF, the species and their concentrations in all product and waste streams were produced as the output. By using these data, along with a defined set of assumptions, including regulatory requirements, it was possible to calculate the waste forms, their radioactivities, volumes and quantities. Quantification of secondary wastes, such as plant maintenance, housekeeping and clean-up wastes, was achieved by reviewing actual operating experience from THORP during its hot operation from 1994 to the present time. This work was carried out under a contract from the United States Department of Energy (DOE) and, so as to enable DOE to make valid comparisons with other similar work, a number of assumptions were agreed. These include an assumed reprocessing capacity of 800 tonnes per year, the requirement to remove as waste forms the volatile fission products carbon-14, iodine-129, krypton-85, tritium and ruthenium-106, the restriction of discharge of any water from the facility unless it meets US Environmental Protection Agency drinking water standards, no intentional blending of wastes to lower their classification, and the requirement for the recovered uranium to be sufficiently free from fission products and neutron-absorbing species to allow it to be re-enriched and recycled as nuclear fuel. The results from this work showed that over 99.9% of the radioactivity in the UNF can be concentrated via reprocessing into a fission-product-containing vitrified product, bottles of compressed krypton storage and a cement grout containing the tritium, that together have a volume of only about one eighth the volume of the original UNF. The other waste forms have larger volumes than the original UNF but contain only the remaining 0.1% of the radioactivity. (authors)

Phillips, Chris; Willis, William; Carter, Robert [EnergySolutions Federal EPC., 2345 Stevens Drive, Richland, WA, 99354 (United States)] [EnergySolutions Federal EPC., 2345 Stevens Drive, Richland, WA, 99354 (United States); Baker, Stephen [UK National Nuclear Laboratory, Warrington, Cheshire (United Kingdom)] [UK National Nuclear Laboratory, Warrington, Cheshire (United Kingdom)

2013-07-01T23:59:59.000Z

420

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

SciTech Connect (OSTI)

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

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

2003-02-26T23:59:59.000Z

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


421

Waste Classification based on Waste Form Heat Generation in Advanced Nuclear Fuel Cycles Using the Fuel-Cycle Integration and Tradeoffs (FIT) Model - 13413  

SciTech Connect (OSTI)

This study explores the impact of wastes generated from potential future fuel cycles and the issues presented by classifying these under current classification criteria, and discusses the possibility of a comprehensive and consistent characteristics-based classification framework based on new waste streams created from advanced fuel cycles. A static mass flow model, Fuel-Cycle Integration and Tradeoffs (FIT), was used to calculate the composition of waste streams resulting from different nuclear fuel cycle choices. This analysis focuses on the impact of waste form heat load on waste classification practices, although classifying by metrics of radiotoxicity, mass, and volume is also possible. The value of separation of heat-generating fission products and actinides in different fuel cycles is discussed. It was shown that the benefits of reducing the short-term fission-product heat load of waste destined for geologic disposal are neglected under the current source-based radioactive waste classification system, and that it is useful to classify waste streams based on how favorable the impact of interim storage is in increasing repository capacity. (authors)

Djokic, Denia [Department of Nuclear Engineering, University of California - Berkeley, 4149 Etcheverry Hall, Berkeley, CA 94720-1730 (United States)] [Department of Nuclear Engineering, University of California - Berkeley, 4149 Etcheverry Hall, Berkeley, CA 94720-1730 (United States); Piet, Steven J.; Pincock, Layne F.; Soelberg, Nick R. [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)] [Idaho National Laboratory - INL, 2525 North Fremont Avenue, Idaho Falls, ID 83415 (United States)

2013-07-01T23:59:59.000Z

422

Rock mass modification around a nuclear waste repository in welded tuff  

SciTech Connect (OSTI)

This report presents the results of numerical analyses to estimate the extent of rock mass modification resulting from the presence of a High Level Waste (HLW) repository. Changes in rock mass considered are stresses and joint deformations resulting from disposal room excavation and thermal efffects induced by the heat generated by nuclear waste. rock properties and site conditions are taken from the Site Characterization Plan Conceptual Design Report for the potential repository site at Yucca Mountain, Nevada. Analyses were conducted using boundary element and distinct element methods. Room-scale models and repository-scale models were investigated for up to 500 years after waste emplacement. Results of room-scale analyses based on the thermoelastic boundary element model indicate that a zone of modified rock develops around the disposal rooms for both vertical and horizontal waste emplacement. This zone is estimated to extend a distance of roughly two room diameters from the room surface. Results from the repository-scale model, which are based on the thermoelastic boundary element model and the distinct element model, indicate a zone with modified rock mass properties starting approximately 100 m above and below the repository, with a thickness of approximately 200 m above and 150 m below the repository. Slip-prone subhorizontal features are shown to have a substantial effect on rock mass response. The estimates of rock mass modification reflect uncertainties and simplifying assumptions in the models. 32 refs., 57 figs., 1 tab.

Mack, M.G.; Brandshaug, T.; Brady, B.H.

1989-08-01T23:59:59.000Z

423

Simulation of Self-Irradiation of High-Sodium Content Nuclear Waste Glasses  

SciTech Connect (OSTI)

Alkali-borosilicate glasses are widely used in nuclear industry as a matrix for immobilisation of hazardous radioactive wastes. Durability or corrosion resistance of these glasses is one of key parameters in waste storage and disposal safety. It is influenced by many factors such as composition of glass and surrounding media, temperature, time and so on. As these glasses contain radioactive elements most of their properties including corrosion resistance are also impacted by self-irradiation. The effect of external gamma-irradiation on the short-term (up to 27 days) dissolution of waste borosilicate glasses at moderate temperatures (30 deg. to 60 deg. C) was studied. The glasses studied were Magnox Waste glass used for immobilisation of HLW in UK, and K-26 glass used in Russia for ILW immobilisation. Glass samples were irradiated under {gamma}-source (Co-60) up to doses 1 and 11 MGy. Normalised rates of elemental release and activation energy of release were measured for Na, Li, Ca, Mg, B, Si and Mo before and after irradiation. Irradiation up to 1 MGy results in increase of leaching rate of almost all elements from both MW and K-26 with the exception of Na release from MW glass. Further irradiation up to a dose of 11 MGy leads to the decrease of elemental release rates to nearly initial value. Another effect of irradiation is increase of activation energies of elemental release. (authors)

Pankov, Alexey S.; Ojovan, Michael I. [Immobilisation Science Laboratory, Department of Engineering Materials, University of Sheffield, Sir Robert Hadfield Building, Mappin Street, Sheffield, S1 3JD (United Kingdom); Batyukhnova, Olga G. [International Education Training Centre, SUE SIA 'Radon', The 7-th Rostovsky Lane 2/14, Moscow, 119121 (Russian Federation); Lee, William E. [Department of Materials, Imperial College London, South Kensington Campus, Exhibition Road, London, SW7 2AZ (United Kingdom)

2007-07-01T23:59:59.000Z

424

Evaluation of nuclear facility decommissioning projects: Summary status report: Three Mile Island Unit 2. Radioactive waste and laundry shipments  

SciTech Connect (OSTI)

This document summarizes information concerning radioactive waste and laundry shipments from the Three Mile Island Nuclear Station Unit 2 to radioactive waste disposal sites and to protective clothing decontamination facilities (laundries) since the loss of coolant accident experienced on March 28, 1979. Data were collected from radioactive shipment records, summarized, and placed in a computerized data information retrieval/manipulation system which permits extraction of specific information. This report covers the period of April 9, 1979 through April 19, 1987. Included in this report are: waste disposal site locations, dose rates, curie content, waste description, container type and number, volumes and weights. This information is presented in two major categories: protective clothing (laundry) and radioactive waste. Each of the waste shipment reports is in chronological order.

Doerge, D. H.; Haffner, D. R.

1988-06-01T23:59:59.000Z

425

Supercritical Fluid Extraction of Radionuclides - A Green Technology for Nuclear Waste Management  

SciTech Connect (OSTI)

Supercritical fluid carbon dioxide (SF-CO2) is capable of extracting radionuclides including cesium, strontium, uranium, plutonium and lanthanides directly from liquid and solid samples with proper complexing agents. Of particular interest is the ability of SF-CO2 to dissolve uranium dioxide directly using a CO2-soluble tri-nbutylphosphate- nitric acid (TBP-HNO3) extractant to form a highly soluble UO2(NO3)2(TBP)2 complex that can be transported and separated from Cs, Sr, and other transition metals. This method can also dissolve plutonium dioxide in SF-CO2. The SF-CO2 extraction technology offers several advantages over conventional solvent-based methods including ability to extract radionuclides directly from solids, easy separation of solutes from CO2, and minimization of liquid waste generation. Potential applications of the SF-CO2 extraction technology for nuclear waste treatment and for reprocessing of spent nuclear fuels will be discussed. Information on current demonstrations of the SF-CO2 technology by nuclear companies and research organizations in different countries will be reviewed.

Wai, Chien M.

2003-09-10T23:59:59.000Z

426

High performance gamma measurements of equipment retrieved from Hanford high-level nuclear waste tanks  

SciTech Connect (OSTI)

The cleanup of high level defense nuclear waste at the Hanford site presents several progressive challenges. Among these is the removal and disposal of various components from buried active waste tanks to allow new equipment insertion or hazards mitigation. A unique automated retrieval system at the tank provides for retrieval, high pressure washing, inventory measurement, and containment for disposal. Key to the inventory measurement is a three detector HPGe high performance gamma spectroscopy system capable of recovering data at up to 90% saturation (200,000 counts per second). Data recovery is based on a unique embedded electronic pulser and specialized software to report the inventory. Each of the detectors have different shielding specified through Monte Carlo simulation with the MCNP program. This shielding provides performance over a dynamic range of eight orders of magnitude. System description, calibration issues and operational experiences are discussed.

Troyer, G.L.

1997-03-17T23:59:59.000Z

427

Recommendation by the Secretary of Energy Regarding the Suitability of the Yucca Mountain Site for a Repository Under the Nuclear Waste Policy Act of 1982  

Broader source: Energy.gov [DOE]

Recommendation by the Secretary of Energy Regarding the Suitability of the Yucca Mountain Site for a Repository Under the Nuclear Waste Policy Act of 1982

428

DOE Awards Management and Operating Contract for DOE's Waste Isolation  

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

Management and Operating Contract for DOE's Waste Management and Operating Contract for DOE's Waste Isolation Pilot Plant DOE Awards Management and Operating Contract for DOE's Waste Isolation Pilot Plant April 20, 2012 - 12:00pm Addthis Media Contacts Bill Taylor Environmental Management Consolidated Business Center (803) 952-8564 Deb Gill U.S. DOE Carlsbad Field Office (575) 234-7270 CARLSBAD, N.M. - The U.S. Department of Energy (DOE) announced today that Nuclear Waste Partnership LLC (members comprised of URS Energy & Construction, Inc., of Boise, Idaho, and Babcock & Wilcox Technical Services Group, Inc., of Lynchburg, Virginia, and Major Subcontractor, AREVA Federal Services LLC, of Bethesda, Maryland) has been awarded a $1.3 billion contract for management and operating (M&O) at DOE's Waste

429

Integrated Data Base report--1993: U.S. spent nuclear fuel and radioactive waste inventories, projections, and characteristics. Revision 10  

SciTech Connect (OSTI)

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and DOE spent nuclear fuel; also, commercial and US government-owned radioactive wastes through December 31, 1993. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 256 refs., 38 figs., 141 tabs.

Not Available

1994-12-01T23:59:59.000Z

430

Virginia/Incentives | Open Energy Information  

Open Energy Info (EERE)

Virginia/Incentives Virginia/Incentives < Virginia Jump to: navigation, search Contents 1 Financial Incentive Programs for Virginia 2 Rules, Regulations and Policies for Virginia Download All Financial Incentives and Policies for Virginia CSV (rows 1 - 134) Financial Incentive Programs for Virginia Download Financial Incentives for Virginia CSV (rows 1 - 51) Incentive Incentive Type Active Arlington County - Green Building Incentive Program (Virginia) Green Building Incentive Yes Cape Charles - STIP Minimum Sustainability Requirements (Virginia) Green Building Incentive No Charlottesville Gas - Residential Energy Efficiency Rebate Program (Virginia) Utility Rebate Program Yes City of Danville Utilities - Business Energy Efficiency Rebates (Virginia) Utility Rebate Program Yes

431

Very long term communication intelligence: The case of markers for nuclear waste sites  

Science Journals Connector (OSTI)

Warning markers for long-term nuclear waste storage sites are required to prevent inadvertent human intrusion in the distant future. Two interdisciplinary teams have addressed the issues of physical durability and cognitive intelligibility of such markers for a U.S. government site in New Mexico. Preliminary design criteria have determined which materials are best suited to constitute markers of different sizes and shapes. A variety of linguistic, symbolic, and pictographic approaches to content have been suggested. Additional study and testing of both materials and messages is required. International standardization of marker strategies is extremely desirable.

Jon Lomberg; Stephen C. Hora

1997-01-01T23:59:59.000Z

432

A Characteristics-Based Approach to Radioactive Waste Classification in Advanced Nuclear Fuel Cycles  

E-Print Network [OSTI]

Nuclear   Fuel”,   Nuclear  Engineering  and  Technology,  in   Engineering  -­?  Nuclear  Engineering   and  the  in  Engineering  -­?  Nuclear  Engineering   and  the  

Djokic, Denia

2013-01-01T23:59:59.000Z

433

A Science-Based Approach to Understanding Waste Form Durability in Open and Closed Nuclear Fuel Cycles  

SciTech Connect (OSTI)

There are two compelling reasons for understanding source term and near-field processes in a radioactive waste geologic repository. First, almost all of the radioactivity is initially in the waste form, mainly in the spent nuclear fuel (SNF) or nuclear waste glass. Second, over long periods, after the engineered barriers are degraded, the waste form is a primary control on the release of radioactivity. Thus, it is essential to know the physical and chemical state of the waste form after hundreds of thousands of years. The United States Department of Energy's Yucca Mountain Repository Program has initiated a long-term program to develop a basic understanding of the fundamental mechanisms of radionuclide release and a quantification of the release as repository conditions evolve over time. Specifically, the research program addresses four critical areas: (a) SNF dissolution mechanisms and rates; (b) formation and properties of U{sup 6+}-secondary phases; (c) waste form-waste package interactions in the near-field; and (d) integration of in-package chemical and physical processes. The ultimate goal is to integrate the scientific results into a larger scale model of source term and near-field processes. This integrated model will be used to provide a basis for understanding the behavior of the source term over long time periods (greater than 10{sup 5} years). Such a fundamental and integrated experimental and modeling approach to source term processes can also be readily applied to development of advanced waste forms as part of a closed nuclear fuel cycle. Specifically, a fundamental understanding of candidate waste form materials stability in high temperature/high radiation environments and near-field geochemical/hydrologic processes could enable development of advanced waste forms ''tailored'' to specific geologic settings.

M.T. Peters; R.C. Ewing

2006-06-22T23:59:59.000Z

434

Waste degradation and mobilization in performance assessments for the Yucca Mountain disposal system for spent nuclear fuel and high-level radioactive waste  

Science Journals Connector (OSTI)

Abstract This paper summarizes modeling of waste degradation and mobilization in performance assessments (PAs) conducted between 1984 and 2008 to evaluate feasibility, viability, and assess compliance of a repository for spent nuclear fuel and high-level radioactive waste at Yucca Mountain in southern Nevada. As understanding of the Yucca Mountain disposal system increased, the waste degradation module, or succinctly called the source-term, evolved from initial assumptions in 1984 to results based on process modeling in 2008. In early PAs, waste degradation had significant influence on calculated behavior but as the robustness of the waste container was increased and modeling of the container degradation improved, waste degradation had much less influence in later PAs. The variation of dissolved concentrations of radionuclides progressed from simple probability distributions in early \\{PAs\\} to functions dependent upon water chemistry in later PAs. Also, transport modeling of radionuclides in the waste, container, and invert were added in 1995; and, colloid-facilitated transport of radionuclides was added in 1998.

Rob P. Rechard; Christine T. Stockman

2014-01-01T23:59:59.000Z

435

The National Nuclear Laboratory's Approach to Processing Mixed Wastes and Residues - 13080  

SciTech Connect (OSTI)

The National Nuclear Laboratory (NNL) treats a wide variety of materials produced as by-products of the nuclear fuel cycle, mostly from uranium purification and fuel manufacture but also including materials from uranium enrichment and from the decommissioning of obsolete plants. In the context of this paper, treatment is defined as recovery of uranium or other activity from residues, the recycle of uranium to the fuel cycle or preparation for long term storage and the final disposal or discharge to the environment of the remainder of the material. NNL's systematic but flexible approach to residue assessment and treatment is described in this paper. The approach typically comprises up to five main phases. The benefits of a systematic approach to waste and residue assessments and processing are described in this paper with examples used to illustrate each phase of work. Benefits include early identification of processing routes or processing issues and the avoidance of investment in inappropriate and costly plant or processes. (authors)

Greenwood, Howard; Docrat, Tahera; Allinson, Sarah J.; Coppersthwaite, Duncan P.; Sultan, Ruqayyah; May, Sarah [National Nuclear Laboratory, Springfields, Preston, UK, PR4 0XJ (United Kingdom)] [National Nuclear Laboratory, Springfields, Preston, UK, PR4 0XJ (United Kingdom)

2013-07-01T23:59:59.000Z

436

Circleville, West Virginia 26804  

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

P.O. Box 194 P.O. Box 194 Circleville, West Virginia 26804 March 28, 2012 Lamont Jackson Office of Electricity Delivery and Energy Reliability U.S. Department of Energy 1000 Independence Ave. SW Washington, DC 20585 Via email to lamont.jackson@hq.doe.gov Re: OE Docket No. RRTT-IR-001 (Rapid Response Team for Transmission); Office of Electricity Delivery and Energy Reliability, Department of Energy Dear Mr. Jackson: Please accept the following comments submitted on behalf of the Allegheny Highlands Alliance, Inc. ("AHA"), an organization comprised of residents of the states of West Virginia, Pennsylvania, Maryland, Virginia and North Carolina. AHA is presently awaiting a decision

437

Global Nuclear Energy Partnership Fact Sheet - Minimize Nuclear...  

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

Minimize Nuclear Waste Global Nuclear Energy Partnership Fact Sheet - Minimize Nuclear Waste GNEP will increase the efficiency in the management of used nuclear fuel, also known as...

438

Virginia Gas and Oil Act (Virginia) | Department of Energy  

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

Virginia Gas and Oil Act (Virginia) Virginia Gas and Oil Act (Virginia) Virginia Gas and Oil Act (Virginia) < Back Eligibility Commercial Construction Industrial Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Systems Integrator Utility Program Info State Virginia Program Type Safety and Operational Guidelines Siting and Permitting Provider Virginia Department of Mines, Minerals, and Energy The Gas and Oil Act addresses the exploration, development, and production of oil and gas resources in the Commonwealth of Virginia. It contains provisions pertaining to wells and well spacing, permits and fees, ownership of coalbed methane gas, and land leases. No county, city, town or other political subdivision of the Commonwealth may impose any condition, or require any other local license, permit, fee or bond to perform any gas,

439

SBOT VIRGINIA THOMAS JEFFERSON LAB POC Danny Llyod Telephone  

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

VIRGINIA VIRGINIA THOMAS JEFFERSON LAB POC Danny Llyod Telephone (757) 269-7121 Email lloyd@jlab.org ADMINISTATIVE / WASTE / REMEDIATION Facilities Support Services 561210 Employment Placement Agencies 561311 Travel Agencies 561510 Locksmiths 561622 Exterminating and Pest Control Services 561710 Janitorial Services 561720 Landscaping Services 561730 Carpet and Upholstery Cleaning Services 561740 Hazardous Waste Collection 562112 CONSTRUCTION Industrial Building Construction 236210 Commercial and Institutional Building Construction 236220 Water and Sewer Line and Related Structures Construction 237110 Power and Communication Line and Related Structures Construction 237130 Highway, Street, and Bridge Construction 237310 Other Heavy and Civil Engineering Construction 237990 Other Foundation, Structure, and Building Exterior Contractors

440

Thermal impact of waste emplacement and surface cooling associated with geologic disposal of high-level nuclear waste  

Science Journals Connector (OSTI)

This article is a study of the thermal effects associated with the emplacement of aged radioactive high-level wastes in a geologic repository, with emphasis on the following subjects: waste characteristics, re...

J. S. Y. Wang; D. C. Mangold; C. F. Tsang

1988-04-01T23:59:59.000Z

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


441

Assessment of Nuclear Safety Culture at the Idaho Cleanup Project Sodium Bearing Waste Treatment Project, November 2012  

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

Idaho Cleanup Project Idaho Cleanup Project Sodium Bearing Waste Treatment Project May 2011 November 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy Independent Oversight Assessment of Nuclear Safety Culture at the Idaho Cleanup Project Sodium Bearing Waste Treatment Project Table of Contents 1.0 Introduction........................................................................................................................................... 1 2.0 Scope and Methodology ....................................................................................................................... 2

442

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

SciTech Connect (OSTI)

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

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

2011-01-01T23:59:59.000Z

443

Selection of candidate canister materials for high-level nuclear waste containment in a tuff repository  

SciTech Connect (OSTI)

A repository located at Yucca Mountain at the Nevada Test Site is a potential site for permanent geological disposal of high-level nuclear waste. The repository can be located in a horizon in welded tuff, a volcanic rock, which is above the static water level at this site. The environmental conditions in this unsaturated zone are expected to be air and water vapor dominated for much of the containment period. Type 304L stainless steel is the reference material for fabricating canisters to contain the solid high-level wastes. Alternative stainless alloys are considered because of possible susceptibility of 304L to localized and stress forms of corrosion. For the reprocessed glass wastes, the canisters serve as the recipient for pouring the glass with the result that a sensitized microstructure may develop because of the times at elevated temperatures. Corrosion testing of the reference and alternative materials has begun in tuff-conditioned water and steam environments. 21 references, 8 figures, 8 tables.

McCright, R.D.; Weiss, H.; Juhas, M.C.; Logan, R.W.

1983-11-01T23:59:59.000Z

444

Virginia Regional Industrial Facilities Act (Virginia) | Department of  

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

Regional Industrial Facilities Act (Virginia) Regional Industrial Facilities Act (Virginia) Virginia Regional Industrial Facilities Act (Virginia) < Back Eligibility Commercial Construction Developer Industrial Investor-Owned Utility Local Government Municipal/Public Utility Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Virginia Program Type Industry Recruitment/Support Provider Regional Industrial Facility Authorities The Virginia Regional Industrial Facilities Act is meant to aid the economic development of localities within the Commonwealth. The Act provides a mechanism for localities to establish regional industrial facility authorities, enabling them to pool financial resources to stimulate economic development. The purpose of a regional industrial

445

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

446

Blending mining and nuclear industries at the Waste Isolation Pilot Plant  

SciTech Connect (OSTI)

At the Waste Isolation Pilot Plant (WIPP) traditional procedures for underground mining activities have been significantly altered in order to assure underground safety and project adherence to numerous regulatory requirements. Innovative techniques have been developed for WIPP underground procedures, mining equipment, and operating environments. The mining emphasis at WIPP is upon the quality of the excavation, not (as in conventional mines) on the production of ore. The WIPP is a United States Department of Energy (DOE) project that is located 30 miles southeast of Carlsbad, New Mexico, where the nation's first underground engineered nuclear repository is being constructed. The WIPP site was selected because of its location amidst a 607 meter thick salt bed, which provides a remarkably stable rock formation for the permanent storage of nuclear waste. The underground facility is located 655 meters below the earth's surface, in the Salado formation, which comprises two-hundred million year old halites with minor amounts of clay and anhydrites. When completed, the WIPP underground facility will consist of two components: approximately 81 square kilometers of experimental areas, and approximately 405 square kilometers of repository. 3 figs.

Walls, J.R.

1990-01-01T23:59:59.000Z

447

Summary of four release consequence analyses for hypothetical nuclear waste repositories in salt and granite  

SciTech Connect (OSTI)

Release consequence methology developed under the Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) program has now been applied to four hypothetical repository sites. This paper summarizes the results of these four studies in order to demonstrate that the far-field methodology developed under the AEGIS program offers a practical approach to the post-closure safety assessment of nuclear waste repositories sited in deep continental geologic formations. The four studies are briefly described and compared according to the following general categories: physical description of the repository (size, inventory, emplacement depth); geologic and hydrologic description of the site and the conceptual hydrologic model for the site; description of release scenario; hydrologic model implementation and results; engineered barriers and leach rate modeling; transport model implementation and results; and dose model implementation and results. These studies indicate the following: numerical modeling is a practical approach to post-closure safety assessment analysis for nuclear waste repositories; near-field modeling capability needs improvement to permit assessment of the consequences of human intrusion and pumping well scenarios; engineered barrier systems can be useful in mitigating consequences for postulated release scenarios that short-circuit the geohydrologic system; geohydrologic systems separating a repository from the natural biosphere discharge sites act to mitigate the consequences of postulated breaches in containment; and engineered barriers of types other than the containment or absorptive type may be useful.

Cole, C.R.; Bond, F.W.

1980-12-01T23:59:59.000Z

448

Virginia Gasoline Price Data  

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

Virginia Virginia Exit Fueleconomy.gov The links below are to pages that are not part of the fueleconomy.gov. We offer these external links for your convenience in accessing additional information that may be useful or interesting to you. Selected Cities Alexandria AlexandriaGasPrices.com Automotive.com Mapquest.com Arlington ArlingtonGasPrices.com Automotive.com Mapquest.com Chesapeake ChesapeakeGasPrices.com Automotive.com Mapquest.com Hampton HamptonGasPrices.com Automotive.com Mapquest.com Newport News NewportNewsGasPrices.com Automotive.com Mapquest.com Norfolk NorfolkGasPrices.com Automotive.com Mapquest.com Portsmouth PortsmouthGasPrices.com Automotive.com Mapquest.com Richmond RichmondGasPrices.com Automotive.com Mapquest.com Virginia Beach VirginiaBeachGasPrices.com Automotive.com Mapquest.com

449

Virginia | OpenEI  

Open Energy Info (EERE)

Virginia Virginia Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 88, and contains only the reference case. The data is broken down into electric power sector, cumulative planned additions,cumulative unplanned additions,cumulative retirements, end-use sector, electricity sales, net energy for load, generation by fuel type and price by service category. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO Carolina EIA Electric power projections Virginia Data application/vnd.ms-excel icon ASEO2011: Electric Power Projections for EMM Region - SERC Reliability Corporation / Virginia-Carolina- Reference Case (xls, 259.3 KiB)

450

Technologies for destruction of long-lived radionuclides in high-level nuclear waste: Overview and requirements  

SciTech Connect (OSTI)

This paper, and this topical session on Nuclear Waste Minimization, Management and Remediation, focuses on two nuclear systems, and their associated technologies, that have the potential to address concerns surrounding long-lived radionuclides in high-level waste. Both systems offer technology applicable to HLW from present light-water reactors (LWR). Additionally these systems represent advanced nuclear power concepts that have important features associated with integrated management of wastes, long-term fuel supplies, and enhanced safety. The first system is the Integral Fast Reactor (IFR) concept. This system incorporates a metal-fueled fast reactor coupled with chemical separations based on pyroprocessing to produce power while simultaneously burning long-lived actinide waste. IFR applications include burning of actinides from current LWR spent fuel and energy production in a breeder environment. The second concept, Accelerator Transmutation of Waste (ATW), is based upon an accelerator-induced intense source of thermal neutrons and is aimed at destruction of long-lived actinides and fission products. This concept can be applied to long-lived radionuclides in spent fuel HLW as well as a future fission power source built around use of natural thorium or uranium as fuels coupled with concurrent waste destruction.

Arthur, E.D.

1993-10-01T23:59:59.000Z

451

Management of Low-Level Radioactive Waste from Research, Hospitals and Nuclear Medical Centers in Egypt - 13469  

SciTech Connect (OSTI)

The application of radioisotopes and radiation sources in medical diagnosis and therapy is an important issue. Physicians can use radioisotopes to diagnose and treat diseases. Methods of treatment, conditioning and management of low level radioactive wastes from the use of radiation sources and radioisotopes in hospitals and nuclear medicine application, are described. Solid Radioactive waste with low-level activity after accumulation, minimization, segregation and measurement, are burned or compressed in a compactor according to the international standards. Conditioned drums are transported to the interim storage site at the Egyptian Atomic Energy Authority (EAEA) represented in Hot Labs and Waste Management Center (HLWMC) for storage and monitoring. (authors)

Hasan, M.A.; Selim, Y.T.; Lasheen, Y.F. [Hot Labs and Waste Management Center, Atomic Energy Authority, 3 Ahmed El-Zomor St., El-Zohour District, Naser City, 11787, Cairo (Egypt)] [Hot Labs 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

452

Apatite- and monazite-bearing glass-crystal composites for the immobilization of low-level nuclear and hazardous wastes  

SciTech Connect (OSTI)

This study demonstrates that glass-crystal composite waste forms can be produced from waste streams containing high proportions of phosphorus, transition metals, and/or halides. The crystalline phases produced in crucible-scale melts include apatite, monazite, spinels, and a Zr-Si-Fe-Ti phase. These phases readily incorporated radionuclide and toxic metals into their crystal structures, while corrosion tests have demonstrated that glass-crystal composites can be up to 300-fold more durable than simulated high-level nuclear waste glasses, such as SRL 202U.

Wronkiewicz, D.J.; Wolf, S.F.; DiSanto, T.S.

1995-12-31T23:59:59.000Z

453

Solid-state NMR examination of alteration layers on nuclear waste glasses  

Science Journals Connector (OSTI)

Abstract Solid-state nuclear magnetic resonance (NMR) is a powerful tool for probing the role and significance of alteration layers in determining the kinetics for the corrosion of nuclear waste glass. NMR methods are used to probe the chemical structure of the alteration layers to elucidate information about their chemical complexity, leading to increased insight into the mechanism of altered layer formation. Two glass compositions were examined in this study: a glass preliminarily designed for nuclear waste immobilization (called AFCI) and a simplified version of this AFCI glass (which we call SA1R). Powdered glasses with controlled and known particle sizes were corroded in ASTM type I water at 90 °C for periods of one and five months with a glass surface-area to solution-volume ratio of 100,000 m? 1. 1H–29Si cross-polarization Carr-Purcell-Meiboom-Gill (CP-CPMG) magic angle spinning (MAS) NMR, 1H–27Al CP-MAS NMR, 1H–11B CP-MAS NMR, and 1H–23Na CP-MAS NMR experiments provided isolated structural information about the alteration layers, which differ in structure from that of the pristine glass. Both glasses studied here develop alteration layers composed primarily of [IV]Si species. Aluminum is also retained in the alteration layers, perhaps facilitated by the observed increase in coordination from [IV]Al to [VI]Al, which correlates with a loss of charge balancing cations. The mechanism of increasing coordination appears to occur through an unstable [V]Al intermediate. 1H–11B CP-MAS NMR observations indicated a retention of boron in the hydrated glass layers, which has not been characterized by previous work. For the AFCI glass, secondary phase formation begins during the corrosion times considered here, and these new phases are detected within the alteration layers. We identify new phases (termed as precursor phases) as crystalline sodium metasilicates. An important finding is that simple glass compositions, while providing general trends about the formation of alteration layers, do not account for all of the various reaction products that occur in the corrosion of more complex nuclear waste glass compositions.

Kelly A. Murphy; Nancy M. Washton; Joseph V. Ryan; Carlo G. Pantano; Karl T. Mueller

2013-01-01T23:59:59.000Z

454

Environmental assessment for DOE permission for off-loading activities to support the movement of commercial low level nuclear waste across the Savannah River Site  

SciTech Connect (OSTI)

This environmental assessment investigates the potential environmental and safety effects which could result from the land transport of low level radioactive wastes across the Savannah River Plant. Chem-Nuclear Systems operates a low level radioactive waste burial facility adjacent to the Savannah River Plant and is seeking permission from the DOE to transport the waste across Savannah River Plant.

NONE

1995-02-01T23:59:59.000Z

455

State Nuclear Profiles 2010  

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

8 8 Virginia Virginia total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,501 14.5 26,572 36.4 Coal 5,868 24.3 25,459 34.9 Hydro and Pumped Storage 4,107 17.0 10 * Natural Gas 7,581 31.4 16,999 23.3 Other 1 - - 414 0.6 Other Renewable 1 621 2.6 2,220 3.0 Petroleum 2,432 10.1 1,293 1.8 Total 24,109 100.0 72,966 100.0 * = Absolute percentage less than 0.05. - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture byproducts, other biomass, geothermal, solar thermal, photovoltaic energy, and wind. Source: Form EIA-860, "Annual Electric Generator Report," and Form EIA-923, "Power Plant Operations Report." Share of State total (percent)

456

State Nuclear Profiles 2010  

Gasoline and Diesel Fuel Update (EIA)

8 8 Virginia Virginia total electric power industry, summer capacity and net generation, by energy source, 2010 Nuclear 3,501 14.5 26,572 36.4 Coal 5,868 24.3 25,459 34.9 Hydro and Pumped Storage 4,107 17.0 10 * Natural Gas 7,581 31.4 16,999 23.3 Other 1 - - 414 0.6 Other Renewable 1 621 2.6 2,220 3.0 Petroleum 2,432 10.1 1,293 1.8 Total 24,109 100.0 72,966 100.0 * = Absolute percentage less than 0.05. - = No data reported. Other Renewable: Wood, black liquor, other wood waste, biogenic municipal solid waste, landfill gas, sludge waste, agriculture byproducts, other biomass, geothermal, solar thermal, photovoltaic energy, and wind. Source: Form EIA-860, "Annual Electric Generator Report," and Form EIA-923, "Power Plant Operations Report." Share of State total (percent)

457

Virginia Capital Access Program (Virginia) | Department of Energy  

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

Capital Access Program (Virginia) Capital Access Program (Virginia) Virginia Capital Access Program (Virginia) < Back Eligibility Commercial Industrial Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Virginia Program Type Loan Program Provider Virginia Economic Development Partnership The Virginia Capital Access Program (CAP), in partnership with Virginia's Small Business Financing Authority, provides access to capital for small businesses. Businesses must apply to participating banks for a traditional loan, and the lender advises the company of enrollment in CAP. The program offers loan guarantees on a portfolio of loans through a loan loss reserve, which it establishes at each participating bank. Funds can be used for

458

Virginia Jobs Investment Program (Virginia) | Department of Energy  

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

Jobs Investment Program (Virginia) Jobs Investment Program (Virginia) Virginia Jobs Investment Program (Virginia) < Back Eligibility Commercial Industrial Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Virginia Program Type Industry Recruitment/Support Training/Technical Assistance Workforce development Provider Virginia Department of Business Assistance The Virginia Jobs Investment Program provides cash grants to existing businesses which seek expansion or new facility locations. The company must create a minimum of 25 net new jobs within 12 months from the date of first hire and make a capital investment of at least $1,000,000. The Virginia Jobs Investment Program offers three programs to both new and

459

Nuclear Waste: Knowledge Waste?  

Science Journals Connector (OSTI)

...procedurally, the issues that concern the public. Fortunately, there is a sizable social science...systematically investigated the questions of public acceptability, making basic tenets of public concerns quite clear (8, 22). People do...

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

2010-08-13T23:59:59.000Z

460

Nuclear Waste: Knowledge Waste?  

Science Journals Connector (OSTI)

...A. Dan A. Dietz T. , Risk Anal. 29 , 425 ( 2009...Trust and the Management of Risk , Cvetkovich G. Lofstedt...Council , Understanding Risk: Informing Decisions in...Washington, DC , 1996 ). 22 Fischhoff B. , in Oxford Textbook...

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

2010-08-13T23:59:59.000Z

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


461

Initial performance assessment of the disposal of spent nuclear fuel and high-level waste stored at Idaho National Engineering Laboratory. Volume 2: Appendices  

SciTech Connect (OSTI)

This performance assessment characterized plausible treatment options conceived by the Idaho National Engineering Laboratory (INEL) for its spent fuel and high-level radioactive waste and then modeled the performance of the resulting waste forms in two hypothetical, deep, geologic repositories: one in bedded salt and the other in granite. The results of the performance assessment are intended to help guide INEL in its study of how to prepare wastes and spent fuel for eventual permanent disposal. This assessment was part of the Waste Management Technology Development Program designed to help the US Department of Energy develop and demonstrate the capability to dispose of its nuclear waste, as mandated by the Nuclear Waste Policy Act of 1982. The waste forms comprised about 700 metric tons of initial heavy metal (or equivalent units) stored at the INEL: graphite spent fuel, experimental low enriched and highly enriched spent fuel, and high-level waste generated during reprocessing of some spent fuel. Five different waste treatment options were studied; in the analysis, the options and resulting waste forms were analyzed separately and in combination as five waste disposal groups. When the waste forms were studied in combination, the repository was assumed to also contain vitrified high-level waste from three DOE sites for a common basis of comparison and to simulate the impact of the INEL waste forms on a moderate-sized repository, The performance of the waste form was assessed within the context of a whole disposal system, using the U.S. Environmental Protection Agency`s Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Wastes, 40 CFR 191, promulgated in 1985. Though the waste form behavior depended upon the repository type, all current and proposed waste forms provided acceptable behavior in the salt and granite repositories.

Rechard, R.P. [ed.

1993-12-01T23:59:59.000Z

462

Challenge problem and milestones for : Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC).  

SciTech Connect (OSTI)

This report describes the specification of a challenge problem and associated challenge milestones for the Waste Integrated Performance and Safety Codes (IPSC) supporting the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The NEAMS challenge problems are designed to demonstrate proof of concept and progress towards IPSC goals. The goal of the Waste IPSC is to develop an integrated suite of modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. To demonstrate proof of concept and progress towards these goals and requirements, a Waste IPSC challenge problem is specified that includes coupled thermal-hydrologic-chemical-mechanical (THCM) processes that describe (1) the degradation of a borosilicate glass waste form and the corresponding mobilization of radionuclides (i.e., the processes that produce the radionuclide source term), (2) the associated near-field physical and chemical environment for waste emplacement within a salt formation, and (3) radionuclide transport in the near field (i.e., through the engineered components - waste form, waste package, and backfill - and the immediately adjacent salt). The initial details of a set of challenge milestones that collectively comprise the full challenge problem are also specified.

Freeze, Geoffrey A.; Wang, Yifeng; Howard, Robert; McNeish, Jerry A.; Schultz, Peter Andrew; Arguello, Jose Guadalupe, Jr.

2010-09-01T23:59:59.000Z

463

Novel Problems Associated with Accounting and Control of Nuclear Material from Decontamination and Decommissioning and in Waste  

SciTech Connect (OSTI)

Abstract The reduction in nuclear arms and the production facilities that supported the weapons programs have produced some unique problems for nuclear material control and accountability (MC&A). Many of these problems are not limited to the weapons complex, but have the potential to appear in many legacy facilities as they undergo dismantlement and disposal. Closing facilities find that what was previously defined as product has become a waste stream bringing regulatory, human, and technological conflict. The sometimes unique compositions of these materials produce both storage and measurement problems. The nuclear material accounting and control programs have had to become very adaptive and preemptive to ensure control and protection is maintained. This paper examines some of the challenges to Safeguards generated by deinventory, decontamination decommissioning, dismantlement, demolition, and waste site remediation from predictable sources and some from unpredictable sources. 1.0 Introduction The United States is eliminating many facilities that support the nuclear weapons program. With the changing political conditions around the world and changes in military capabilities, the decreased emphasis on nuclear weapons has eliminated the need for many of the aging facilities. Additionally, the recovery of plutonium from dismantled weapons and reuse of components has eliminated the need to produce more plutonium for the near future. Because the nuclear weapons program and commercial applications generally do not mix in the United States, the facilities in the DOE complex that no longer have a weapon mission are being deinventoried, decontaminated, decommissioned, and dismantled/demolished. The materials from these activities are then disposed of in various ways but usually in select waste burial sites. Additionally, the waste in many historical burial sites associated with the weapons complex are being recovered, repackaged if necessary, and disposed of in either geological sites or low-level waste sites. The type of waste from the decontamination and decommissioning (D&D) activities varies from uncontaminated construction materials to nuclear weapon components. This variety of forms, types, and composition of nuclear material presents many challenges to MC&A. It requires the creative application of regulations, but current regulations are adequate to ensure the security and control of the nuclear material. This paper examines some of the approaches used to meet regulatory requirements and problems that occurred during D&D. Experiences are drawn for the Hanford site and elsewhere in the DOE complex.

Schlegel, Steven C.

2007-07-10T23:59:59.000Z

464

Experimental Methods to Estimate Accumulated Solids in Nuclear Waste Tanks - 13313  

SciTech Connect (OSTI)

The Department of Energy has a large number of nuclear waste tanks. It is important to know if fissionable materials can concentrate when waste is transferred from staging tanks prior to feeding waste treatment plants. Specifically, there is a concern that large, dense particles, e.g., plutonium containing, could accumulate in poorly mixed regions of a blend tank heel for tanks that employ mixing jet pumps. At the request of the DOE Hanford Tank Operations Contractor, Washington River Protection Solutions, the Engineering Development Laboratory of the Savannah River National Laboratory performed a scouting study in a 1/22-scale model of a waste tank to investigate this concern and to develop measurement techniques that could be applied in a more extensive study at a larger scale. Simulated waste tank solids and supernatant were charged to the test tank and rotating liquid jets were used to remove most of the solids. Then the volume and shape of the residual solids and the spatial concentration profiles for the surrogate for plutonium were measured. This paper discusses the overall test results, which indicated heavy solids only accumulate during the first few transfer cycles, along with the techniques and equipment designed and employed in the test. Those techniques include: - Magnetic particle separator to remove stainless steel solids, the plutonium surrogate from a flowing stream. - Magnetic wand used to manually remove stainless steel solids from samples and the tank heel. - Photographs were used to determine the volume and shape of the solids mounds by developing a composite of topographical areas. - Laser range finders to determine the volume and shape of the solids mounds. - Core sampler to determine the stainless steel solids distribution within the solids mounds. - Computer driven positioner that placed the laser range finders and the core sampler over solids mounds that accumulated on the bottom of a scaled staging tank in locations where jet velocities were low. These devices and techniques were very effective to estimate the movement, location, and concentrations of the solids representing plutonium and are expected to perform well at a larger scale. The operation of the techniques and their measurement accuracies will be discussed as well as the overall results of the accumulated solids test. (authors)

Duignan, Mark R.; Steeper, Timothy J.; Steimke, John L. [Savannah River Nuclear Solutions, Savannah River National Laboratory, Aiken, SC 29808 (United States)] [Savannah River Nuclear Solutions, Savannah River National Laboratory, Aiken, SC 29808 (United States)

2013-07-01T23:59:59.000Z

465

Overview on backfill materials and permeable reactive barriers for nuclear waste disposal facilities.  

SciTech Connect (OSTI)

A great deal of money and effort has been spent on environmental restoration during the past several decades. Significant progress has been made on improving air quality, cleaning up and preventing leaching from dumps and landfills, and improving surface water quality. However, significant challenges still exist in all of these areas. Among the more difficult and expensive environmental problems, and often the primary factor limiting closure of contaminated sites following surface restoration, is contamination of ground water. The most common technology used for remediating ground water is surface treatment where the water is pumped to the surface, treated and pumped back into the ground or released at a nearby river or lake. Although still useful for certain remediation scenarios, the limitations of pump-and-treat technologies have recently been recognized, along with the need for innovative solutions to ground-water contamination. Even with the current challenges we face there is a strong need to create geological repository systems for dispose of radioactive wastes containing long-lived radionuclides. The potential contamination of groundwater is a major factor in selection of a radioactive waste disposal site, design of the facility, future scenarios such as human intrusion into the repository and possible need for retrieving the radioactive material, and the use of backfills designed to keep the radionuclides immobile. One of the most promising technologies for remediation of contaminated sites and design of radioactive waste repositories is the use of permeable reactive barriers (PRBs). PRBs are constructed of reactive material(s) to intercept and remove the radionuclides from the water and decontaminate the plumes in situ. The concept of PRBs is relatively simple. The reactive material(s) is placed in the subsurface between the waste or contaminated area and the groundwater. Reactive materials used thus far in practice and research include zero valent iron, hydroxyapatite, magnesium oxide, and others. As the contaminant moves through the reactive material, the contaminant is either sorbed by the reactive material or chemically reacts with the material to form a less harmful substance. Because of the high risk associated with failure of a geological repository for nuclear waste, most nations favor a near-field multibarrier engineered system using backfill materials to prevent release of radionuclides into the surrounding groundwater.

Moore, Robert Charles; Hasan, Ahmed Ali Mohamed; Holt, Kathleen Caroline; Hasan, Mahmoud A. (Egyptian Atomic Energy Authority, Cairo, Egypt)

2003-10-01T23:59:59.000Z

466

FUPWG Meeting Agenda- Williamsburg, Virginia  

Broader source: Energy.gov [DOE]

November 19-20, 2008Hosted by Virginia Natural Gas, an AGL Resources Company, in Partnership with Energy Systems Group

467

Numerical study of the THM effects on the near-field safety of a hypothetical nuclear waste repository--BMT1 of the DECOVALEX III project. Part 1: Conceptualization  

E-Print Network [OSTI]

Numerical study of the THM effects on the near-field safety of a hypothetical nuclear waste on the safety of a hypothetical nuclear waste repository at the near-field and are presented in three on the safety of nuclear waste repositories. To achieve the second objective, hypothetical benchmark test

Paris-Sud XI, Université de

468

Alternative Fuels Data Center: West Virginia Information  

Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

West Virginia West Virginia Information to someone by E-mail Share Alternative Fuels Data Center: West Virginia Information on Facebook Tweet about Alternative Fuels Data Center: West Virginia Information on Twitter Bookmark Alternative Fuels Data Center: West Virginia Information on Google Bookmark Alternative Fuels Data Center: West Virginia Information on Delicious Rank Alternative Fuels Data Center: West Virginia Information on Digg Find More places to share Alternative Fuels Data Center: West Virginia Information on AddThis.com... West Virginia Information This state page compiles information related to alternative fuels and advanced vehicles in West Virginia and includes new incentives and laws, alternative fueling station locations, truck stop electrification sites,

469

EA-1985: Virginia Offshore Wind Technology Advancement Project...  

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

5: Virginia Offshore Wind Technology Advancement Project (VOWTAP), 24 nautical miles offshore of Virginia Beach, Virginia EA-1985: Virginia Offshore Wind Technology Advancement...

470

Waste-to-Energy Workshop  

Broader source: Energy.gov [DOE]

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

471

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

SciTech Connect (OSTI)

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

Fernandez, J.A.

1985-02-01T23:59:59.000Z

472

Cyclic voltammetric studies for the electrochemical determination of palladium in high-level nuclear waste  

Science Journals Connector (OSTI)

Cyclic voltammetric studies of Pd(II)/Pd(0) electrode process were carried out on a Glassy Carbon Electrode (GCE) in HCl for the development of an Anodic Stripping Voltammetric (ASV) method for the determination of palladium in High-Level Nuclear Waste (HLNW). Pd(II) reduces electrochemically to Pd(0) in a wide potential range, depending upon the concentration of HCl. No significant effect of concentration was observed on the oxidation of palladium, which more or less occurs at 500 mV. Effects of HCl concentration, potential scan range, scan rate and scan repetition were studied in detail. The oxidation of palladium in HCl medium was relatively more distinct than in nitric and sulphuric acids. Maximum anodic and cathodic peak currents of unequal heights were observed at 1.0 × 10?2 M concentration of HCl. An ASV method was developed successfully on the basis of these studies for the determination of palladium in HLNW.

T.K. Bhardwaj

2012-01-01T23:59:59.000Z

473

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

SciTech Connect (OSTI)

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

W. Lee Poe, Jr

1998-10-01T23:59:59.000Z

474

Assessment of alternatives for management of ORNL retrievable transuranic waste. Nuclear Waste Program: transuranic waste (Activity No. AR 05 15 15 0; ONL-WT04)  

SciTech Connect (OSTI)

Since 1970, solid waste with TRU or U-233 contamination in excess of 10 ..mu..Ci per kilogram of waste has been stored in a retrievable fashion at ORNL, such as in ss drums, concrete casks, and ss-lined wells. This report describes the results of a study performed to identify and evaluate alternatives for management of this waste and of the additional waste projected to be stored through 1995. The study was limited to consideration of the following basic strategies: Strategy 1: Leave waste in place as is; Strategy 2: Improve waste confinement; and Strategy 3: Retrieve waste and process for shipment to a Federal repository. Seven alternatives were identified and evaluated, one each for Strategies 1 and 2 and five for Strategy 3. Each alternative was evaluated from the standpoint of technical feasibility, cost, radiological risk and impact, regulatory factors and nonradiological environmental impact.

Not Available

1980-10-01T23:59:59.000Z

475

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

SciTech Connect (OSTI)

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

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

1984-04-01T23:59:59.000Z

476

The Transmutation of Nuclear Waste in the Two-Zone Subcritical System Driven by High- Intensity Neutron Generator - 12098  

SciTech Connect (OSTI)

The main problems of transmutation of high-level radioactive waste (minor actinides and long-lived fission products) are considered in our work. The range of radioactive waste of nuclear power is analyzed. The conditions under which the transmutation of radioactive waste will be most effective are analyzed too. The modeling results of a transmutation of the main radioactive isotopes are presented and discussed. The transmutation of minor actinides and long-lived fission products are modeled in our work (minor actinides - Np-237, Am-241, Am-242, Am-243, Cm-244, Cm-245; long-lived fission products - I-129, Tc-99). The two-zone subcritical system is calculated with help of different neutron-physical codes (MCNP, Scale, Montebarn, Origen). The ENDF/B-VI nuclear data library used in above calculations. Thus, radioactive wastes can be divided into two main groups that need to be transmuted. The minor actinides form the first group and the long-lived fission products form the second one. For the purpose of effective transmutation these isotopes must be extracted from the spent nuclear fuel with the help of either PUREX technology or pyrometallurgical technology. The two-zone reactor system with fast and thermal regions is more effective for nuclear waste transmutation than the one-zone reactor. Modeling results show that nearly all radioactive wastes can be transmuted in the two-zone subcritical system driven by a high-intensity neutron generator with the external neutron source strength of 1.10{sup 13} n/sec. Obviously, transmutation rate will increase with a rise of the external neutron source strength. From the results above we can also see that the initial loading of radioactive isotopes into the reactor system should exceed by mass those isotopes that are finally produced. (authors)

Babenko, V.O. [Bogolyubov Institute for Theoretical Physics, Metrolohichna str. 14-b, Kiev, 03680 (Ukraine); Gulik, V.I.; Pavlovych, V.M. [Institute for Nuclear Research, pr. Nauky 47, Kyiv, 03680 (Ukraine)

2012-07-01T23:59:59.000Z

477

Crystallization of Sodium Phosphate Dodecahydrate and Re-Crystallization to Natrophosphate in Simulated Hanford Nuclear Waste  

SciTech Connect (OSTI)

The nuclear waste at the Hanford site near Richland, WA, has large concentrations of phosphate in the form of the phosphate ion, sodium phosphate dodecahydrate (Na3PO4.12H2O.(1/4)NaOH) and natrophosphate (Na7F(PO4)3.19H2O). Sodium phosphate dodecahydrate can form a gel and natrophosphate can crystallize large particles, complicating the processing of slurries of both salts. The gel is regarded as more problematic, so natrophosphate has historically been crystallized to prevent phosphate gelling. This study determined that natrophosphate crystals can grow to large size in short time periods (a few weeks), time periods relevant to short process shutdowns. Solutions of NaOH and NaAl(OH)4 were blended at different ratios with stock solutions containing NaOH, NaF, and Na3PO4 at 50 °C. The mixtures were allowed to cool to 22 °C, and the crystal growth was monitored by Polarized Light Microscopy (PLM) for 17 days. Four of the six blends investigated gelled rapidly due to Na3PO4.12H2O.(1/4)NaOH precipitation. The gel slowly dissipated over time as the solids recrystallized into natrophosphate. In one case, the natrophosphate reached sizes of greater than 1000 microns in diameter in just 4 days. This rapid gelling and crystallization kinetics is important to engineers trying to manage nuclear wastes high in phosphates. Hanford tank farm engineers are developing sampling plans to support temperature and process control strategies for preventing the formation of solid phosphates. They are also developing methods of suspending large natrophosphate crystals.

Reynolds, J. G.

2014-12-22T23:59:59.000Z

478

Solid-State NMR Examination of Alteration Layers on a Nuclear Waste Glasses  

SciTech Connect (OSTI)

Solid-state NMR is a powerful tool for probing the role and significance of alteration layers in determining the kinetics for the corrosion of nuclear waste glass. NMR methods are used to probe the chemical structure of the alteration layers to elucidate information about their chemical complexity, leading to increased insight into the mechanism of altered layer formation. Two glass compositions were examined in this study: a glass preliminarily designed for nuclear waste immobilization (called AFCI) and a simplified version of this AFCI glass (which we call SA1R). Powdered glasses with controlled and known particles sizes were corroded at 90 °C for periods of one and five months with a surface-area to solution-volume ratio of 100,000 m-1. 1H-29Si CP-CPMG MAS NMR, 1H-27Al CP-MAS NMR, 1H-11B CP-MAS NMR, and 1H-23Na CP-MAS NMR experiments provide isolated structural information about the alteration layers, which differ in structure from that of the pristine glass. Both glasses studied here develop alteration layers composed primarily of [IV]Si species. Aluminum is also retained in the alteration layers, perhaps facilitated by the observed increase in coordination from [IV]Al to [VI]Al, which correlates with a loss of charge balancing cations. 1H-11B CP-MAS NMR observations indicated a retention of boron in hydrated glass layers, which has not been characterized by previous work. For the AFCI glass, secondary phase formation begins during the corrosion times considered here, and these neophases are detected within the alteration layers. We identify precursor phases as crystalline sodium metasilicates. An important finding is that layer thickness depends on the length of the initial alteration stages and varies only with respect to silicon species during the residual rate regime.

Murphy, Kelly A. [Penn State Univ., State College, PA (United States). Dept. of Chemistry; Washton, Nancy M. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States). Environmental Molecular Science Lab.; Ryan, Joseph V. [Pacific Northwest National Laboratory (PNNL), Richland, WA (United States); Pantano, Carlo G. [Penn State Univ., State College, PA (United States). Dept. of Materials Science and Engineering; Mueller, Karl T. [Penn State Univ., State College, PA (United States). Dept. of Chemistry; Pacific Northwest National Laboratory (PNNL), Richland, WA (United States). Environmental Molecular Science Lab.

2013-06-01T23:59:59.000Z

479

Low-temperature lithium diffusion in simulated high-level boroaluminosilicate nuclear waste glasses  

Science Journals Connector (OSTI)

Abstract Ion exchange is recognized as an integral, if underrepresented, mechanism influencing glass corrosion. However, due to the formation of various alteration layers in the presence of water during the corrosion process, it is difficult to conclusively deconvolute the mechanisms of ion exchange from other simultaneously occurring processes. In this work, an inert non-aqueous solution was used as an alkali source material to isolate ion exchange and study the solid-state diffusion of lithium. Specifically, the experiments involved contacting simulated nuclear waste glass coupons, the 6-oxide CJ6 and the 26-oxide SON68, with a non-aqueous solution of 6LiCl dissolved in dimethyl sulfoxide at 90 °C for various time periods. The depth profiles of major elements in the glass coupons were measured using time-of-flight secondary ion mass spectrometry (ToF-SIMS). Lithium interdiffusion coefficients, DLi, were then calculated based on the measured depth profiles. The results indicate that the penetration of 6Li is faster in the simplified CJ6 (D6Li ? 4.0–8.0 × 10? 21 m2/s) compared to the more complex SON68 (D6Li ? 2.0–4.0 × 10? 21 m2/s). These values are roughly an order of magnitude greater than measured water diffusion in glasses at similar temperatures. Additionally, sodium ions present in the glass were observed to participate in ion exchange reactions with lithium from the solution. Implications of the diffusion coefficients obtained in the absence of alteration layers to the long-term performance of nuclear waste glasses in a geological repository system are also discussed.

James J. Neeway; Sebastien Kerisit; Stéphane Gin; Zhaoying Wang; Zihua Zhu; Joseph V. Ryan

2014-01-01T23:59:59.000Z

480

Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) verification and validation plan. version 1.  

SciTech Connect (OSTI)

The objective of the U.S. Department of Energy Office of Nuclear Energy Advanced Modeling and Simulation Waste Integrated Performance and Safety Codes (NEAMS Waste IPSC) is to provide an integrated suite of computational modeling and simulation (M&S) capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive-waste storage facility or disposal repository. To meet this objective, NEAMS Waste IPSC M&S capabilities will be applied to challenging spatial domains, temporal domains, multiphysics couplings, and multiscale couplings. A strategic verification and validation (V&V) goal is to establish evidence-based metrics for the level of confidence in M&S codes and capabilities. Because it is economically impractical to apply the maximum V&V rigor to each and every M&S capability, M&S capabilities will be ranked for their impact on the performance assessments of various components of the repository systems. Those M&S capabilities with greater impact will require a greater level of confidence and a correspondingly greater investment in V&V. This report includes five major components: (1) a background summary of the NEAMS Waste IPSC to emphasize M&S challenges; (2) the conceptual foundation for verification, validation, and confidence assessment of NEAMS Waste IPSC M&S capabilities; (3) specifications for the planned verification, validation, and confidence-assessment practices; (4) specifications for the planned evidence information management system; and (5) a path forward for the incremental implementation of this V&V plan.

Bartlett, Roscoe Ainsworth; Arguello, Jose Guadalupe, Jr.; Urbina, Angel; Bouchard, Julie F.; Edwards, Harold Carter; Freeze, Geoffrey A.; Knupp, Patrick Michael; Wang, Yifeng; Schultz, Peter Andrew; Howard, Robert (Oak Ridge National Laboratory, Oak Ridge, TN); McCornack, Marjorie Turner

2011-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "virginia nuclear waste" from the National Library of EnergyBeta (NLEBeta).
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481

FLUIDIZED BED STEAM REFORMING MINERALIZATION FOR HIGH ORGANIC AND NITRATE WASTE STREAMS FOR THE GLOBAL NUCLEAR ENERGY PARTNERSHIP  

SciTech Connect (OSTI)

Waste streams that may be generated by the Global Nuclear Energy Partnership (GNEP) Advanced Energy Initiative may contain significant quantities of organics (0-53 wt%) and/or nitrates (0-56 wt%). Decomposition of high nitrate streams requires reducing conditions, e.g. organic additives such as sugar or coal, to reduce the NO{sub x} in the off-gas to N{sub 2} to meet the Clean Air Act (CAA) standards during processing. Thus, organics will be present during waste form stabilization regardless of which GNEP processes are chosen, e.g. organics in the feed or organics for nitrate destruction. High organic containing wastes cannot be stabilized with the existing HLW Best Developed Available Technology (BDAT) which is HLW vitrification (HLVIT) unless the organics are removed by preprocessing. Alternative waste stabilization processes such as Fluidized Bed Steam Reforming (FBSR) operate at moderate temperatures (650-750 C) compared to vitrification (1150-1300 C). FBSR converts organics to CAA compliant gases, creates no secondary liquid waste streams, and creates a stable mineral waste form that is as durable as glass. For application to the high Cs-137 and Sr-90 containing GNEP waste streams a single phase mineralized Cs-mica phase was made by co-reacting illite clay and GNEP simulated waste. The Cs-mica accommodates up to 30% wt% Cs{sub 2}O and all the GNEP waste species, Ba, Sr, Rb including the Cs-137 transmutation to Ba-137. For reference, the cesium mineral pollucite (CsAlSi{sub 2}O{sub 6}), currently being studied for GNEP applications, can only be fabricated at {ge} 1000 C. Pollucite mineralization creates secondary aqueous waste streams and NO{sub x}. Pollucite is not tolerant of high concentrations of Ba, Sr or Rb and forces the divalent species into different mineral host phases. The pollucite can accommodate up to 33% wt% Cs{sub 2}O.

Jantzen, C; Michael Williams, M

2008-01-11T23:59:59.000Z

482

Sandia National Laboratories performance assessment methodology for long-term environmental programs : the history of nuclear waste management.  

SciTech Connect (OSTI)

Sandia National Laboratories (SNL) is the world leader in the development of the detailed science underpinning the application of a probabilistic risk assessment methodology, referred to in this report as performance assessment (PA), for (1) understanding and forecasting the long-term behavior of a radioactive waste disposal system, (2) estimating the ability of the disposal system and its various components to isolate the waste, (3) developing regulations, (4) implementing programs to estimate the safety that the system can afford to individuals and to the environment, and (5) demonstrating compliance with the attendant regulatory requirements. This report documents the evolution of the SNL PA methodology from inception in the mid-1970s, summarizing major SNL PA applications including: the Subseabed Disposal Project PAs for high-level radioactive waste; the Waste Isolation Pilot Plant PAs for disposal of defense transuranic waste; the Yucca Mountain Project total system PAs for deep geologic disposal of spent nuclear fuel and high-level radioactive waste; PAs for the Greater Confinement Borehole Disposal boreholes at the Nevada National Security Site; and PA evaluations for disposal of high-level wastes and Department of Energy spent nuclear fuels stored at Idaho National Laboratory. In addition, the report summarizes smaller PA programs for long-term cover systems implemented for the Monticello, Utah, mill-tailings repository; a PA for the SNL Mixed Waste Landfill in support of environmental restoration; PA support for radioactive waste management efforts in Egypt, Iraq, and Taiwan; and, most recently, PAs for analysis of alternative high-level radioactive waste disposal strategies including repositories deep borehole disposal and geologic repositories in shale and granite. Finally, this report summarizes the extension of the PA methodology for radioactive waste disposal toward development of an enhanced PA system for carbon sequestration and storage systems. These efforts have produced a generic PA methodology for the evaluation of waste management systems that has gained wide acceptance within the international community. This report documents how this methodology has been used as an effective management tool to evaluate different disposal designs and sites; inform development of regulatory requirements; identify, prioritize, and guide research aimed at reducing uncertainties for objective estimations of risk; and support safety assessments.

Marietta, Melvin Gary; Anderson, D. Richard; Bonano, Evaristo J.; Meacham, Paul Gregory (Raytheon Ktech, Albuquerque, NM)

2011-11-01T23:59:59.000Z

483

Virginia Enterprise Zone Job Creation Grant (Virginia) | Department of  

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

Enterprise Zone Job Creation Grant (Virginia) Enterprise Zone Job Creation Grant (Virginia) Virginia Enterprise Zone Job Creation Grant (Virginia) < Back Eligibility Commercial Industrial Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Maximum Rebate $500 per position Program Info State Virginia Program Type Enterprise Zone Grant Program Provider Virginia Department of Housing and Community Development The Virginia Enterprise Zone Job Creation Grant provides cash grants to businesses located in Enterprise zones that create permanent new jobs over a four-job threshold. State incentives are available to businesses and zone investors who create jobs and invest in real property within the boundaries of enterprise zones. The positions must pay at least 175 percent of the

484

Virginia.indd  

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

Virginia Virginia www.effi cientwindows.org March 2013 1. Meet the Energy Code and Look for the ENERGY STAR ® Windows must comply with your local energy code. Windows that are ENERGY STAR qualifi ed typically meet or exceed energy code requirements. To verify if specific window energy properties comply with the local code requirements, go to Step 2. 2. Look for Effi cient Properties on the NFRC Label The National Fenestration Rating Council (NFRC) label is needed for verifi cation of energy code compliance (www.nfrc. org). The NFRC label displays whole- window energy properties and appears on all fenestration products which are part of the ENERGY STAR program.

485

Design methodology to develop a conceptual underground facility for the disposal of high-level nuclear waste at Yucca Mountain, Nevada  

SciTech Connect (OSTI)

This paper examines the design methodology employed to develop conceptual underground layouts for a prospective high level nuclear waste repository at Yucca Mountain, Nevada. This study is in conjunction with the Nevada Nuclear Waste Storage Investigations (NNWSI), project studying the disposal of high level waste in densely welded tuff. The fundamental design effort concentraes on the effects of the heat released from the decaying waste forms and the impact of this heat on ventilation, waste emplacement configurations, and rock stability. This effort will perfect the design of the waste emplacement layout including emplacement hole spacing, emplacement drift spacing, and the areal power density (APD) for the installed waste. This paper contains only viewgraphs. 11 figs.

Zerga, D.P.; B