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1

ISOLATION OF RADIOACTIVE METALS FROM LIQUID WASTES  

EPA Science Inventory

Metals are present in many waste streams, and pose challenges with regard to their disposal. Release of metals into the environment presents both human health and ecological concerns. As a result, efforts are directed at reducing their toxicity, bioavailability, and environment...

2

Thermochemical Processing of Radioactive Waste Using Powder Metal Fuels  

SciTech Connect

Problematic radioactive wastes were generated during various activities of both industrial facilities and research institutions usually in relative small amounts. These can be spent ion exchange resins, inorganic absorbents, wastes from research nuclear reactors, irradiated graphite, mixed, organic or chlorine-containing radioactive waste, contaminated soils, un-burnable heavily surface-contaminated materials, etc. Conventional treatment methods encounter serious problems concerning processing efficiency of such waste, e.g. complete destruction of organic molecules and avoiding of possible emissions of radionuclides, heavy metals and chemically hazardous species. Some contaminations cannot be removed from surface using common decontamination methods. Conditioning of ash residues obtained after treatment of solid radioactive waste including ashes received from treating problematic wastes also is a complicated task. Moreover due to relative small volume of specific type radioactive waste the development of target treatment procedures and facilities to conduct technological processes and their deployment could be economically unexpedient and ecologically no justified. Thermochemical processing technologies are used for treating and conditioning problematic radioactive wastes. The thermochemical processing uses powdered metal fuels (PMF) that are specifically formulated for the waste composition and react chemically with the waste components. The composition of the PMF is designed in such a way as to minimize the release of hazardous components and radionuclides in the off gas and to confine the contaminants in the ash residue. The thermochemical procedures allow decomposition of organic matter and capturing hazardous radionuclides and chemical species simultaneously. A significant advantage of thermochemical processing is its autonomy. Thermochemical treatment technologies use the energy of exothermic reactions in the mixture of radioactive or hazardous waste with PMF. When used energy of exothermic reactions in waste thermochemical treatment processing, the problems concerned with heating method choice, appropriate heating equipment operation, and maintenance of this equipment reliability are excluded. Generally, the PMF consists of combustible powder metal, oxygen containing component, and some additives (pore-forming materials, stabilizers, surface-active substances, and other) with a predominance of metal powder. A thermodynamic simulation is applied widely at the designing of the PMF.

Ojovan, M. I.; Sobolev, I. A.; Dmitriev, S. A.; Panteleev, V. I.; Karlina, O. K.; Klimov. V. L.

2003-02-25

3

Radioactive Waste.  

ERIC Educational Resources Information Center

|Presents a literature review of radioactive waste disposal, covering publications of 1976-77. Some of the studies included are: (1) high-level and long-lived wastes, and (2) release and burial of low-level wastes. A list of 42 references is also presented. (HM)|

Blaylock, B. G.

1978-01-01

4

Radioactive Wastes  

NSDL National Science Digital Library

The purposes of this module are to develop multiple representations for decay of radioactive substances, in the context of environmental policies on a university campus, and to determine storage times for wastes to decay to safe levels for disposal.

Smith, David; Moore, Lang

2000-09-02

5

Radioactive Wastes  

NSDL National Science Digital Library

This module develops multiple representations for decay of radioactive substances, in the context of environmental policies on a university campus, and discusses storage times for wastes to decay to safe levels for disposal.

Smith, David

2000-09-02

6

Radioactive wastes  

Microsoft Academic Search

A review is presented of the treatment, storage, fixation and disposal of radioactive wastes. Various methods are described for extracting and separating the radionuclides, for example ¹³⁴Cs, ¹³⁷Cs, ²°⁴Tl and ⁶°Co ions were simultaneously deactivated on natural sorbents by precipitation reactions. For long term storage, wastes should be solidified and immobilized to ensure containment, reduce surveillance, and reduce the need

Straub

1977-01-01

7

Radioactive Wastes  

NSDL National Science Digital Library

Created by David Smith for the Connected Curriculum Project, this module develops multiple representations for decay of radioactive substances, in the context of environmental policies on a university campus, and discusses storage times for wastes to decay to safe levels for disposal. This is one of a much larger set of learning modules hosted by Duke University.

Smith, David

2010-04-29

8

Radioactive Wastes  

NSDL National Science Digital Library

Created by Lang Moore and David Smith for the Connected Curriculum Project, the purposes of this module are to develop multiple representations for decay of radioactive substances, in the context of environmental policies on a university campus, and to determine storage times for wastes to decay to safe levels for disposal. This is one lesson within a larger set of learning modules hosted by Duke University.

Smith, David; Moore, Lang

2010-07-06

9

Radioactive waste material disposal  

DOEpatents

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

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

1995-01-01

10

Radioactive Waste Management Basis  

SciTech Connect

The purpose of this Radioactive Waste Management Basis is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE Manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Perkins, B K

2009-06-03

11

Understanding radioactive waste  

SciTech Connect

This document contains information on all aspects of radioactive wastes. Facts are presented about radioactive wastes simply, clearly and in an unbiased manner which makes the information readily accessible to the interested public. The contents are as follows: questions and concerns about wastes; atoms and chemistry; radioactivity; kinds of radiation; biological effects of radiation; radiation standards and protection; fission and fission products; the Manhattan Project; defense and development; uses of isotopes and radiation; classification of wastes; spent fuels from nuclear reactors; storage of spent fuel; reprocessing, recycling, and resources; uranium mill tailings; low-level wastes; transportation; methods of handling high-level nuclear wastes; project salt vault; multiple barrier approach; research on waste isolation; legal requiremnts; the national waste management program; societal aspects of radioactive wastes; perspectives; glossary; appendix A (scientific American articles); appendix B (reference material on wastes). (ATT)

Murray, R.L.

1981-12-01

12

Radioactive Wastes. Revised.  

ERIC Educational Resources Information Center

|This publication is one of a series of information booklets for the general public published by the United States Atomic Energy Commission. This booklet deals with the handling, processing and disposal of radioactive wastes. Among the topics discussed are: The Nature of Radioactive Wastes; Waste Management; and Research and Development. There are

Fox, Charles H.

13

ORNL radioactive waste operations  

Microsoft Academic Search

Since its beginning in 1943, ORNL has generated large amounts of solid, liquid, and gaseous radioactive waste material as a by-product of the basic research and development work carried out at the laboratory. The waste system at ORNL has been continually modified and updated to keep pace with the changing release requirements for radioactive wastes. Major upgrading projects are currently

J. D. Sease; E. M. King; J. H. Coobs; T. H. Row

1982-01-01

14

Radioactive Waste Management.  

National Technical Information Service (NTIS)

Management of radioactive wastes is necessary to protect public health, public safety, and the environment from radioactive materials resulting from national defense programs, energy research and development, and commercial activities. Access to informati...

1990-01-01

15

Low-level radioactive waste from nuclear power generating stations: Characterization, classification and assessment of activated metals and waste streams  

SciTech Connect

Since the enactment of 10 CFR Part 61, additional difficult-to-measure long-lived radionuclides, not specified in Tables 1 2 of Part 61, have been identified (e.g., [sup 108m]Ag, [sup 93]Mo, [sup 36]Cl, [sup 10]Be, [sup 113m]Cd, [sup 121m]Sn, [sup 126]Sn, [sup 93m]Nb) that may be of concern in certain types of waste. These nuclides are primarily associated with activated metal and perhaps other nuclear power low-level waste (LLW) being sent to disposal facilities. The concentration of a radionuclide in waste materials is normally determined by direct measurement or by indirect calculational methods, such as using a scaling factor to relate inferred concentration of a difficult-to-measure radionuclide to another that is easily measured. The total disposal site inventory of certain difficult-to-measure radionuclides (e.g., [sup 14]C, [sup 129]I, and [sup 99]Tc) often control the total quantities of radioactive waste permitted in LLW burial facilities. Overly conservative scaling factors based on lower limits of detection (LLD), often used in the nuclear power industry to estimate these controlling nuclides, could lead to premature closure of a disposal facility. Samples of LLW (Class B and C activated metals [AM] and other waste streams) are being collected from operating nuclear power stations and analyzed for radionuclides covered in 10 CFR Part 61 and the additional difficult-to-measure radionuclides. This analysis will enhance the NRC's understanding of the distribution and projected quantities of radionuclides within AM and LLW streams from commercial nuclear power stations. This research will also provide radiological characterization of AM specimens for others to use in leach-rate and lysimeter experiments to determine nuclide releases and subsequent movement in natural soil environments.

Thomas, V.W.; Robertson, D.E.; Thomas, C.W.

1993-02-01

16

Low-level radioactive waste from nuclear power generating stations: Characterization, classification and assessment of activated metals and waste streams  

SciTech Connect

Since the enactment of 10 CFR Part 61, additional difficult-to-measure long-lived radionuclides, not specified in Tables 1 2 of Part 61, have been identified (e.g., {sup 108m}Ag, {sup 93}Mo, {sup 36}Cl, {sup 10}Be, {sup 113m}Cd, {sup 121m}Sn, {sup 126}Sn, {sup 93m}Nb) that may be of concern in certain types of waste. These nuclides are primarily associated with activated metal and perhaps other nuclear power low-level waste (LLW) being sent to disposal facilities. The concentration of a radionuclide in waste materials is normally determined by direct measurement or by indirect calculational methods, such as using a scaling factor to relate inferred concentration of a difficult-to-measure radionuclide to another that is easily measured. The total disposal site inventory of certain difficult-to-measure radionuclides (e.g., {sup 14}C, {sup 129}I, and {sup 99}Tc) often control the total quantities of radioactive waste permitted in LLW burial facilities. Overly conservative scaling factors based on lower limits of detection (LLD), often used in the nuclear power industry to estimate these controlling nuclides, could lead to premature closure of a disposal facility. Samples of LLW (Class B and C activated metals [AM] and other waste streams) are being collected from operating nuclear power stations and analyzed for radionuclides covered in 10 CFR Part 61 and the additional difficult-to-measure radionuclides. This analysis will enhance the NRC`s understanding of the distribution and projected quantities of radionuclides within AM and LLW streams from commercial nuclear power stations. This research will also provide radiological characterization of AM specimens for others to use in leach-rate and lysimeter experiments to determine nuclide releases and subsequent movement in natural soil environments.

Thomas, V.W.; Robertson, D.E.; Thomas, C.W.

1993-02-01

17

Canister arrangement for storing radioactive waste  

DOEpatents

The subject invention relates to a canister arrangement for jointly storing high level radioactive chemical waste and metallic waste resulting from the reprocessing of nuclear reactor fuel elements. A cylindrical steel canister is provided with an elongated centrally disposed billet of the metallic waste and the chemical waste in vitreous form is disposed in the annulus surrounding the billet.

Lorenzo, Donald K. (Knoxville, TN); Van Cleve, Jr., John E. (Kingston, TN)

1982-01-01

18

Engineering 'Deinococcus Radiodurans' for Metal Remediation in Radioactive Mixed Waste Sites. (Final Report, 1997-2004).  

National Technical Information Service (NTIS)

Immense volumes of radioactive waste were generated from the production of 46,000 nuclear weapons in the United States between 1945 and 1986. This is a period when national security priorities often surmounted concerns over the environment. Most wastes in...

M. J. Daly J. K. Fredrickson L. P. Wackett

2005-01-01

19

Radioactive waste disposal package  

DOEpatents

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

Lampe, Robert F. (Bethel Park, PA)

1986-01-01

20

Radioactive waste shredding: Preliminary evaluation  

SciTech Connect

The critical constraints for sizing solid radioactive and mixed wastes for subsequent thermal treatment were identified via a literature review and a survey of shredding equipment vendors. The types and amounts of DOE radioactive wastes that will require treatment to reduce the waste volume, destroy hazardous organics, or immobilize radionuclides and/or hazardous metals were considered. The preliminary steps of waste receipt, inspection, and separation were included because many potential waste treatment technologies have limits on feedstream chemical content, physical composition, and particle size. Most treatment processes and shredding operations require at least some degree of feed material characterization. Preliminary cost estimates show that pretreatment costs per unit of waste can be high and can vary significantly, depending on the processing rate and desired output particle size.

Soelberg, N.R.; Reimann, G.A.

1994-07-01

21

THERMODYNAMICS OF THE VOLATILIZATION OF ACTINIDE METALS IN THE HIGH-TEMPERATURE TREATMENT OF RADIOACTIVE WASTES  

EPA Science Inventory

We are proposing to perform a detailed study of the volatilization behavior of the U, Pu and possibly Am under conditions relevant to the thermal treatment (destruction) of actinide-containing organic-based mixed and radioactive wastes. The primary objective of this 3-year projec...

22

Incineration of Radioactive Waste.  

National Technical Information Service (NTIS)

In this study, made on contract for the Swedish Nuclear Power Inspectorate, different methods for incineration of radioactive wastes are reviewed. Operation experiences and methods under development are also discussed. The aim of incineration of radioacti...

C. Thegerstroem

1980-01-01

23

Process for treating radioactive waste  

Microsoft Academic Search

A process for treating radioactive sludge waste wasted in a nuclear power plant comprises the steps of pulverizing the radioactive sludge waste into dry powder which is combustible, burning the powder into ashes, and pelletizing the ashes. The radioactive sludge waste including granular ion-exchange resins, powder resins, filter sludge, etc. is reduced in volume by subjecting to combustion.

M. Hirano; S. Horiuchi

1985-01-01

24

Fusion reactor radioactive waste management  

Microsoft Academic Search

Quantities and compositions of non-tritium radioactive waste are estimated for some current conceptual fusion reactor designs, and disposal of large amounts of radioactive waste appears necessary. Although the initial radioactivity of fusion reactor and fission reactor wastes are comparable, the radionuclides in fusion reactor wastes are less hazardous and have shorter half-lives. Areas requiring further research are discussed.

J. D. Kaser; A. K. Postma; D. J. Bradley

1976-01-01

25

Microbiological treatment of radioactive wastes  

SciTech Connect

The ability of microorganisms which are ubiquitous throughout nature to bring about information of organic and inorganic compounds in radioactive wastes has been recognized. Unlike organic contaminants, metals cannot be destroyed, but must be either removed or converted to a stable form. Radionuclides and toxic metals in wastes may be present initially in soluble form or, after disposal may be converted to a soluble form by chemical or microbiological processes. The key microbiological reactions include (i) oxidation/reduction; (ii) change in pH and Eh which affects the valence state and solubility of the metal; (iii) production of sequestering agents; and (iv) bioaccumulation. All of these processes can mobilize or stabilize metals in the environment.

Francis, A.J.

1992-12-31

26

Radioactive waste shredding: Preliminary evaluation.  

National Technical Information Service (NTIS)

The critical constraints for sizing solid radioactive and mixed wastes for subsequent thermal treatment were identified via a literature review and a survey of shredding equipment vendors. The types and amounts of DOE radioactive wastes that will require ...

N. R. Soelberg G. A. Reimann

1994-01-01

27

Development of materials for the removal of metal ions from radioactive and non-radioactive waste streams  

NASA Astrophysics Data System (ADS)

Nuclear wastes that were generated during cold-war era from various nuclear weapon programs are presently stored in hundreds of tanks across the United States. The composition of these wastes is rather complex containing both radionuclides and heavy metals, such as 137Cs, 90Sr, Al, Pb, Cr, and Cd. In this study, chitosan based biosorbents were prepared to adsorb some of these metal ions. Chitosan is a partially acetylated glucosamine biopolymer encountered in the cell walls of fungi. In its natural form this material is soft and has a tendency to agglomerate or form gels. Various methods were used to modify chitosan to avoid these problems. Chitosan is generally available commercially in the form of flakes. For use in an adsorption system, chitosan was made in the form of beads to reduce the pressure drop in an adsorption column. In this research, spherical beads were prepared by mixing chitosan with perlite and then by dropwise addition of the slurry mixture into a NaOH precipitation bath. Beads were characterized using Fourier Transform InfraRed Spectroscopy (FTIR), Scanning Electron Microscopy (SEM), Energy dispersive spectroscopy (EDS), Tunneling Electron Microscopy (TEM), X-ray Photoelectron Spectroscopy (XPS), and Thermogravimetric Analysis (TGA). The SEM, EDS, and TEM data indicated that the beads were porous in nature. The TGA data showed that bead contained about 32% chitosan. The surface area, pore volume, and porosity of the beads were determined from the BET surface area that was measured using N2 as adsorbate at 77K. Adsorption and desorption of Cr(VI), Cr(III), Cd(II), U(VI), Cu(II), from aqueous solutions of these metal ions were studied to evaluate the adsorption capacities of the beads for these metals ions. Equilibrium adsorption data of these metals on the beads were found to correlate well with the Langmuir isotherm equation. Chitosan coated perlite beads had negligible adsorption capacity for Sr(II) and Cs(I). It was found that Fullers earth had very good capacity for these two metals. However, the mechanical strength of Fullers earth granules available commercially was not sufficient for use in a column. In this study chitosan was used as a binder to make Fullers earth beads and were used for adsorption of Cs(I) and Sr(II). (Abstract shortened by UMI.)

Hasan, Md. Shameem

28

PROCESSING OF RADIOACTIVE WASTE  

DOEpatents

A process for treating radioactive waste solutions prior to disposal is described. A water-soluble phosphate, borate, and/or silicate is added. The solution is sprayed with steam into a space heated from 325 to 400 deg C whereby a powder is formed. The powder is melted and calcined at from 800 to 1000 deg C. Water vapor and gaseous products are separated from the glass formed. (AEC)

Johnson, B.M. Jr.; Barton, G.B.

1961-11-14

29

Final disposal of radioactive waste  

NASA Astrophysics Data System (ADS)

In this paper the origin and properties of radioactive waste as well as its classification scheme (low-level waste - LLW, intermediate-level waste - ILW, high-level waste - HLW) are presented. The various options for conditioning of waste of different levels of radioactivity are reviewed. The composition, radiotoxicity and reprocessing of spent fuel and their effect on storage and options for final disposal are discussed. The current situation of final waste disposal in a selected number of countries is mentioned. Also, the role of the International Atomic Energy Agency with regard to the development and monitoring of international safety standards for both spent nuclear fuel and radioactive waste management is described.

Freiesleben, H.

2013-06-01

30

Radioactive Waste: Production, Storage, Disposal.  

National Technical Information Service (NTIS)

Radioactive wastes are the leftovers from the use of nuclear materials for the production of electricity, diagnosis and treatment of disease, and other purposes. The materials are either naturally occurring or man-made. Certain kinds of radioactive materi...

2002-01-01

31

Radioactive waste processing apparatus  

DOEpatents

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

Nelson, Robert E. (Lombard, IL); Ziegler, Anton A. (Darien, IL); Serino, David F. (Maplewood, MN); Basnar, Paul J. (Western Springs, IL)

1987-01-01

32

Radioactive Waste Streams: Waste Classification for Disposal.  

National Technical Information Service (NTIS)

Radioactive waste is a byproduct of nuclear weapons production, commercial nuclear power generation, and the naval reactor program. Waste byproducts also result from radioisotopes used for scientific, medical, and industrial purposes. The legislative defi...

A. Andrews

2006-01-01

33

Radioactive Waste Management  

NASA Astrophysics Data System (ADS)

Issues related to the management of radioactive wastes are presented with specific emphasis on high-level wastes generated as a result of energy and materials production using nuclear reactors. The final disposition of these high-level wastes depends on which nuclear fuel cycle is pursued, and range from once-through burning of fuel in a light water reactor followed by direct disposal in a geologic repository to more advanced fuel cycles (AFCs) where the spent fuel is reprocessed or partitioned to recover the fissile material (primarily 235U and 239Pu) as well as the minor actinides (MAs) (neptunium, americium, and curium) and some long-lived fission products (e.g., 99Tc and 129I). In the latter fuel cycle, the fissile materials are recycled through a reactor to produce more energy, the short-lived fission products are vitrified and disposed of in a geologic repository, and the minor actinides and long-lived fission products are converted to less radiotoxic or otherwise stable nuclides by a process called transmutation. The advantages and disadvantages of the various fuel cycle options and the challenges to the management of nuclear wastes they represent are discussed.

Baisden, P. A.; Atkins-Duffin, C. E.

34

High-Level Radioactive Waste.  

ERIC Educational Resources Information Center

|Presents a method to calculate the amount of high-level radioactive waste by taking into consideration the following factors: the fission process that yields the waste, identification of the waste, the energy required to run a 1-GWe plant for one year, and the uranium mass required to produce that energy. Briefly discusses waste disposal and

Hayden, Howard C.

1995-01-01

35

Radioactive waste processing apparatus  

DOEpatents

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

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

1985-08-30

36

Radioactive Waste Incineration: Status Report  

Microsoft Academic Search

Incineration is generally accepted as a method of reducing the volume of radioactive waste. In some cases, the resulting ash may have high concentrations of materials such as Plutonium or Uranium that are valuable materials for recycling. Incineration can also be effective in treating waste that contains hazardous chemicals as well as radioactive contamination. Despite these advantages, the number of

A. R. Diederich; M. J. Akins

2008-01-01

37

Radioactive waste disposal and geology  

Microsoft Academic Search

This book is an excellent, well-presented treatise on the nature and types of radioactive wastes, disposal alternatives and strategies, radionuclide release and disposal models, geologic repositories, natural analogues, subsea-bed options, and low-level wastes. The authors provide national and international perspectives on radioactive waste disposal problems. They carefully dissected each issue, treating its pros and cons equally. Moreover, they is careful

K. B. Krauskopf

1988-01-01

38

Apparatus for infectious radioactive waste  

SciTech Connect

This patent describes an apparatus for housing solid, radioactively and biologically contaminated waste during steam autoclave treatment thereof. It comprises a container means for housing solid infectious radioactive biological wastes, suitable for use during an autoclaving procedure, having at least one opening therein; a filter means for entrapping radioactive compounds contained in gases exiting the container means during autoclave treatment, the filter means being securely disposed within an opening of the container means such that any gas exiting the container means during autoclave treatment passes through the filter means; and indicator means for establishing that the biologically contaminated waste has been inactivated by exposure to a predetermined autoclaving temperature.

Stinson, M.C.; Galanek, M.S.

1991-11-19

39

Radioactive Waste Processing and Disposal.  

National Technical Information Service (NTIS)

The Technical Information Center, beginning in 1958, periodically issues bibliographies on radioactive wastes. This compilation contains 4144 citations of foreign and domestic research reports, journal articles, patents, conference proceedings, and books....

1980-01-01

40

Radioactive Waste Processing and Disposal.  

National Technical Information Service (NTIS)

The Technical Information Center, beginning in 1958, periodically issues bibliographies on radioactive wastes. This compilation contains 3597 citations of foreign and domestic research reports, journal articles, patents, conference proceedings, and books....

1980-01-01

41

TREATMENT OF RADIOACTIVE WASTE GASES  

Microsoft Academic Search

The disposal of radioactive waste gases from the plant-scale processes ; at the Hanford Atomic Products Operation presents a problem that is of ; coniderable importance in plant operation. Equipment developed for the efficicnt ; removal of the two prinipal contaminants: 1) gaseous radioactive iodine; and 2) ; an aerosol composed of other fission products is described. The program has

A. G. Blasewitz; W. C. Schmidt

1958-01-01

42

Electrochemical treatment of mixed (hazardous and radioactive) wastes  

Microsoft Academic Search

Electrochemical treatment technologies for mixed hazardous waste are currently under development at Los Alamos National Laboratory. For a mixed waste containing toxic components such as heavy metals and cyanides in addition to a radioactive component, the toxic components can be removed or destroyed by electrochemical technologies allowing for recovery of the radioactive component prior to disposal of the solution. Mixed

J. Dziewinski; C. Zawodzinski; W. H. Smith

1995-01-01

43

75 FR 68840 - Request for a License To Import Radioactive Waste  

Federal Register 2010, 2011, 2012, 2013

...NUCLEAR REGULATORY COMMISSION Request for a License To Import Radioactive Waste Pursuant to 10 CFR 110.70 (b) ``Public Notice...Oregon Specialty Metals......... Radioactive Waste 186,000 kilograms Return of U.S. Canada...

2010-11-09

44

Crystallization of sodium nitrate from radioactive waste  

SciTech Connect

From the 1940s to the 1980s, the Institute of Physical Chemistry of the Russian Academy of Sciences (IPC/RAS) conducted research and development on processes to separate acetate and nitrate salts and acetic acid from radioactive wastes by crystallization. The research objective was to decrease waste volumes and produce the separated decontaminated materials for recycle. This report presents an account of the IPC/RAS experience in this field. Details on operating conditions, waste and product compositions, decontamination factors, and process equipment are described. The research and development was generally related to the management of intermediate-level radioactive wastes. The waste solutions resulted from recovery and processing of uranium, plutonium, and other products from irradiated nuclear fuel, neutralization of nuclear process solutions after extractant recovery, regeneration of process nitric acid, equipment decontamination, and other radiochemical processes. Waste components include nitric acid, metal nitrate and acetate salts, organic impurities, and surfactants. Waste management operations generally consist of two stages: volume reduction and processing of the concentrates for storage, solidification, and disposal. Filtration, coprecipitation, coagulation, evaporation, and sorption were used to reduce waste volume. 28 figs., 40 tabs.

Krapukhin, V.B.; Krasavina, E.P. Pikaev, A.K. [Russian Academy of Sciences, Moscow (Russian Federation). Institute of Physical Chemistry

1997-07-01

45

Radioactive Waste Incineration: Status Report  

SciTech Connect

Incineration is generally accepted as a method of reducing the volume of radioactive waste. In some cases, the resulting ash may have high concentrations of materials such as Plutonium or Uranium that are valuable materials for recycling. Incineration can also be effective in treating waste that contains hazardous chemicals as well as radioactive contamination. Despite these advantages, the number of operating incinerators currently in the US currently appears to be small and potentially declining. This paper describes technical, regulatory, economic and political factors that affect the selection of incineration as a preferred method of treating radioactive waste. The history of incinerator use at commercial and DOE facilities is summarized, along with the factors that have affected each of the sectors, thus leading to the current set of active incinerator facilities. In summary: Incineration has had a long history of use in radioactive waste processing due to their ability to reduce the volume of the waste while destroying hazardous chemicals and biological material. However, combinations of technical, regulatory, economic and political factors have constrained the overall use of incineration. In both the Government and Private sectors, the trend is to have a limited number of larger incineration facilities that treat wastes from a multiple sites. Each of these sector is now served by only one or two incinerators. Increased use of incineration is not likely unless there is a change in the factors involved, such as a significant increase in the cost of disposal. Medical wastes with low levels of radioactive contamination are being treated effectively at small, local incineration facilities. No trend is expected in this group. (authors)

Diederich, A.R.; Akins, M.J. [WorleyParsons, Reading, PA (United States)

2008-07-01

46

Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility  

Microsoft Academic Search

The purpose of this plan is to describe the organization and methodology for the certification of radioactive mixed waste (RMW) handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). RMW is low-level radioactive waste (LLW) or transuranic (TRU) waste that is co-contaminated with dangerous waste as defined in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria

1992-01-01

47

Source, Transport and Dumping of Radioactive Waste.  

National Technical Information Service (NTIS)

The results of an examination into the problems of radioactive waste are presented, in particular the sources, transport and dumping and the policy considerations in favour of specific methods. The theoretical background of radioactive waste is described,...

1980-01-01

48

Radioactive waste disposal in granite  

Microsoft Academic Search

The principal geotechnical problems in selecting a repository site for radioactive waste disposal in granite are to evaluate the suitability of the rock mass in terms of: (1) fracture characteristics, (2) thermomechanical effects, and (3) fracture hydrology. Underground experiments in a mine in Sweden have provided an opportunity to study these problems. The research has demonstrated the importance of hydrogeology

P. A. Witherspoon; D. J. Watkins

1982-01-01

49

Radioactive waste treatment technologies and environment  

Microsoft Academic Search

The radioactive waste treatment and conditioning are the most important steps in radioactive waste management. At the Slovak Electric, plc, a range of technologies are used for the processing of radioactive waste into a form suitable for disposal in near surface repository. These technologies operated by JAVYS, PLc. Nuclear and Decommissioning Company, PLc. Jaslovske Bohunice are described. Main accent is

Jan HORVATH; Dusan KRASNY

2007-01-01

50

"Final Report for Grant No. DE-FG02-97ER62492 "Engineering Deinococcus radiodurans for Metal Remediation in Radioactive Mixed Waste Sites"  

SciTech Connect

The groundwater and sediments of numerous U. S. Department of Energy (DOE) field sites are contaminated with mixtures of heavy metals (e.g., Hg, Cr, Pd) and radionuclides (e.g., U, Tc), as well as the fuel hydrocarbons benzene, toluene, ethylbenzene and xylenes (BTEX); chlorinated hydrocarbons, such as trichloroethylene (TCE); and polychlorinated biphenyls (PCBs). The remediation of such mixed wastes constitutes an immediate and complex waste management challenge for DOE, particularly in light of the costliness and limited efficacy of current physical and chemical strategies for treating mixed wastes. In situ bioremediation via natural microbial processes (e.g., metal reduction) remains a potent, potentially cost-effective approach to the reductive immobilization or detoxification of environmental contaminants. Seventy million cubic meters of soil and three trillion liters of groundwater have been contaminated by leaking radioactive waste generated in the United States during the Cold War. A cleanup technology is being developed based on the extremely radiation resistant bacterium Deinococcus radiodurans. Our recent isolation and characterization of D. radiodurans from a variety of DOE environments, including highly radioactive sediments beneath one of the leaking tanks (SX-108) at the Hanford Site in south-central Washington state, underscores the potential for this species to survive in such extreme environments. Research aimed at developing D. radiodurans for metal remediation in radioactive waste sites was started by this group in September 1997 with support from DOE NABIR grant DE-FG02-97ER62492. Our grant was renewed for the period 2000-2003, which includes work on the thermophilic radiation resistant bacterium Deinococcus geothermalis. Work funded by the existing grant contributed to 18 papers in the period 1997-2004 on the fundamental biology of D. radiodurans and its design for bioremediation of radioactive waste environments. Our progress since September 2000 closely matches the Aims proposed in our second NABIR application and is summarized as follows. We have further refined expression vectors for D. radiodurans and successfully tested engineered strains in natural DOE sediment and groundwater samples. Further, we have shown that D. geothermalis is transformable with plasmids and integration vectors designed for D. radiodurans. This was demonstrated by engineering Hg(II)-resistant D. geothermalis strains capable of reducing Hg(II) at elevated temperatures and under chronic irradiation. Additionally, we showed that D. geothermalis, like D. radiodurans, is naturally capable of reducing U(VI), Cr(VI), and Fe(III). These characteristics support the prospective development of this thermophilic radiophile for bioremediation of radioactive mixed waste environments with temperatures as high as 55 C, of which there are many examples. Our annotation of the D. radiodurans genome has been an important guide throughout this project period and continues to be a source of inspiration in the development of new genetic technologies dedicated to this bacterium. For example, our genome analyses have enabled us to achieve engineering goals that were unattainable in our first NABIR project (1997-2000), where uncertainties relating to its metabolic configuration prevented efforts to expand its metabolic capabilities. As just one example, we showed that D. radiodurans has a functioning tricarboxylic acid (TCA) cycle glyoxylate bypass which could be integrated with toluene oxidation. And, we successfully engineered D. radiodurans to derive carbon and energy from complete toluene mineralization and showed that toluene oxidation can be coupled to cellular biosynthesis, survival, as well as its native and engineered metal reducing capabilities. We have also constructed a whole genome microarray for D. radiodurans covering {approx}94% of its predicted genes and have successfully used the array to examine the response of cells to radiation and other DOE relevant conditions. Similarly, we have used high throughput proteomic approaches to

Michael J. Daly, Ph.D.

2005-03-17

51

Determination of a Radioactive Waste Classification System.  

National Technical Information Service (NTIS)

Several classification systems for radioactive wastes are reviewed and a system is developed that provides guidance on disposition of the waste. The system has three classes: high-level waste (HLW), which requires complete isolation from the biosphere for...

J. J. Cohen W. C. King

1978-01-01

52

Control of high level radioactive waste-glass melters. Part 6, Noble metal catalyzed formic acid decomposition, and formic acid/denitration  

SciTech Connect

A necessary step in Defense Waste Processing Facility (DWPF) melter feed preparation for the immobilization of High Level Radioactive Waste (HLW) is reduction of Hg(II) to Hg(0), permitting steam stripping of the Hg. Denitrition and associated NOx evolution is a secondary effect of the use of formic acid as the mercury-reducing agent. Under certain conditions the presence of transition or noble metals can result in significant formic acid decomposition, with associated CO{sub 2} and H{sub 2} evolution. These processes can result in varying redox properties of melter feed, and varying sequential gaseous evolution of oxidants and hydrogen. Electrochemical methods for monitoring the competing processes are discussed. Laboratory scale techniques have been developed for simulating the large-scale reactions, investigating the relative effectiveness of the catalysts, and the effectiveness of catalytic poisons. The reversible nitrite poisoning of formic acid catalysts is discussed.

Bickford, D.F.; Coleman, C.J.; Hsu, C.L.W.; Eibling, R.E.

1990-12-31

53

PROCESSING OF RADIOACTIVE WASTE  

DOEpatents

A process for concentrating fission-product-containing waste solutions from fuel element processing is described. The process comprises the addition of sugar to the solution, preferably after it is made alkaline; spraying the solution into a heated space whereby a dry powder is formed; heating the powder to at least 220 deg C in the presence of oxygen whereby the powder ignites, the sugar is converted to carbon, and the salts are decomposed by the carbon; melting the powder at between 800 and 900 deg C; and cooling the melt. (AEC) antidiuretic hormone from the blood by the liver. Data are summarized from the following: tracer studies on cardiovascular functions; the determination of serum protein-bound iodine; urinary estrogen excretion in patients with arvanced metastatic mammary carcinoma; the relationship between alheroclerosis aad lipoproteins; the physical chemistry of lipoproteins; and factors that modify the effects of densely ionizing radia

Allemann, R.T.; Johnson, B.M. Jr.

1961-10-31

54

Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities  

SciTech Connect

One critical aspect of any denuclearization of the Democratic Peoples Republic of Korea (DPRK) involves dismantlement of its nuclear facilities and management of their associated radioactive wastes. The decommissioning problem for its two principal operational plutonium facilities at Yongbyun, the 5MWe nuclear reactor and the Radiochemical Laboratory reprocessing facility, alone present a formidable challenge. Dismantling those facilities will create radioactive waste in addition to existing inventories of spent fuel and reprocessing wastes. Negotiations with the DPRK, such as the Six Party Talks, need to appreciate the enormous scale of the radioactive waste management problem resulting from dismantlement. The two operating plutonium facilities, along with their legacy wastes, will result in anywhere from 50 to 100 metric tons of uranium spent fuel, as much as 500,000 liters of liquid high-level waste, as well as miscellaneous high-level waste sources from the Radiochemical Laboratory. A substantial quantity of intermediate-level waste will result from disposing 600 metric tons of graphite from the reactor, an undetermined quantity of chemical decladding liquid waste from reprocessing, and hundreds of tons of contaminated concrete and metal from facility dismantlement. Various facilities for dismantlement, decontamination, waste treatment and packaging, and storage will be needed. The shipment of spent fuel and liquid high level waste out of the DPRK is also likely to be required. Nuclear facility dismantlement and radioactive waste management in the DPRK are all the more difficult because of nuclear nonproliferation constraints, including the call by the United States for complete, verifiable and irreversible dismantlement, or CVID. It is desirable to accomplish dismantlement quickly, but many aspects of the radioactive waste management cannot be achieved without careful assessment, planning and preparation, sustained commitment, and long completion times. The radioactive waste management problem in fact offers a prospect for international participation to engage the DPRK constructively. DPRK nuclear dismantlement, when accompanied with a concerted effort for effective radioactive waste management, can be a mutually beneficial goal.

Jooho, W.; Baldwin, G. T.

2005-04-01

55

Radioactive Waste Management BasisSept 2001  

SciTech Connect

This Radioactive Waste Management Basis (RWMB) documents radioactive waste management practices adopted at Lawrence Livermore National Laboratory (LLNL) pursuant to Department of Energy (DOE) Order 435.1, Radioactive Waste Management. The purpose of this RWMB is to describe the systematic approach for planning, executing, and evaluating the management of radioactive waste at LLNL. The implementation of this document will ensure that waste management activities at LLNL are conducted in compliance with the requirements of DOE Order 435.1, Radioactive Waste Management, and the Implementation Guide for DOE manual 435.1-1, Radioactive Waste Management Manual. Technical justification is provided where methods for meeeting the requirements of DOE Order 435.1 deviate from the DOE Manual 435.1-1 and Implementation Guide.

Goodwin, S S

2011-08-31

56

Membrane Treatment of Liquid Salt Bearing Radioactive Wastes  

SciTech Connect

The main fields of introduction and application of membrane methods for preliminary treatment and processing salt liquid radioactive waste (SLRW) can be nuclear power stations (NPP) and enterprises on atomic submarines (AS) utilization. Unlike the earlier developed technology for the liquid salt bearing radioactive waste decontamination and concentrating this report presents the new enhanced membrane technology for the liquid salt bearing radioactive waste processing based on the state-of-the-art membrane unit design, namely, the filtering units equipped with the metal-ceramic membranes of ''TruMem'' brand, as well as the electrodialysis and electroosmosis concentrators. Application of the above mentioned units in conjunction with the pulse pole changer will allow the marked increase of the radioactive waste concentrating factor and the significant reduction of the waste volume intended for conversion into monolith and disposal. Besides, the application of the electrodialysis units loaded with an ion exchange material at the end polishing stage of the radioactive waste decontamination process will allow the reagent-free radioactive waste treatment that meets the standards set for the release of the decontaminated liquid radioactive waste effluents into the natural reservoirs of fish-farming value.

Dmitriev, S. A.; Adamovich, D. V.; Demkin, V. I.; Timofeev, E. M.

2003-02-25

57

Overview of Radioactive Waste Disposal at Sea  

Microsoft Academic Search

For hundreds of years, the seas have been used as a place to dispose of wastes from human activities. Although no high level radioactive waste has been disposed of into the sea, variable amounts of packaged low level radioactive wastes have been dumped at 47 sites in the northern part of the Atlantic and Pacific Oceans. in 1946 the first

Dominique Calmet

1992-01-01

58

Acid digestion of combustible radioactive wastes  

Microsoft Academic Search

The following conclusions resulted from operation of Radioactive Acid Digestion Test Unit (RADTU) for processing transuranic waste: (1) the acid digestion process can be safely and efficiently operated for radioactive waste treatment.; (2) in transuranic waste treatment, there was no detectable radionuclide carryover into the exhaust off-gas. The plutonium decontamination factor (DF) between the digester and the second off-gas tower

C. R. Allen; R. E. Lerch; M. D. Crippen; R. G. Cowan

1982-01-01

59

Removal of Radioactive Cesium from Nuclear Waste Solutions with the Transition Metal Hexacyanoferrate Ion Exchanger CsTreat  

SciTech Connect

A transition metal hexacyanoferrate product CsTreat has been utilized at industrial scale for radioactive cesium separation at several nuclear power plants (NPPs) in several countries. A granular hexacyanoferrate ion exchanger has been used in packed-bed column mode operations for the removal of cesium from a variety of wastewater types. CsTreat beds have successfully purified both high-salt evaporator concentrates and dilute floor drain waters at NPPs in Finland and the United States. Furthermore, medium-active reprocessing solutions, containing high concentrations of sodium nitrate, have been decontaminated by a CsTreat bed at the Japan Atomic Energy Research Institute. These solutions are described as are other industrial applications of this ion exchange material, which, of all the commercial materials, has been shown to be the most selective exchanger for cesium. In addition, some prospective fields of hexacyanoferrate utilization, such as the use of CsTreat powder in a precoat filtration system, are discussed.

Harjula, R. [University of Helsinki (Finland); Lehto, J. [University of Helsinki (Finland); Paajanen, A. [University of Helsinki (Finland); Brodkin, L. [University of Helsinki (Finland); Tusa, E. [Fortum Engineering (Finland)

2001-02-15

60

Liquid radioactive waste subsystem design description  

SciTech Connect

The Liquid Radioactive Waste Subsystem provides a reliable system to safely control liquid waste radiation and to collect, process, and dispose of all radioactive liquid waste without impairing plant operation. Liquid waste is stored in radwaste receiver tanks and is processed through demineralizers and temporarily stored in test tanks prior to sampling and discharge. Radwastes unsuitable for discharge are transferred to the Solid Radwaste System.

NONE

1986-06-01

61

A glass-encapsulated calcium phosphate wasteform for the immobilization of actinide-, fluoride-, and chloride-containing radioactive wastes from the pyrochemical reprocessing of plutonium metal  

NASA Astrophysics Data System (ADS)

Chloride-containing radioactive wastes are generated during the pyrochemical reprocessing of Pu metal. Immobilization of these wastes in borosilicate glass or Synroc-type ceramics is not feasible due to the very low solubility of chlorides in these hosts. Alternative candidates have therefore been sought including phosphate-based glasses, crystalline ceramics and hybrid glass/ceramic systems. These studies have shown that high losses of chloride or evolution of chlorine gas from the melt make vitrification an unacceptable solution unless suitable off-gas treatment facilities capable of dealing with these corrosive by-products are available. On the other hand, both sodium aluminosilicate and calcium phosphate ceramics are capable of retaining chloride in stable mineral phases, which include sodalite, Na8(AlSiO4)6Cl2, chlorapatite, Ca5(PO4)3Cl, and spodiosite, Ca2(PO4)Cl. The immobilization process developed in this study involves a solid state process in which waste and precursor powders are mixed and reacted in air at temperatures in the range 700 800 C. The ceramic products are non-hygroscopic free-flowing powders that only require encapsulation in a relatively low melting temperature phosphate-based glass to produce a monolithic wasteform suitable for storage and ultimate disposal.

Donald, I. W.; Metcalfe, B. L.; Fong, S. K.; Gerrard, L. A.; Strachan, D. M.; Scheele, R. D.

2007-03-01

62

Handling and treatment of low-level radioactive wastes from United States gaseous diffusion plants  

Microsoft Academic Search

The US gaseous diffusion plants currently generate very small quantities of low-level radioactive wastes. These wastes consist primarily of airborne effluent solid trapping media and liquid scrubber solutions; liquid effluent treatment sludges; waste oils and solvents; scrap metals; and conventional combustible wastes such as floor sweepings, cleaning rags, and shoe covers. In addition to waste emanating from current operations, large

J. F. Wing; M. E. Mitchell; J. E. Behrend

1983-01-01

63

Control of high level radioactive waste-glass melters. Part 6, Noble metal catalyzed formic acid decomposition, and formic acid/denitration.  

National Technical Information Service (NTIS)

A necessary step in Defense Waste Processing Facility (DWPF) melter feed preparation for the immobilization of High Level Radioactive Waste (HLW) is reduction of Hg(II) to Hg(0), permitting steam stripping of the Hg. Denitrition and associated NOx evoluti...

D. F. Bickford C. J. Coleman C. L. W. Hsu R. E. Eibling

1990-01-01

64

Hanford Site annual dangerous waste report: Volume 4, Waste Management Facility report, Radioactive mixed waste  

SciTech Connect

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

NONE

1994-12-31

65

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

SciTech Connect

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

NONE

1994-12-31

66

The safe disposal of radioactive wastes  

PubMed Central

A comprehensive review is given of the principles and problems involved in the safe disposal of radioactive wastes. The first part is devoted to a study of the basic facts of radioactivity and of nuclear fission, the characteristics of radioisotopes, the effects of ionizing radiations, and the maximum permissible levels of radioactivity for workers and for the general public. In the second part, the author describes the different types of radioactive wastereactor wastes and wastes arising from the use of radioisotopes in hospitals and in industryand discusses the application of the maximum permissible levels of radioactivity to their disposal and treatment, illustrating his discussion with an account of the methods practised at the principal atomic energy establishments.

Kenny, A. W.

1956-01-01

67

Repository for radioactive waste-vault backfill  

US Patent & Trademark Office Database

A method of forming a repository for radioactive waste comprises locating the waste in a subterranean vault and backfilling the vault with a filling material which is water permeable and provides a substantial reservoir of available alkalinity such that any ground water permeating through the filling material to the waste has a pH of at least 10.5.

Hooper; Alan James (Gloucester, GB)

1998-04-14

68

EVALUATION OF BITUMENS FOR RADIOACTIVE WASTE IMMOBILIZATION  

Microsoft Academic Search

The Brazilian research center CDTN - Centro de Desenvolvimento da Tecnologia Nuclear - has been carrying out research on the incorporation of radioactive wastes in different types of bitumen, aiming to obtain monolithic, homogeneous, chemically and mechanically stable waste forms. The solidification of waste is mandatory if compliance with the safety standards for transport, storage and disposal are sought. The

Marcia Flavia; Righi Guzella; Tnia Valria da Silva

69

Evaluation of radioactive scrap metal recycling  

SciTech Connect

This report evaluates the human health risks and environmental and socio-political impacts of options for recycling radioactive scrap metal (RSM) or disposing of and replacing it. Argonne National Laboratory (ANL) is assisting the US Department of Energy (DOE), Office of Environmental Restoration and Waste Management, Oak Ridge Programs Division, in assessing the implications of RSM management alternatives. This study is intended to support the DOE contribution to a study of metal recycling being conducted by the Task Group on Recycling and Reuse of the Organization for Economic Cooperation and Development. The focus is on evaluating the justification for the practice of recycling RSM, and the case of iron and steel scrap is used as an example in assessing the impacts. To conduct the evaluation, a considerable set of data was compiled and developed. Much of this information is included in this document to provide a source book of information.

Nieves, L.A.; Chen, S.Y.; Kohout, E.J.; Nabelssi, B.; Tilbrook, R.W.; Wilson, S.E.

1995-12-01

70

Radioactive Waste: Resources for Environmental Literacy  

NSDL National Science Digital Library

Since World War II, hundreds of thousands of tons of radioactive materials have been produced in the United States. How we will dispose of nuclear waste is a controversial issue with a large technical component. This book provides a useful resource for enhancing student understanding of the physics of radioactivity as well as the storage and disposal of radioactive waste. It encourages students to discuss these complex environmental issues using arguments based on the science behind issues related to radioactivity, technology, risk assessment, and tradeoffs.

Council, Environmental L.; National Science Teachers Association (NSTA)

2007-05-16

71

Cross flow filtration of aqueous radioactive tank wastes  

SciTech Connect

The Tank Focus Area (TFA) of the Department of Energy (DOE) Office of Science and Technology addresses remediation of radioactive waste currently stored in underground tanks. Baseline technologies for treatment of tank waste can be categorized into three types of solid liquid separation: (a) removal of radioactive species that have been absorbed or precipitated, (b) pretreatment, and (c) volume reduction of sludge and wash water. Solids formed from precipitation or absorption of radioactive ions require separation from the liquid phase to permit treatment of the liquid as Low Level Waste. This basic process is used for decontamination of tank waste at the Savannah River Site (SRS). Ion exchange of radioactive ions has been proposed for other tank wastes, requiring removal of insoluble solids to prevent bed fouling and downstream contamination. Additionally, volume reduction of washed sludge solids would reduce the tank space required for interim storage of High Level Wastes. The scope of this multi-site task is to evaluate the solid/liquid separations needed to permit treatment of tank wastes to accomplish these goals. Testing has emphasized cross now filtration with metal filters to pretreat tank wastes, due to tolerance of radiation and caustic.

McCabe, D.J. [Westinghouse Savannah River Co., Aiken, SC (United States); Reynolds, B.A. [Battelle Pacific Northwest Lab., Richland, WA (United States); Todd, T.A. [Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States); Wilson, J.H. [Oak Ridge National Lab., TN (United States)

1997-02-01

72

Particulate collection in a low level radioactive waste incinerator  

Microsoft Academic Search

As designed, sintered stainless steel filters will clean the gas from the secondary cyclone at a low level radioactive waste incinerator. Bench-scale apparatus was used to evaluate asbestos floats and diatomaceous earth as filter aids to prevent clogging of the sintered metal interstices and to decrease filter penetration. Both precoats prevented irreversible pressure drop increase, and decreased cold DOP penetration

S. N. Rudnick; D. Leith; M. W. First

1976-01-01

73

Evaluation of Terrorist Interest in Radioactive Wastes  

SciTech Connect

Since September 11, 2001, intelligence gathered from Al Qaeda training camps in Afghanistan, and the ensuing terrorist activities, indicates nuclear material security concerns are valid. This paper reviews available information on sealed radioactive sources thought to be of interest to terrorists, and then examines typical wastes generated during environmental management activities to compare their comparative 'attractiveness' for terrorist diversion. Sealed radioactive sources have been evaluated in numerous studies to assess their security and attractiveness for use as a terrorist weapon. The studies conclude that tens of thousands of curies in sealed radioactive sources are available for potential use in a terrorist attack. This risk is mitigated by international efforts to find lost and abandoned sources and bring them under adequate security. However, radioactive waste has not received the same level of scrutiny to ensure security. This paper summarizes the activity and nature of radioactive sources potentially available to international terrorists. The paper then estimates radiation doses from use of radioactive sources as well as typical environmental restoration or decontamination and decommissioning wastes in a radioactive dispersal device (RDD) attack. These calculated doses indicate that radioactive wastes are, as expected, much less of a health risk than radioactive sources. The difference in radiation doses from wastes used in an RDD are four to nine orders of magnitude less than from sealed sources. We then review the International Atomic Energy Agency (IAEA) definition of 'dangerous source' in an adjusted comparison to common radioactive waste shipments generated in environmental management activities. The highest waste dispersion was found to meet only category 1-3.2 of the five step IAEA scale. A category '3' source by the IAEA standard 'is extremely unlikely, to cause injury to a person in the immediate vicinity'. The obvious conclusion of the analysis is that environmental management generated radioactive wastes have substantially less impact than radioactive sources if dispersed by terrorist-induced explosion or fire. From a health standpoint, the impact is very small. However, there is no basis to conclude that wastes are totally unattractive for use in a disruptive or economic damage event. Waste managers should be cognizant of this potential and take measures to ensure security of stored waste and waste shipments. (authors)

McFee, J.N.; Langsted, J.M.; Young, M.E. [Shaw Environmental and Infrastructure, Inc., 9201 East Dry Creek Rd. Centennial, CO 80112 (United States); Day, J.E. [Shaw Environmental and Infrastructure, Inc., 1725 Duke St, Suite 400, Alexandria, VA 22314 (United States)

2006-07-01

74

Basic chemistry for radioactive waste management. Studies on the chemical behaviors of radioactive elements.  

National Technical Information Service (NTIS)

The goal of this study is to obtain the information about the chemical behavior of radionuclides in groundwater for the safety of radioactive waste management. The effect of o-phenanthroline and 2,2'-bipyridine on the adsorption of metal(II) (Mn, Fe, Co, ...

T. Y. Eom K. K. Park W. H. Kim K. Y. Jee J. K. Kim

1992-01-01

75

[The investigation of the composition of liquid radioactive waste].  

PubMed

In investigation the process of composition sediment of liquid unorganic radioactive waste, that are forming in cistern-selectors at PNPI RAS, it was discovered apart from great quantity of ions of different metals and radionuclides considerable maintenance of organic material (to 30% and more from volume of sediment) unknown origin. A supposition was made about its microbiological origin. Investigation shows, that the main microorganisms, setting this sediment, are the bacterious of Pseudomonas kind, capable of effectively bind in process of grow the radionuclide 90Sr, that confirms the potential posibility of using this microorganisms for bioremediation of liquid low radioactive wastes (LRW). PMID:18825999

Suslov, A V; Suslova, I N; Bagiian, A; Leonov, V V; Kapustin, V K

76

Low-Level Radioactive Biomedical Wastes.  

National Technical Information Service (NTIS)

A summary of the management and hazards of low-level radioactive biomedical wastes is presented. The volume, disposal methods, current problems, regulatory agencies, and possible solutions to disposal problems are discussed. The benefits derived from usin...

G. W. Casarett

1978-01-01

77

Legal Approach to Radioactive Waste Management.  

National Technical Information Service (NTIS)

The authors of this paper review the major legal problems raised by radioactive waste management. They stress the complexity of such problems by posing three main queries: surveillance or no surveillance; liability or no liability and finally internationa...

B. Derche P. Rocamora A. Salelles

1983-01-01

78

Control of high level radioactive waste-glass melters. Part 6, Noble metal catalyzed formic acid decomposition, and formic acid\\/denitration  

Microsoft Academic Search

A necessary step in Defense Waste Processing Facility (DWPF) melter feed preparation for the immobilization of High Level Radioactive Waste (HLW) is reduction of Hg(II) to Hg(0), permitting steam stripping of the Hg. Denitrition and associated NOx evolution is a secondary effect of the use of formic acid as the mercury-reducing agent. Under certain conditions the presence of transition or

D. F. Bickford; C. J. Coleman; C. L. W. Hsu; R. E. Eibling

1990-01-01

79

Hazardous chemical and radioactive wastes at Hanford  

SciTech Connect

The Hanford Site was established in 1944 to produce plutonium for defense. During the past four decades, a number of reactors, processing facilities, and waste management facilities have been built at Hanford for plutonium production. Generally, Hanford`s 100 Area was dedicated to reactor operation; the 200 Area to fuel reprocessing, plutonium recovery, and waste management; and the 300 Area to fuel fabrication and research and development. Wastes generated from these operations included highly radioactive liquid wastes, which were discharged to single- and double-shell tanks; solid wastes, including both transuranic (TRU) and low-level wastes, which were buried or discharged to caissons; and waste water containing low- to intermediate-level radioactivity, which was discharged to the soil column via near-surface liquid disposal units such as cribs, ponds, and retention basins. Virtually all of the wastes contained hazardous chemical as well as radioactive constituents. This paper will focus on the hazardous chemical components of the radioactive mixed waste generated by plutonium production at Hanford. The processes, chemicals used, methods of disposition, fate in the environment, and actions being taken to clean up this legacy are described by location.

Keller, J.F.; Stewart, T.L.

1991-07-01

80

Hazardous chemical and radioactive wastes at Hanford  

SciTech Connect

The Hanford Site was established in 1944 to produce plutonium for defense. During the past four decades, a number of reactors, processing facilities, and waste management facilities have been built at Hanford for plutonium production. Generally, Hanford's 100 Area was dedicated to reactor operation; the 200 Area to fuel reprocessing, plutonium recovery, and waste management; and the 300 Area to fuel fabrication and research and development. Wastes generated from these operations included highly radioactive liquid wastes, which were discharged to single- and double-shell tanks; solid wastes, including both transuranic (TRU) and low-level wastes, which were buried or discharged to caissons; and waste water containing low- to intermediate-level radioactivity, which was discharged to the soil column via near-surface liquid disposal units such as cribs, ponds, and retention basins. Virtually all of the wastes contained hazardous chemical as well as radioactive constituents. This paper will focus on the hazardous chemical components of the radioactive mixed waste generated by plutonium production at Hanford. The processes, chemicals used, methods of disposition, fate in the environment, and actions being taken to clean up this legacy are described by location.

Keller, J.F.; Stewart, T.L.

1991-07-01

81

Radioactive waste management in a hospital.  

PubMed

Most of the tertiary care hospitals use radioisotopes for diagnostic and therapeutic applications. Safe disposal of the radioactive waste is a vital component of the overall management of the hospital waste. An important objective in radioactive waste management is to ensure that the radiation exposure to an individual (Public, Radiation worker, Patient) and the environment does not exceed the prescribed safe limits. Disposal of Radioactive waste in public domain is undertaken in accordance with the Atomic Energy (Safe disposal of radioactive waste) rules of 1987 promulgated by the Indian Central Government Atomic Energy Act 1962. Any prospective plan of a hospital that intends using radioisotopes for diagnostic and therapeutic procedures needs to have sufficient infrastructural and manpower resources to keep its ambient radiation levels within specified safe limits. Regular monitoring of hospital area and radiation workers is mandatory to assess the quality of radiation safety. Records should be maintained to identify the quality and quantity of radioactive waste generated and the mode of its disposal. Radiation Safety officer plays a key role in the waste disposal operations. PMID:21475524

Khan, Shoukat; Syed, At; Ahmad, Reyaz; Rather, Tanveer A; Ajaz, M; Jan, Fa

2010-01-01

82

Treatment methods for radioactive mixed wastes in commercial low-level wastes: technical considerations  

SciTech Connect

Treatment options for the management of three generic categories of radioactive mixed waste in commercial low-level wastes (LLW) have been identified and evaluated. These wastes were characterized as part of a BNL study in which LLW generators were surveyed for information on potential chemical hazards in their wastes. The general treatment options available for mixed wastes are destruction, immobilization, and reclamation. Solidification, absorption, incineration, acid digestion, wet-air oxidation, distillation, liquid-liquid wastes. Containment, segregation, decontamination, and solidification or containment of residues, have been considered for lead metal wastes which have themselves been contaminated and are not used for purposes of waste disposal shielding, packaging, or containment. For chromium-containing wastes, solidification, incineration, wet-air oxidation, acid digestion, and containment have been considered. For each of these wastes, the management option evaluation has included an assessment of testing appropriate to determine the effect of the option on both the radiological and potential chemical hazards present.

MacKenzie, D.R.; Kempf, C.R.

1986-01-01

83

77 FR 10401 - Low-Level Radioactive Waste Management Issues  

Federal Register 2010, 2011, 2012, 2013

...NRC-2011-0012] Low-Level Radioactive Waste Management Issues AGENCY: Nuclear Regulatory...assessment as part of its radioactive waste management decision-making. The DOE...Assessment Directorate, Division of Waste Management and Environmental...

2012-02-22

84

77 FR 26991 - Low-Level Radioactive Waste Management Issues  

Federal Register 2010, 2011, 2012, 2013

...3150-AI92 Low-Level Radioactive Waste Management Issues AGENCY: Nuclear Regulatory...and Low-Level Radioactive Waste Management'' (76 FR 50500; August...Assessment Directorate, Division of Waste Management and Environmental...

2012-05-08

85

Radionuclides, Heavy Metals, and Polychlorinate Biphenyls in Soils Collected Around the Perimeter of Low-Level Radioactive Waste Disposal Area G during 2006.  

National Technical Information Service (NTIS)

Twenty-one soil surface samples were collected in March around the perimeter of Area G, the primary disposal facility for low-level radioactive solid waste at Los Alamos National Laboratory (LANL). Three more samples were collected in October around the n...

2006-01-01

86

Radioactive-Waste Incineration at Purdue University.  

National Technical Information Service (NTIS)

A study conducted at Purdue University to evaluate the feasibility of using a small (45 kg/h), inexpensive (less than $10K) incinerator for incinerating low-level radioactive waste is described. An oil-fired, dual-chamber pathological waste incinerator wa...

1982-01-01

87

Notes on Incineration of Radioactive Waste.  

National Technical Information Service (NTIS)

The problem of finding commercial sites for the disposal of low-level radioactive waste and temporary storage of residues containing transuranic elements has led to research on using a method to reduce the volume of the waste originating from nuclear inst...

L. M. Martin

1984-01-01

88

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2008  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2008 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report.

West, B.; Waltz, R.

2009-06-11

89

Reduction of INTEC Analytical Radioactive Liquid Wastes  

SciTech Connect

This report details the evaluation of the reduction in radioactive liquid waste from the analytical laboratories sent to the Process Effluent Waste system (deep tanks). The contributors are the Analytical Laboratories Department (ALD), the Waste Operations Department, the laboratories at CPP-637, and natural run off. Other labs were contacted to learn the methods used and if any new technologies had emerged. A waste generation database was made from the current methods in used in the ALD. From this database, methods were targeted to reduce waste. Individuals were contacted on ways to reduce waste. The results are: a new method generating much less waste, several methods being handled differently, some cleaning processes being changed to reduce waste, and changes to reduce chemicals to waste.

V. J. Johnson; J. S. Hu; A. G. Chambers

1999-06-01

90

Reduction of INTEC Analytical Radioactive Liquid Waste  

SciTech Connect

This report details the evaluation of the reduction in radioactive liquid waste from the analytical laboratories sent to the Process Effluent Waste system (deep tanks). The contributors are the Analytical Laboratories Department (ALD), the Waste Operations Department, the laboratories at CPP-637, and natural run off. Other labs were contacted to learn of methods used and if any new technologies had emerged. A waste generation database was made from the current methods in use in the ALD. From this database, methods were targeted to reduce waste. Individuals were contacted on ways to reduce waste. The results are: a new method generating much less waste, several methods being handled differently, some cleaning processes being changed to reduce waste, and changes to reduce chemicals to waste.

Johnson, Virgil James; Hu, Jian Sheng; Chambers, Andrea

1999-06-01

91

Apparatus and method for radioactive waste screening  

SciTech Connect

An apparatus and method relating to screening radioactive waste are disclosed for ensuring that at least one calculated parameter for the measurement data of a sample falls within a range between an upper limit and a lower limit prior to the sample being packaged for disposal. The apparatus includes a radiation detector configured for detecting radioactivity and radionuclide content of the of the sample of radioactive waste and generating measurement data in response thereto, and a collimator including at least one aperture to direct a field of view of the radiation detector. The method includes measuring a radioactive content of a sample, and calculating one or more parameters from the radioactive content of the sample.

Akers, Douglas W.; Roybal, Lyle G.; Salomon, Hopi; Williams, Charles Leroy

2012-09-04

92

Hazardous and radioactive waste incineration studies  

SciTech Connect

Development and demonstration of a transuranic (TRU) waste volume-reduction process is described. A production-scale controlled air incinerator using commercially available equipment and technology has been modified for solid radioactive waste service. This unit successfully demonstrated the volume reduction of transuranic (TRU) waste with an average TRU content of about 20 nCi/g. The same incinerator and offgas treatment system is being modified further to evaluate the destruction of hazardous liquid wastes such as polychlorinated biphenyls (PCBs) and hazardous solid wastes such as pentachlorophenol (PCP)-treated wood.

Vavruska, J.S.; Stretz, L.A.; Borduin, L.C.

1981-01-01

93

Radioactive tank waste remediation focus area  

SciTech Connect

EM`s Office of Science and Technology has established the Tank Focus Area (TFA) to manage and carry out an integrated national program of technology development for tank waste remediation. The TFA is responsible for the development, testing, evaluation, and deployment of remediation technologies within a system architecture to characterize, retrieve, treat, concentrate, and dispose of radioactive waste stored in the underground stabilize and close the tanks. The goal is to provide safe and cost-effective solutions that are acceptable to both the public and regulators. Within the DOE complex, 335 underground storage tanks have been used to process and store radioactive and chemical mixed waste generated from weapon materials production and manufacturing. Collectively, thes tanks hold over 90 million gallons of high-level and low-level radioactive liquid waste in sludge, saltcake, and as supernate and vapor. Very little has been treated and/or disposed or in final form.

NONE

1996-08-01

94

Iron phosphate compositions for containment of hazardous metal waste  

DOEpatents

An improved iron phosphate waste form for the vitrification, containment and long-term disposition of hazardous metal waste such as radioactive nuclear waste is provided. The waste form comprises a rigid iron phosphate matrix resulting from the cooling of a melt formed by heating a batch mixture comprising the metal waste and a matrix-forming component. The waste form comprises from about 30 to about 70 weight percent P{sub 2}O{sub 5} and from about 25 to about 50 weight percent iron oxide and has metals present in the metal waste chemically dissolved therein. The concentration of iron oxide in the waste form along with a high proportion of the iron in the waste form being present as Fe{sup 3+} provide a waste form exhibiting improved chemical resistance to corrosive attack. A method for preparing the improved iron phosphate waste forms is also provided. 21 figs.

Day, D.E.

1998-05-12

95

Iron phosphate compositions for containment of hazardous metal waste  

DOEpatents

An improved iron phosphate waste form for the vitrification, containment and long-term disposition of hazardous metal waste such as radioactive nuclear waste is provided. The waste form comprises a rigid iron phosphate matrix resulting from the cooling of a melt formed by heating a batch mixture comprising the metal waste and a matrix-forming component. The waste form comprises from about 30 to about 70 weight percent P.sub.2 O.sub.5 and from about 25 to about 50 weight percent iron oxide and has metals present in the metal waste chemically dissolved therein. The concentration of iron oxide in the waste form along with a high proportion of the iron in the waste form being present as Fe.sup.3+ provide a waste form exhibiting improved chemical resistance to corrosive attack. A method for preparing the improved iron phosphate waste forms is also provided.

Day, Delbert E. (Rolla, MO)

1998-01-01

96

Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility  

SciTech Connect

The purpose of this plan is to describe the organization and methodology for the certification of radioactive mixed waste (RMW) handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). RMW is low-level radioactive waste (LLW) or transuranic (TRU) waste that is co-contaminated with dangerous waste as defined in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and the Washington State Dangerous Waste Regulations, 173-303-040 (18). This waste is to be transferred to the Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington. This plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF (Section 4); and a list of the current and planned implementing procedures used in waste certification.

Albert, R.

1992-06-30

97

40 CFR 227.30 - High-level radioactive waste.  

Code of Federal Regulations, 2013 CFR

...2013-07-01 2013-07-01 false High-level radioactive waste. 227.30 Section 227.30 Protection... Definitions § 227.30 High-level radioactive waste. High-level radioactive waste means the aqueous waste resulting...

2013-07-01

98

Storing solid radioactive wastes at the Savannah River Plant  

Microsoft Academic Search

The facilities and the operation of solid radioactive waste storage at the Savannah River Plant (SRP) are discussed in the report. The procedures used to segregate and the methods used to store radioactive waste materials are described, and the monitoring results obtained from studies of the movement of radionuclides from buried wastes at SRP are summarized. The solid radioactive waste

J. H. Horton; J. C. Corey

1976-01-01

99

The UK Committee on Radioactive Waste Management.  

PubMed

The UK Committee on Radioactive Waste Management is charged with recommending to Government, by July 2006, options for the long term management of the UK's radioactive waste legacy. These options should inspire public confidence. Now, more than halfway into the time allotted, we, as two former members of the Committee, express our concerns at the wayward approach that has been adopted. The Committee has placed emphasis on gaining public confidence but this has been done at the expense of recruiting the best scientific expertise in the management of radioactive waste, an act which we believe will actually undermine public confidence. Furthermore, given also the immense importance of this decision to public safety, national security and the national interest, we believe urgent steps should be taken to review the Committee's process, its management and its sponsorship. PMID:16286694

Baverstock, Keith; Ball, David J

2005-09-06

100

Packaging radioactive wastes for geologic disposal  

SciTech Connect

The M&O contractor for the DOE Office of Civilian Radioactive Waste Management is developing designs of waste packages that will contain the spent nuclear fuel assemblies from commercial and Navy reactor plants and various civilian and government research reactor plants, as well as high-level wastes vitrified in glass. The safe and cost effective disposal of the large and growing stockpile of nuclear waste is of national concern and has generated political and technical debate. This paper addresses the technical aspects of disposing of these wastes in large and robust waste packages. The paper discusses the evolution of waste package design and describes the current concepts. In addition, the engineering and regulatory issues that have governed the development are summarized and the expected performance in meeting the requirements are discussed.

Benton, H.A.

1996-08-01

101

Method for decontamination of radioactive metal surfaces  

DOEpatents

Disclosed is a method for removing radioactive contaminants from metal surfaces by applying steam containing an inorganic acid and cerium IV. Cerium IV is applied to contaminated metal surfaces by introducing cerium IV in solution into a steam spray directed at contaminated metal surfaces. Cerium IV solution is converted to an essentially atomized or vapor phase by the steam.

Bray, L.A.

1996-08-13

102

Corrosion Studies of Container Materials for Radioactive Waste Disposal in Granite Formation.  

National Technical Information Service (NTIS)

This report describes the research carried out for the assessment of corrosion behaviour of materials selected for the manufacture of containers for disposal of radioactive waste in granite formation. Metals and alloys included in laboratory test program ...

G. Plante M. Helie O. Sanatine A. Cheniere

1984-01-01

103

Radioactive waste management in the former USSR  

SciTech Connect

Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world's largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes.

Bradley, D.J.

1992-06-01

104

Processing of solid mixed waste containing radioactive and hazardous materials  

DOEpatents

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination of a plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter.

Gotovchikov, Vitaly T. (Moscow, RU); Ivanov, Alexander V. (Moscow, RU); Filippov, Eugene A. (Moscow, RU)

1998-05-12

105

Method for solidification of radioactive and other hazardous waste  

SciTech Connect

Solidification of liquid radioactive waste, and other hazardous wastes, is accomplished by the method of the invention by incorporating the waste into a porous glass crystalline molded block. The porous block is first loaded with the liquid waste and then dehydrated and exposed to thermal treatment at 50-1,000.degree. C. The porous glass crystalline molded block consists of glass crystalline hollow microspheres separated from fly ash (cenospheres), resulting from incineration of fossil plant coals. In a preferred embodiment, the porous glass crystalline blocks are formed from perforated cenospheres of grain size -400+50, wherein the selected cenospheres are consolidated into the porous molded block with a binder, such as liquid silicate glass. The porous blocks are then subjected to repeated cycles of saturating with liquid waste, and drying, and after the last cycle the blocks are subjected to calcination to transform the dried salts to more stable oxides. Radioactive liquid waste can be further stabilized in the porous blocks by coating the internal surface of the block with metal oxides prior to adding the liquid waste, and by coating the outside of the block with a low-melting glass or a ceramic after the waste is loaded into the block.

Anshits, Alexander G. (Krasnoyarsk, RU); Vereshchagina, Tatiana A. (Krasnoyarsk, RU); Voskresenskaya, Elena N. (Krasnoyarsk, RU); Kostin, Eduard M. (Zheleznogorsk, RU); Pavlov, Vyacheslav F. (Krasnoyarsk, RU); Revenko, Yurii A. (Zheleznogorsk, RU); Tretyakov, Alexander A. (Zheleznogorsk, RU); Sharonova, Olga M. (Krasnoyarsk, RU); Aloy, Albert S. (Saint-Petersburg, RU); Sapozhnikova, Natalia V. (Saint-Petersburg, RU); Knecht, Dieter A. (Idaho Falls, ID); Tranter, Troy J. (Idaho Falls, ID); Macheret, Yevgeny (Idaho Falls, ID)

2002-01-01

106

Data base for radioactive waste management: waste source options report  

SciTech Connect

This document is prepared in three volumes and provides part of the technical support to the draft environmental impact statement (NUREG-0782) on a proposed regulation, 10CFR Part 61, setting forth licensing requirements for land disposal of low level radioactive waste. Volume 2 provides a summary of low level waste volumes and characteristics as projected to the year 2000, in addition to characterizing treatment options for this waste.

Wild, R.E.; Oztunali, O.I.; Clancy, J.J.; Pitt, C.J.; Picazo, E.D.

1981-11-01

107

Synthesis and Properties of Metallic Technetium and Technetium - Zirconium Alloys as a Radioactive Storage Waste Form to Stabilize the Technetium Waste Stream of the UREX+1 Process  

Microsoft Academic Search

In the AFCI program the UREX+1 process is proposed as one of the most promising technique to separate TRU (transuranic elements) form LWR spent nuclear fuel in the years to come. The application of UREX+1 results in good separation of the 5f-transuranics from the 4f-lanthanides, reduced waste volumes by eliminating the uranium content, and reduced waste package costs. Technetium-99 will

Frederic Poineau; Thomas Hartmann; Kenneth Czerwinski

2006-01-01

108

Process Knowledge Characterization of Radioactive Waste at the Classified Waste Landfill Remediation Project Sandia National Laboratories, Albuquerque, New Mexico  

SciTech Connect

This paper discusses the development and application of process knowledge (PK) to the characterization of radioactive wastes generated during the excavation of buried materials at the Sandia National Laboratories/New Mexico (SNL/NM) Classified Waste Landfill (CWLF). The CWLF, located in SNL/NM Technical Area II, is a 1.5-acre site that received nuclear weapon components and related materials from about 1950 through 1987. These materials were used in the development and testing of nuclear weapon designs. The CWLF is being remediated by the SNL/NM Environmental Restoration (ER) Project pursuant to regulations of the New Mexico Environment Department. A goal of the CWLF project is to maximize the amount of excavated materials that can be demilitarized and recycled. However, some of these materials are radioactively contaminated and, if they cannot be decontaminated, are destined to require disposal as radioactive waste. Five major radioactive waste streams have been designated on the CWLF project, including: unclassified soft radioactive waste--consists of soft, compatible trash such as paper, plastic, and plywood; unclassified solid radioactive waste--includes scrap metal, other unclassified hardware items, and soil; unclassified mixed waste--contains the same materials as unclassified soft or solid radioactive waste, but also contains one or more Resource Conservation and Recovery Act (RCRA) constituents; classified radioactive waste--consists of classified artifacts, usually weapons components, that contain only radioactive contaminants; and classified mixed waste--comprises radioactive classified material that also contains RCRA constituents. These waste streams contain a variety of radionuclides that exist both as surface contamination and as sealed sources. To characterize these wastes, the CWLF project's waste management team is relying on data obtained from direct measurement of radionuclide activity content to the maximum extent possible and, in cases where direct measurement is not technically feasible, from accumulated PK of the excavated materials.

DOTSON,PATRICK WELLS; GALLOWAY,ROBERT B.; JOHNSON JR,CARL EDWARD

1999-11-03

109

Aspects of Underground Disposal of Radioactive Waste in Rock Salt.  

National Technical Information Service (NTIS)

The subject of the thesis concerns disposal of radioactive waste in underground rock-salt formations. Rock salt is one of the few potential host formations for accomodating radioactive waste; it has a relatively high thermal conductivity and is practicall...

W. M. G. T. van den Broek

1989-01-01

110

Development of long-term performance models for radioactive waste forms  

SciTech Connect

The long-term performance of solid radioactive waste is measured by the release rate of radionuclides into the environment, which depends on corrosion or weathering rates of the solid waste form. The reactions involved depend on the characteristics of the solid matrix containing the radioactive waste, the radionuclides of interest, and their interaction with surrounding geologic materials. This chapter describes thermo-hydro-mechanical and reactive transport models related to the long-term performance of solid radioactive waste forms, including metal, ceramic, glass, steam reformer and cement. Future trends involving Monte-Carlo simulations and coupled/multi-scale process modeling are also discussed.

Bacon, Diana H.; Pierce, Eric M.

2011-03-22

111

Annual radioactive waste tank inspection program - 1992  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1992 to evaluate these vessels and evaluations based on data accrued by inspections made since the tanks were constructed are the subject of this report.

McNatt, F.G.

1992-12-31

112

Annual radioactive waste tank inspection program - 1996  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1996 to evaluate these vessels, and evaluations based on data accrued by inspections performed since the tanks were constructed, are the subject of this report.

McNatt, F.G.

1997-04-01

113

Evaluation of Terrorist Interest in Radioactive Wastes  

Microsoft Academic Search

Since September 11, 2001, intelligence gathered from Al Qaeda training camps in Afghanistan, and the ensuing terrorist activities, indicates nuclear material security concerns are valid. This paper reviews available information on sealed radioactive sources thought to be of interest to terrorists, and then examines typical wastes generated during environmental management activities to compare their comparative 'attractiveness' for terrorist diversion. Sealed

J. N. McFee; J. M. Langsted; M. E. Young; J. E. Day

2006-01-01

114

Annual Radioactive Waste Tank Inspection Program - 1997  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1997 to evaluate these vessels, and evaluations based on data accrued by inspections performed since the tanks were constructed are the subject of this report.

McNatt, F.G. [Westinghouse Savannah River Company, AIKEN, SC (United States)

1998-05-01

115

Clay barriers in radioactive waste disposal  

Microsoft Academic Search

Deep geological is one of the preferred options for the disposal of high level radioactive waste. In most designs, the canisters placed in drifts or boreholes are surrounded by an engineered barrier usually made of compacted swelling clay. The barrier undergoes severe heating from the canisters and hydration from the host rock. In this situation a number of interacting thermal,

Antonio Gens; Sebasti Olivella

2001-01-01

116

Annual Radioactive Waste Tank Inspection Program - 1998  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site separations processes are contained in large underground carbon steel tanks. Inspections made during 1998 to evaluate these vessels and auxiliary appurtenances, along with evaluations based on data accrued by inspections performed since the tanks were constructed, are the subject of this report.

McNatt, F.G.

1999-10-27

117

Radioactive waste disposal in granite. [Stripa mine  

Microsoft Academic Search

The principal geotechnical problems in selecting a repository site for radioactive waste disposal in granite are to evaluate the suitability of the rock mass in terms of: (1) fracture characteristics, (2) thermomechanical effects, and (3) fracture hydrology. Underground experiments in a mine in Sweden have provided an opportunity to study these problems. The research has demonstrated the importance of hydrogeology

P. A. Witherspoon; D. J. Watkins

1982-01-01

118

RADIOACTIVE WASTE DISPOSAL IN THE RUSSIAN FEDERATION  

Microsoft Academic Search

There are currently few licensed repositories for disposal of radioactive waste within the Russian Federation. This impasse has evolved due to extreme concerns by local and state governments about the safety of such facilities and the lack of coordinated action by the many ministries and agencies that each have some responsibility for the design, siting, licensing and operation of these

Nikolai Laverov; Yuriy Shiyan; Paul Childress

2000-01-01

119

Radionuclides, Heavy Metals, and Polychlorinated Biphenyls in Soils Collected Around the Perimeter of Low-Level Radioactive Waste Disposal Area G during 2006  

SciTech Connect

Twenty-one soil surface samples were collected in March around the perimeter of Area G, the primary disposal facility for low-level radioactive solid waste at Los Alamos National Laboratory (LANL). Three more samples were collected in October around the northwest corner after elevated tritium levels were detected on an AIRNET station located north of pit 38 in May. Also, four soil samples were collected along a transect at various distances (48, 154, 244, and 282 m) from Area G, starting from the northeast corner and extending to the Pueblo de San Ildefonso fence line in a northeasterly direction (this is the main wind direction). Most samples were analyzed for radionuclides ({sup 3}H, {sup 238}Pu, {sup 239,240}Pu, {sup 241}Am, {sup 234}U, {sup 235}U, and {sup 238}U), inorganic elements (Al, Ba, Be, Ca, Cr, Co, Cu, Fe, Mg, Mn, Ni, K, Na, V, Hg, Zn, Sb, As, Cd, Pb, Se, Ag, and Tl) and polychlorinated biphenyl (PCB) concentrations. As in previous years, the highest levels of {sup 3}H in soils (690 pCi/mL) were detected along the south portion of Area G near the {sup 3}H shafts; whereas, the highest concentrations of {sup 241}Am (1.2 pCi/g dry) and the Pu isotopes (1.9 pCi/g dry for {sup 238}Pu and 5 pCi/g dry for {sup 239,240}Pu) were detected along the northeastern portions near the transuranic waste pads. Concentrations of {sup 3}H in three soil samples and {sup 241}Am and Pu isotopes in one soil sample collected around the northwest corner in October increased over concentrations found in soils collected at the same locations earlier in the year. Almost all of the heavy metals, with the exception of Zn and Sb in one sample each, in soils around the perimeter of Area G were below regional statistical reference levels (mean plus three standard deviations) (RSRLs). Similarly, only one soil sample collected on the west side contained PCB concentrations--67 {micro}g/kg dry of aroclor-1254 and 94 {micro}g/kg dry of aroclor-1260. Radionuclide and inorganic element concentrations in soils collected along a transect from Area G to the Pueblo de San Ildefonso fence line show that most contained concentrations of {sup 241}Am, {sup 238}Pu, and {sup 239,240}Pu above the RSRLs. Overall, all concentrations of radionuclides, heavy metals, and PCBs that were detected above background levels in soils collected around the perimeter of Area G and towards the Pueblo de San Ildefonso boundary were still very low and far below LANL screening levels and regulatory standards.

P. R. Fresquez

2007-02-28

120

40 CFR 147.3005 - Radioactive waste injection wells.  

Code of Federal Regulations, 2013 CFR

...2013-07-01 2013-07-01 false Radioactive waste injection wells. 147.3005...Other New Mexico Tribes § 147.3005 Radioactive waste injection wells. Notwithstanding...operators of wells used to dispose of radioactive waste (as defined in 10 CFR part...

2013-07-01

121

Beneficial role of conflict in radioactive waste management programs  

Microsoft Academic Search

Of the technical, political, and social problems associated with radioactive waste management, least is known about the latter two. Lay persons tend to generalize negative attitudes about other nuclear activity to radioactive waste management. Thus, conflict appears inevitable between the general public, citizen action groups, and decision-makers on radioactive waste management. The basis of conflict, we believe, can be found

B. A. Payne; R. G. Williams

1985-01-01

122

Handbook of high-level radioactive waste transportation  

SciTech Connect

The High-Level Radioactive Waste Transportation Handbook serves as a reference to which state officials and members of the general public may turn for information on radioactive waste transportation and on the federal government`s system for transporting this waste under the Civilian Radioactive Waste Management Program. The Handbook condenses and updates information contained in the Midwestern High-Level Radioactive Waste Transportation Primer. It is intended primarily to assist legislators who, in the future, may be called upon to enact legislation pertaining to the transportation of radioactive waste through their jurisdictions. The Handbook is divided into two sections. The first section places the federal government`s program for transporting radioactive waste in context. It provides background information on nuclear waste production in the United States and traces the emergence of federal policy for disposing of radioactive waste. The second section covers the history of radioactive waste transportation; summarizes major pieces of legislation pertaining to the transportation of radioactive waste; and provides an overview of the radioactive waste transportation program developed by the US Department of Energy (DOE). To supplement this information, a summary of pertinent federal and state legislation and a glossary of terms are included as appendices, as is a list of publications produced by the Midwestern Office of The Council of State Governments (CSG-MW) as part of the Midwestern High-Level Radioactive Waste Transportation Project.

Sattler, L.R.

1992-10-01

123

Radioactive Waste Burial Grounds. Environmental Information Document  

SciTech Connect

This document provides environmental information on postulated closure options for the Radioactive Waste Burial Grounds at the Savannah River Plant and was developed as background technical documentation for the Department of Energy`s proposed Environmental Impact Statement (EIS) on waste management activities for groundwater protection at the plant. The results of groundwater and atmospheric pathway analyses, accident analysis, and other environmental assessments discussed in this document are based upon a conservative analysis of all foreseeable scenarios as defined by the National Environmental Policy Act (CFR, 1986). The scenarios do not necessarily represent actual environmental conditions. This document is not meant to be used as a closure plan or other regulatory document to comply with required federal or state environmental regulations. The closure options considered for the Radioactive Waste Burial Grounds are waste removal and closure, no waste removal and closure, and no action. The predominant pathways for human exposure to chemical and/or radioactive constituents are through surface, subsurface, and atmospheric transport. Modeling calculations were made to determine the risks to human population via these general pathways for the three postulated closure options. An ecological assessment was conducted to predict the environmental impacts on aquatic and terrestrial biota. The relative costs for each of the closure options were estimated.

Jaegge, W.J.; Kolb, N.L.; Looney, B.B.; Marine, I.W.; Towler, O.A.; Cook, J.R.

1987-03-01

124

Chemistry and technology of radioactive waste management the IAEA perspective  

NASA Astrophysics Data System (ADS)

The paper refers the consideration of chemical composition of radioactive waste in selection of particular method and technology for waste treatment and conditioning, importance of physicochemical parameters of waste processing techniques for optimisation of waste processing to produce waste form of appropriate quality. Consideration of waste chemistry is illustrated by several IAEA activities on radioactive waste management and by outlining the scope of some selected technical reports on different waste management subjects. Different components of the IAEA activities on radioactive waste management and on technology transfer are presented and discussed.

Efremenkov, V. M.

2003-01-01

125

Soluble pig for radioactive waste transfer lines  

SciTech Connect

Flushing transfer pipe after radioactive waste transfers generates thousands of gallons of additional radioactive waste each year at the Hanford site. The use of pneumatic pigging with waste soluble pigs as a means to clear transfer piping may be an effective alternative to raw water flushes. A feasibility study was performed by a group of senior mechanical engineering students for their senior design project as part of their curriculum at Washington State University. The students divided the feasibility study into three sub-projects involving: (1) materials research, (2) delivery system design, and (3) mockup fabrication and testing. The students screened through twenty-three candidate materials and selected a thermoplastic polymer combined 50:50 wt% with sucrose to meet the established material performance criteria. The students also prepared a conceptual design of a remote pneumatic delivery system and constructed a mockup section of transfer pipe for testing the prototype pigs.

Ohl, P.C., Westinghouse Hanford

1996-12-02

126

Greater confinement disposal of radioactive wastes  

SciTech Connect

Low-level radioactive waste (LLW) includes a broad spectrum of different radionuclide concentrations, half-lives, and hazards. Standard shallow-land burial practice can provide adequate protection of public health and safety for most LLW. A small volume fraction (approx. 1%) containing most of the activity inventory (approx. 90%) requires specific measures known as greater-confinement disposal (GCD). Different site characteristics and different waste characteristics - such as high radionuclide concentrations, long radionuclide half-lives, high radionuclide mobility, and physical or chemical characteristics that present exceptional hazards - lead to different GCD facility design requirements. Facility design alternatives considered for GCD include the augered shaft, deep trench, engineered structure, hydrofracture, improved waste form, and high-integrity container. Selection of an appropriate design must also consider the interplay between basic risk limits for protection of public health and safety, performance characteristics and objectives, costs, waste-acceptance criteria, waste characteristics, and site characteristics.

Trevorrow, L.E.; Gilbert, T.L.; Luner, C.; Merry-Libby, P.A.; Meshkov, N.K.; Yu, C.

1985-01-01

127

Control of radioactive waste-glass melters  

SciTech Connect

Slurries of simulated high level radioactive waste and glass formers have been isothermally reacted and analyzed to identify the sequence of the major chemical reactions in waste vitrification, their effect on glass production rate, and the development of leach resistance. Melting rates of waste batches have been increased by the addition of reducing agents (formic acid, sucrose) and nitrates. The rate increases are attributable in part to exothermic reactions which occur at critical stages in the vitrification process. Nitrates must be balanced by adequate reducing agents to avoid the formation of persistent foam, which would destabilize the melting process. The effect of foaming on waste glass production rates is analyzed, and melt rate limitations defined for waste-glass melters, based upon measurable thermophysical properties. Minimum melter residence times required to homogenize glass and assure glass quality are much smaller than those used in current practice. Thus, melter size can be reduced without adversely affecting glass quality. Physical chemistry and localized heat transfer of the waste-glass melting process are examined, to refine the available models for predicting and assuring glass production rate. It is concluded that the size of replacement melters and future waste processing facilities can be significantly decreased if minimum heat transfer requirements for effective melting are met by mechanical agitation. A new class of waste glass melters has been designed, and proof of concept tests completed on simulated High Level Radioactive Waste slurry. Melt rates have exceeded 155 kg m{sup {minus}2} h{sup {minus}1} with slurry feeds (32 lb ft{sup {minus}2} h{sup {minus}1}), and 229 kg kg m{sup {minus}2} h{sup {minus}1} with dry feed (47 lb ft{sup {minus}2} h{sup {minus}1}). This is about 8 times the melt rate possible in conventional waste- glass melters of the same size. 39 refs., 5 figs., 9 tabs.

Bickford, D.F. (Westinghouse Savannah River Co., Aiken, SC (USA)); Hrma, P. (Case Western Reserve Univ., Cleveland, OH (USA)); Bowan, B.W. II (West Valley Nuclear Services Co., Inc., West Valley, NY (USA))

1990-01-01

128

Waste minimization for commercial radioactive materials users generating low-level radioactive waste. Revision 1  

SciTech Connect

The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature.

Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S. [EG and G Idaho, Inc., Idaho Falls, ID (United States); Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L. [Science Applications International Corp., Idaho Falls, ID (United States)

1991-07-01

129

Waste minimization for commercial radioactive materials users generating low-level radioactive waste  

SciTech Connect

The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature.

Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S. (EG and G Idaho, Inc., Idaho Falls, ID (United States)); Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L. (Science Applications International Corp., Idaho Falls, ID (United States))

1991-07-01

130

Combustible radioactive waste treatment by incineration and chemical digestion  

NASA Astrophysics Data System (ADS)

Present and planned combustible radioactive waste treatment systems in the U.S. are reviewed. Advantages and disadvantages of various systems are considered. Design waste streams are discussed in relation to waste composition, radioactive contaminants by amount and type, and special operating problems caused by the waste.

Stretz, L. A.; Allen, C. R.; Crippen, M. D.

1980-05-01

131

Combustible radioactive waste treatment by incineration and chemical digestion  

SciTech Connect

A review is given of present and planned combustible radioactive waste treatment systems in the US. Advantages and disadvantages of various systems are considered. Design waste streams are discussed in relation to waste composition, radioactive contaminants by amount and type, and special operating problems caused by the waste.

Stretz, L.A.; Crippen, M.D.; Allen, C.R.

1980-05-28

132

Selection of barrier metals for a waste package in tuff  

SciTech Connect

The Nevada Nuclear Waste Storage Investigations (NNWSI) project under the Civilian Radioactive Waste Management Program is planning a repository at Yucca Mountain at the Nevada Test Site for isolation of high-level nuclear waste. Lawrence Livermore National Laboratory is developing designs for an engineered barrier system containing several barriers such as the waste form, a canister and/or an overpack, packing, and near field host rock. In this paper we address the selection of metal containment barriers. 13 references, 4 tables.

Russell, E.W.; McCright, R.D.; O`Neal, W.C.

1983-10-01

133

Application of ceramic membranes for hazardous wastes processing: pilot plant experiments with radioactive solutions  

Microsoft Academic Search

The membrane method combined with complexation was applied for hazardous wastes containing radioactive substance processing. Such complexing agents like soluble chetating polymers and cyanoferrates of transient metals, tested and selected in the laboratory, were used to bind radioactive ions and to enlarge the separated molecule size. The preliminary pilot plant experiments are presented with installation equipped with a ceramic 23-channel

Gra?yna Zakrzewska-Trznadel; Marian Harasimowicz

2004-01-01

134

Hydrogen production during processing of radioactive sludge containing noble metals  

SciTech Connect

Hydrogen was produced when radioactive sludge from Savannah River Site radioactive waste containing noble metals was reacted with formic acid. This will occur in a process tank in the Defense Waste Facility at SRS when waste is vitrified. Radioactive sludges from four tanks were tested in a lab-scale apparatus. Maximum hydrogen generation rates varied from 5 {times}10{sup {minus}7} g H{sub 2}/hr/g of sludge from the least reactive sludge (from Waste Tank 51) to 2 {times}10{sup {minus}4} g H{sub 2}/hr/g of sludge from the most reactive sludge (from Waste Tank 11). The time required for the hydrogen generation to reach a maximum varied from 4.1 to 25 hours. In addition to hydrogen, carbon dioxide and nitrous oxide were produced and the pH of the reaction slurry increased. In all cases, the carbon dioxide and nitrous oxide were generated before the hydrogen. The results are in agreement with large-scale studies using simulated sludges.

Ha, B.C.; Ferrara, D.M.; Bibler, N.E.

1992-09-01

135

Geochemical Aspects of Radioactive Waste Disposal  

NASA Astrophysics Data System (ADS)

The author's stated purpose in writing this book is to summarize the large number of government-sponsored research reports on the geochemical aspects of high-level nuclear waste isolation. Although this book has a 1984 publication date, the majority of the cited documents were published before 1982. Unfortunately, passage of the Nuclear Waste Policy Act (NWPA) of 1982 and its signing into law by President Reagan (January 1983) [U.S. Congress, 1983] has significantly altered the U.S. Department of Energy (DOE) Civilian Radioactive Waste Management (CRWM) Program. Therefore this book does not accurately reflect the present U.S. program in geologic disposal of high-level nuclear waste. For example, chapter 2, Radioactive Waste Management, is almost 3 years out of date in a field that is changing rapidly (see U.S. DOE [1984a] for the current status of the CRWM Program). Additionally, the source material, which forms the input for this book, is chiefly grey literature, i.e., the referenced documents may or may not have undergone peer review and therefore do not represent the technical judgment of the scientific community. Also, this book only presents a selective sampling of information because the literature cited does not include a representative selection of the widespread available literature on this topic.

Moody, Judith B.

1984-04-01

136

System for handling and storing radioactive waste  

DOEpatents

A system and method are claimed for handling and storing spent reactor fuel and other solid radioactive waste, including canisters to contain the elements of solid waste, storage racks to hold a plurality of such canisters, storage bays to store these racks in isolation by means of shielded doors in the bays. This system also includes means for remotely positioning the racks in the bays and an access tunnel within which the remotely operated means is located to position a rack in a selected bay. The modular type of these bays will facilitate the construction of additional bays and access tunnel extension.

Anderson, J.K.; Lindemann, P.E.

1982-07-19

137

THE CURRENT RADIOACTIVE WASTE MANAGEMENT IN ROMANIA  

Microsoft Academic Search

In 1957, Romania commissioned a Russian-designed VVR-S research reactor used for scientific activities and radioisotope production. This reactor is now planned for decommissioning. An American TRIGA -type research reactor has been in use since 1978. The first Canadian CANDU-6 type power reactor was commissioned in December 1996 and is in commercial operation. The radioactive waste management in Romania followed decentralized

V. Andrei; F. Glodeanu; I. Rotaru; T. Chirica

2000-01-01

138

Progress of radioactive waste management in Lithuania  

Microsoft Academic Search

The only one nuclear power plant in the Republic of Lithuania Ignalina Nuclear Power Plant contains two RBMK-1500 water-cooled graphite-moderated channel-type power reactors. The first and the second reactors were shut down by the end of 2004 and by the end of 2009, respectively. During operation, the power plant has accumulated large quantities of radioactive waste, including spent nuclear

P. Poskas; J. E. Adomaitis; V. Ragaisis; V. Simonis; A. Smaizys; R. Kilda; D. Grigaliuniene

139

Performance assessment of radioactive waste repositories  

Microsoft Academic Search

The current plans for permanent disposal of radioactive waste call for its emplacement in deep underground repositories mined from geologically stable rock formations. The U.S. Nuclear Regulatory Commission and U.S. Environmental Protection Agency have established regulations setting repository performance standards for periods of up to 10,000 years after disposal. Compliance with these regulations will be based on a performance assessment

J. E. Campbell; R. M. Cranwell

1988-01-01

140

Design and Construction of Deinococcus Radiodurans for Biodegradation of Organic Toxins at Radioactive DOE Waste Sites  

SciTech Connect

Seventy million cubic meters of ground and three trillion liters of groundwater have been contaminated by leaking radioactive waste generated in the United States during the Cold War. A cleanup technology is being developed based on the extremely radiation resistant bacterium Deinococcus radiodurans that is being engineered to express bioremediating functions. Research aimed at developing D. radiodurans for organic toxin degradation in highly radioactive waste sites containing radionuclides, heavy metals, and toxic organic compounds was started by this group.Work funded by the existing grant has already contributed to eleven papers on the fundamental biology of D. radiodurans and its design for bioremediation of highly radioactive waste environments

Michael J. Daly; Lawrence P. Wackett; James K. Fredrickson

2001-04-22

141

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM - 2011  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2011 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2011 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per SRR-LWE-2011-00026, HLW Tank Farm Inspection Plan for 2011, were completed. Ultrasonic measurements (UT) performed in 2011 met the requirements of C-ESR-G-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 3, and WSRC-TR-2002-00061, Rev.6. UT inspections were performed on Tanks 25, 26 and 34 and the findings are documented in SRNL-STI-2011-00495, Tank Inspection NDE Results for Fiscal Year 2011, Waste Tanks 25, 26, 34 and 41. A total of 5813 photographs were made and 835 visual and video inspections were performed during 2011. A potential leaksite was discovered at Tank 4 during routine annual inspections performed in 2011. The new crack, which is above the allowable fill level, resulted in no release to the environment or tank annulus. The location of the crack is documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.6.

West, B.; Waltz, R.

2012-06-21

142

Chemical species of plutonium in Hanford radioactive tank waste  

SciTech Connect

Large quantities of radioactive wastes have been generated at the Hanford Site over its operating life. The wastes with the highest activities are stored underground in 177 large (mostly one million gallon volume) concrete tanks with steel liners. The wastes contain processing chemicals, cladding chemicals, fission products, and actinides that were neutralized to a basic pH before addition to the tanks to prevent corrosion of the steel liners. Because the mission of the Hanford Site was to provide plutonium for defense purposes, the amount of plutonium lost to the wastes was relatively small. The best estimate of the amount of plutonium lost to all the waste tanks is about 500 kg. Given uncertainties in the measurements, some estimates are as high as 1,000 kg (Roetman et al. 1994). The wastes generally consist of (1) a sludge layer generated by precipitation of dissolved metals from aqueous wastes solutions during neutralization with sodium hydroxide, (2) a salt cake layer formed by crystallization of salts after evaporation of the supernate solution, and (3) an aqueous supernate solution that exists as a separate layer or as liquid contained in cavities between sludge or salt cake particles. The identity of chemical species of plutonium in these wastes will allow a better understanding of the behavior of the plutonium during storage in tanks, retrieval of the wastes, and processing of the wastes. Plutonium chemistry in the wastes is important to criticality and environmental concerns, and in processing the wastes for final disposal. Plutonium has been found to exist mainly in the sludge layers of the tanks along with other precipitated metal hydrous oxides. This is expected due to its low solubility in basic aqueous solutions. Tank supernate solutions do not contain high concentrations of plutonium even though some tanks contain high concentrations of complexing agents. The solutions also contain significant concentrations of hydroxide which competes with other potential complexants. The sodium nitrate and sodium phosphate salts that form most of the salt cake layers have little interaction with plutonium in the wastes and contain relatively small plutonium concentrations. For these reasons the authors consider plutonium species in the sludges and supernate solutions only. The low concentrations of plutonium in waste tank supernate solutions and in the solid sludges prevent identification of chemical species of plutonium by ordinary analytical techniques. Spectrophotometric measurements are not sensitive enough to identify plutons oxidation states or complexes in these waste solutions. Identification of solid phases containing plutonium in sludge solids by x-ray diffraction or by microscopic techniques would be extremely difficult. Because of these technical problems, plutonium speciation was extrapolated from known behavior observed in laboratory studies of synthetic waste or of more chemically simple systems.

Barney, G.S.

1997-10-22

143

Stirring system for radioactive waste water storage tank  

Microsoft Academic Search

A stirring system for 100-m[sup 3] radioactive liquid waste tanks was constructed to unify radioactive concentrations in the tank. The stirring system is effective in certifying that the radioactive concentrations in the tanks are less than the legal limits before they are drained away as waste liquid. This system is composed of discharge units, pipe lines, and a controller. The

Yoshimune Ogata; Kunihide Nishizawa

1999-01-01

144

Risk-informed radioactive waste classification and reclassification.  

PubMed

Radioactive waste classification systems have been developed to allow wastes having similar hazards to be grouped for purposes of storage, treatment, packaging, transportation, and/or disposal. As recommended in the National Council on Radiation Protection and Measurements' Report No. 139, Risk-Based Classification of Radioactive and Hazardous Chemical Wastes, a preferred classification system would be based primarily on the health risks to the public that arise from waste disposal and secondarily on other attributes such as the near-term practicalities of managing a waste, i.e., the waste classification system would be risk informed. The current U.S. radioactive waste classification system is not risk informed because key definitions--especially that of high-level waste--are based on the source of the waste instead of its inherent characteristics related to risk. A second important reason for concluding the existing U.S. radioactive waste classification system is not risk informed is there are no general principles or provisions for exempting materials from being classified as radioactive waste which would then allow management without regard to its radioactivity. This paper elaborates the current system for classifying and reclassifying radioactive wastes in the United States, analyzes the extent to which the system is risk informed and the ramifications of its not being so, and provides observations on potential future direction of efforts to address shortcomings in the U.S. radioactive waste classification system as of 2004. PMID:17033455

Croff, Allen G

2006-11-01

145

Summary of radioactive solid waste received in the 200 Areas  

SciTech Connect

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office. These facilities include radioactive sold waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1991. This report does not include solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, (WHC 1988), liquid waste data are not included in this document.

Anderson, J.D.; McCann, D.C.; Poremba, B.E.

1992-06-01

146

Radioactive scrap metal decontamination technology assessment report  

SciTech Connect

Within the DOE complex there exists a tremendous quantity of radioactive scrap metal. As an example, it is estimated that within the gaseous diffusion plants there exists in excess of 700,000 tons of contaminated stainless steel. At present, valuable material is being disposed of when it could be converted into a high quality product. Liquid metal processing represents a true recycling opportunity for this material. By applying the primary production processes towards the material`s decontamination and re-use, the value of the strategic resource is maintained while drastically reducing the volume of material in need of burial. Potential processes for the liquid metal decontamination of radioactively contaminated metal are discussed and contrasted. Opportunities and technology development issues are identified and discussed. The processes compared are: surface decontamination; size reduction, packaging and burial; melting technologies; electric arc melting; plasma arc centrifugal treatment; air induction melting; vacuum induction melting; and vacuum induction melting and electroslag remelting.

Buckentin, J.M.; Damkroger, B.K.; Schlienger, M.E. [Sandia National Labs., Albuquerque, NM (United States). Liquid Metal Processing Lab.

1996-04-01

147

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM 2010  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. Inspections made during 2010 to evaluate these vessels and other waste handling facilities along with evaluations based on data from previous inspections are the subject of this report. The 2010 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. All inspections scheduled per SRR-LWE-2009-00138, HLW Tank Farm Inspection Plan for 2010, were completed. Ultrasonic measurements (UT) performed in 2010 met the requirements of C-ESG-00006, In-Service Inspection Program for High Level Waste Tanks, Rev. 3, and WSRC-TR-2002-00061, Rev.6. UT inspections were performed on Tanks 30, 31 and 32 and the findings are documented in SRNL-STI-2010-00533, Tank Inspection NDE Results for Fiscal Year 2010, Waste Tanks 30, 31 and 32. A total of 5824 photographs were made and 1087 visual and video inspections were performed during 2010. Ten new leaksites at Tank 5 were identified in 2010. The locations of these leaksites are documented in C-ESR-G-00003, SRS High Level Waste Tank Leaksite Information, Rev.5. Ten leaksites at Tank 5 were documented during tank wall/annulus cleaning activities. None of these new leaksites resulted in a release to the environment. The leaksites were documented during wall cleaning activities and the waste nodules associated with the leaksites were washed away. Previously documented leaksites were reactivated at Tank 12 during waste removal activities.

West, B.; Waltz, R.

2011-06-23

148

Radioactive Waste Disposal Implications of Extending Part IIA to cover Radioactively Contaminated Land  

Microsoft Academic Search

A short study has been carried out of the potential radioactive waste disposal issues associated with the proposed extension of Part IIA to address radioactively contaminated land, where there is no other suitable existing legislation. It was found that there is likely to be an availability problem with respect to disposal at landfills of the radioactive wastes arising from remediation.

DJ Nancarrow

149

Radioactive waste vitrification offgas analysis proposal  

SciTech Connect

Further validation of the Hanford Waste Vitrification Plant (HWVP) feed simulants will be performed by analyzing offgases during crucible melting of actual waste glasses and simulants. The existing method of vitrifying radioactive laboratory-scale samples will be modified to allow offgas analysis during preparation of glass for product testing. The analysis equipment will include two gas chromatographs (GC) with thermal conductivity detectors (TCD) and one NO/NO{sub x} analyzer. This equipment is part of the radioactive formating offgas system. The system will provide real-time analysis of H{sub 2}, O{sub 2}, N{sub 2}, NO, N{sub 2}O, NO{sub 2}, CO, CO{sub 2}, H{sub 2}O, and SO{sub 2}. As with the prior melting method, the product glass will be compatible with durability testing, i.e., Product Consistency Test (PCT) and Material Characterization Center (MCC-1), and crystallinity analysis. Procedures have been included to ensure glass homogeneity and quenching. The radioactive glass will be adaptable to Fe{sup +2}/{Sigma}Fe measurement procedures because the atmosphere above the melt can be controlled. The 325 A-hot cell facility is being established as the permanent location for radioactive offgas analysis during formating, and can be easily adapted to crucible melt tests. The total costs necessary to set up and perform offgas measurements on the first radioactive core sample is estimated at $115K. Costs for repeating the test on each additional core sample are estimated to be $60K. The schedule allows for performing the test on the next available core sample.

Nelson, C.W.; Morrey, E.V.

1993-11-01

150

Treatment of radioactive mixed wastes in commercial low-level wastes  

SciTech Connect

Management options for three generic categories of radioactive mixed waste in commercial low-level wastes have been identified and evaluated. These wastes were characterized as part of a BNL study in which a large number of generators were surveyed for information on potentially hazardous low-level wastes. The general management targets adopted for mixed wastes are immobilization, destruction, and reclamation. It is possible that these targets may not be practical for some wastes, and for these, goals of stabilization or reduction of hazard are addressed. Solidification, absorption, incineration, acid digestion, segregation, and substitution have been considered for organic liquid wastes. Containment, segregation, and decontamination and re-use have been considered for lead metal wastes which have themselves been contaminated and are not used for purposes of waste disposal shielding, packaging, or containment. For chromium-containing wastes, solidification, incineration, containment, substitution, chemical reduction, and biological removal have been considered. For each of these wastes, the management option evaluation has necessarily included assessment/estimation of the effect of the treatment on both the radiological and potential chemical hazards present. 10 refs.

Kempf, C.R.; MacKenzie, D.R.

1985-01-01

151

High level radioactive waste: Doing something about it  

Microsoft Academic Search

In addition to a growing inventory of spent power reactor fuel, there are approximately 100 million gallons of high-level radioactive waste (HLW) containing more than one billion curies of radioactivity stored in the United States today. This waste has been generated mainly from the production of plutonium and tritium and is primarily located on three federal sites. The waste is

G. G. Wicks; D. F. Bickford

1989-01-01

152

Risk methodology for geologic disposal of radioactive waste  

Microsoft Academic Search

Steps to be taken in the development of a methodology for the assessment of the long-term risks from radioactive waste disposal in deep, geologic media are outlined. The first phase involves the development of analytical models to represent the processes by which radioactive waste might leave the waste repository, enter the surface environment and eventually reach humans, and the definition

J. E. Campbell; R. T. Dillon; M. S. Tierney; H. T. Davis; P. E. McGrath; F. J. Pearson Jr.; H. R. Shaw; J. C. Helton; F. A. Donath

1978-01-01

153

Transporting Radioactive Waste: An Engineering Activity. Grades 5-12.  

ERIC Educational Resources Information Center

|This brochure contains an engineering activity for upper elementary, middle school, and high school students that examines the transportation of radioactive waste. The activity is designed to inform students about the existence of radioactive waste and its transportation to disposal sites. Students experiment with methods to contain the waste and

HAZWRAP, The Hazardous Waste Remedial Actions Program.

154

Environmental impact of radioactive waste management in the nuclear industry  

Microsoft Academic Search

Radioactive wastes from the nuclear industry are classified into low, intermediate and high activity levels, and problems of their storage and release examined in detail. Current means of storage are considered with reference to processing of low and intermediate level liquid waste, processing of high level waste, processing of airborne waste, and ground disposal and processing of solid waste. Release

Colin R. Phillips; H. Lin Pai

1977-01-01

155

Radioactive Waste Management Criteria in Fusion Reactor Materials Selection.  

National Technical Information Service (NTIS)

Fusion reactors will have to meet both quantitative and qualitative criteria for the disposal and/or reuse of radioactive materials. The most important quantitative criteria presently govern the near-surface disposal of radioactive wastes in the United St...

J. S. Herring S. Fetter

1987-01-01

156

Overview of techniques for volume reduction and immobilization of radioactive waste, as investigated at KEMA  

NASA Astrophysics Data System (ADS)

Measures to decrease the amount of radioactive waste generated by power plants, to decontaminate active material, and to reduce the final volume of the waste, e.g., by incineration or acid digestion are reviewed. Organic radioactive wastes from nuclear power plants are treated adequately: only inorganic end-products remain, and they have a relatively small volume and are immobilized. Chemical, biological, and alteration processes therefore do not significantly increase the risk of storage, even if water intrudes the storage facility. The considerable volumes of activated and/or contaminated metal that remain after repair or decommissioning of the plants could be treated. Decontamination and melting may significantly reduce the volume of the final waste. It seems probable that estimates of waste volumes are too pessimistic, and relatively small storage facilities will be sufficient. Waste in those facilities presents unacceptable risk for the biosphere during the period it is considered as radioactive.

Kuypers, J.; Matteman, J. L.; Vanloon, A. J.

157

ANNUAL RADIOACTIVE WASTE TANK INSPECTION PROGRAM- 2007  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations and vitrification processes are contained in large underground carbon steel tanks. The 2007 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks were maintained. A very small amount of material had seeped from Tank 12 from a previously identified leaksite. The material observed had dried on the tank wall and did not reach the annulus floor. A total of 5945 photographs were made and 1221 visual and video inspections were performed during 2007. Additionally, ultrasonic testing was performed on four Waste Tanks (15, 36, 37 and 38) in accordance with approved inspection plans that met the requirements of WSRC-TR-2002- 00061, Revision 2 'In-Service Inspection Program for High Level Waste Tanks'. The Ultrasonic Testing (UT) In-Service Inspections (ISI) are documented in a separate report that is prepared by the ISI programmatic Level III UT Analyst. Tanks 15, 36, 37 and 38 are documented in 'Tank Inspection NDE Results for Fiscal Year 2007'; WSRC-TR-2007-00064.

West, B; Ruel Waltz, R

2008-06-05

158

Electronic Denitration Savannah River Site Radioactive Waste  

SciTech Connect

Electrochemical destruction of nitrate in radioactive Savannah River Site Waste has been demonstrated in a bench-scale flow cell reactor. Greater than 99% of the nitrate can be destroyed in either an undivided or a divided cell reactor. The rate of destruction and the overall power consumption is dependent on the cell configuration and electrode materials. The fastest rate was observed using an undivided cell equipped with a nickel cathode and nickel anode. The use of platinized titanium anode increased the energy requirement and costs compared to a nickel anode in both the undivided and divided cell configurations.

Hobbs, D.T.

1995-04-11

159

Radioactive Waste Control and Controversy: The History of Radioactive Waste Regulation in the UK  

Microsoft Academic Search

A hundred years on from the discovery of radioactivity, we have the first book describing the history of the regulation in the UK of the waste arising from its many uses. The first book? Believe it or not, yes. There have been others which provide commentaries on the development (or hapless evolution?) of policy per se and it would be

J H Jackson

1999-01-01

160

Radioactive Waste Management Complex performance assessment: Draft  

SciTech Connect

A radiological performance assessment of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory was conducted to demonstrate compliance with appropriate radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the general public. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the general public via air, ground water, and food chain pathways. Projections of doses were made for both offsite receptors and individuals intruding onto the site after closure. In addition, uncertainty analyses were performed. Results of calculations made using nominal data indicate that the radiological doses will be below appropriate radiological criteria throughout operations and after closure of the facility. Recommendations were made for future performance assessment calculations.

Case, M.J.; Maheras, S.J.; McKenzie-Carter, M.A.; Sussman, M.E.; Voilleque, P.

1990-06-01

161

Dutch geologic radioactive waste disposal project  

NASA Astrophysics Data System (ADS)

Geologic disposal of radioactive waste is reviewed. The radionuclide release consequences of an accidental flooding of the underground excavations was studied. The results of the quantitative examples made for different effective cross sections of the permeable layer connecting the mine excavations with the boundary of the salt dome are that under all circumstances the concentration of the waste nuclides in drinking water will remain well within the ICRP maximum permissible concentrations. Further analysis work was done on what minima can be achieved for both the maximum local rock salt temperatures at the disposal borehole walls and the maximum global rock salt temperatures halfway between a square of disposal boreholes. Different multilayer disposal configurations were analyzed and compared.

Hamstra, J.; Verkerk, B.

162

Is radioactive mixed waste packaging and transportation really a problem  

SciTech Connect

Recently, there has been significant concern expressed in the nuclear community over the packaging and transportation of radioactive mixed waste under US Department of Transportation regulation. This concern has grown more intense over the last 5 to 10 years. Generators and regulators have realized that much of the waste shipped as ``low-level radioactive waste`` was in fact ``radioactive mixed waste`` and that these wastes pose unique transportation and disposal problems. Radioactive mixed wastes must, therefore, be correctly identified and classed for shipment. If must also be packaged, marked, labeled, and otherwise prepared to ensure safe transportation and meet applicable storage and disposal requirements, when established. This paper discusses regulations applicable to the packaging and transportation of radioactive mixed waste and identifies effective methods that waste shippers can adopt to meet the current transportation requirements. This paper will include a characterization and description of the waste, authorized packaging, and hazard communication requirements during transportation. Case studies will be sued to assist generators in understanding mixed waste shipment requirements and clarify the requirements necessary to establish a waste shipment program. Although management and disposal of radioactive mixed waste is clearly a critical issue, packaging and transportation of these waste materials is well defined in existing US Department of Transportation hazardous material regulations.

McCall, D.L.; Calihan, T.W. III

1992-01-01

163

Techniques for the Evaluation of Radioactive Waste Forms.  

National Technical Information Service (NTIS)

Before disposal of the radioactive waste packages, waste forms must meet some requirements to facilitate handling and to provide protection and safety of personnel during transportation, storage and disposal. And they must have the structural stability un...

H. H. Park J. H. Kim H. Y. Kim Y. C. Seo K. J. Jung

1987-01-01

164

HANDBOOK: VITRIFICATION TECHNOLOGIES FOR TREATMENT OF HAZARDOUS AND RADIOACTIVE WASTE  

EPA Science Inventory

The applications and limitations of vitrification technologies for treating hazardous and radioactive waste are presented. everal subgroups of vitrifications technologies exist. iscussions of glass structure, applicable waste types, off gas treatment, testing and evaluation proce...

165

Regulatory criteria for the disposal of radioactive wastes.  

National Technical Information Service (NTIS)

Radiological protection criteria have been proposed by the Atomic Energy Control Board for judging the potential long-term impacts of radioactive waste disposal options in which the wastes are contained and isolated from the human environment. This paper ...

K. P. Wagstaff

1986-01-01

166

'WISP' A Simple Radioactive Waste Management Computer Program.  

National Technical Information Service (NTIS)

The report describes the radioactive waste management program WISP. WISP was developed for rapid comparative assessment of different nuclear scenarios and fuel reprocessing strategies. It provides tables and graphs of low, intermediate and high level wast...

G. Beavan

1987-01-01

167

Radioactive Waste Packaging of Conditioned Waste at Kozloduy NPP Site  

SciTech Connect

An important part of Safety Management of conditioned low and intermediate level Radioactive Waste (RAW) is their packaging and containers for transport, storage and final disposal. A reinforced concrete container (RCC) has been developed to take cemented super compacted dry waste and cement solidified liquid waste at Kozloduy Nuclear Power Plant (KNPP). The container is to be used as a packaging of transportation, storage and final disposal of RAW conditioned by cementation KNPP specialists constructed and performed tests on the container. These tests were possible thanks to a review of European Community States experience, USA experience and IAEA documents. The container was tested by a team of specialists from KNPP, project specialists, fabricator of the containers and from Bulgarian Regulatory Body under IAEA Safety Standards, Safety Series, TECDOC, TRS and Bulgarian Standards. An expert from IAEA was a member of the testing group for RCC examinations. (authors)

Genchev, G.; Dimov, D. [RW Treatment Plant, Kozloduy NPP 3321 (Bulgaria); Russev, K. ['VIT' Ferro-Concrete Elements Production PLC, Bulgarian Aviation Street No 1, 5800 Town of Pleven (Bulgaria)

2006-07-01

168

Plasma separation process: Disposal of PSP radioactive wastes  

SciTech Connect

Radioactive wastes, in the form of natural uranium contaminated scrap hardware and residual materials from decontamination operations, were generated in the PSP facilities in buildings R1 and 106. Based on evaluation of the characteristics of these wastes and the applicable regulations, the various options for the processing and disposal of PSP radioactive wastes were investigated and recommended procedures were developed. The essential features of waste processing included: (1) the solidification of all liquid wastes prior to shipment; (2) cutting of scrap hardware to fit 55-gallon drums and use of inerting agents (diatomaceous earth) to eliminate pyrophoric hazards; and (3) compaction of soft wastes. All PSP radioactive wastes were shipped to the Hanford Site for disposal. As part of the waste disposal process, a detailed plan was formulated for handling and tracking of PSP radioactive wastes, from the point of generation through shipping. In addition, a waste minimization program was implemented to reduce the waste volume or quantity. Included in this document are discussions of the applicable regulations, the types of PSP wastes, the selection of the preferred waste disposal approach and disposal site, the analysis and classification of PSP wastes, the processing and ultimate disposition of PSP wastes, the handling and tracking of PSP wastes, and the implementation of the PSP waste minimization program. 9 refs., 1 fig., 8 tabs.

Not Available

1989-07-01

169

Control of high level radioactive waste-glass melters  

SciTech Connect

A necessary step in Defense Waste Processing Facility (DWPF) melter feed preparation for the immobilization of High Level Radioactive Waste (HLW) is reduction of Hg(II) to Hg(0), permitting steam stripping of the Hg. Denitrition and associated NOx evolution is a secondary effect of the use of formic acid as the mercury-reducing agent. Under certain conditions the presence of transition or noble metals can result in significant formic acid decomposition, with associated CO{sub 2} and H{sub 2} evolution. These processes can result in varying redox properties of melter feed, and varying sequential gaseous evolution of oxidants and hydrogen. Electrochemical methods for monitoring the competing processes are discussed. Laboratory scale techniques have been developed for simulating the large-scale reactions, investigating the relative effectiveness of the catalysts, and the effectiveness of catalytic poisons. The reversible nitrite poisoning of formic acid catalysts is discussed.

Bickford, D.F.; Coleman, C.J.; Hsu, C.L.W.; Eibling, R.E.

1990-01-01

170

The political science of radioactive waste disposal  

SciTech Connect

This paper was first presented at the annual meeting of the HPS in New Orleans in 1984. Twelve years later, the basic lessons learned are still found to be valid. In 1984, the following things were found to be true: A government agency is preferred by the public over a private company to manage radioactive waste. Semantics are important--How you say it is important, but how it is heard is more important. Public information and public relations are very important, but they are the last thing of concern to a scientist. Political constituency is important. Don`t overlook the need for someone to be on your side. Don`t forget that the media is part of the political process-they can make you or break you. Peer technical review is important, but so is citizen review. Sociology is an important issue that scientists and technical people often overlook. In summary, despite the political nature of radioactive waste disposal, it is as true today as it was in 1984 that technical facts must be used to reach sound technical conclusions. Only then, separately and openly, should political factors be considered. So, what can be said today that wasn`t said in 1984? Nothing. {open_quotes}It`s deja vu all over again.{close_quotes}

Jacobi, L.R. Jr. [Texas Los Level Radioactive Waste Disposal Authority, Austin, TX (United States)

1996-06-01

171

HIGH TEMPERATURE TREATMENT OF INTERMEDIATE-LEVEL RADIOACTIVE WASTES - SIA RADON EXPERIENCE  

SciTech Connect

This review describes high temperature methods of low- and intermediate-level radioactive waste (LILW) treatment currently used at SIA Radon. Solid and liquid organic and mixed organic and inorganic wastes are subjected to plasma heating in a shaft furnace with formation of stable leach resistant slag suitable for disposal in near-surface repositories. Liquid inorganic radioactive waste is vitrified in a cold crucible based plant with borosilicate glass productivity up to 75 kg/h. Radioactive silts from settlers are heat-treated at 500-700 0C in electric furnace forming cake following by cake crushing, charging into 200 L barrels and soaking with cement grout. Various thermochemical technologies for decontamination of metallic, asphalt, and concrete surfaces, treatment of organic wastes (spent ion-exchange resins, polymers, medical and biological wastes), batch vitrification of incinerator ashes, calcines, spent inorganic sorbents, contaminated soil, treatment of carbon containing 14C nuclide, reactor graphite, lubricants have been developed and implemented.

Sobolev, I.A.; Dmitriev, S.A.; Lifanov, F.A.; Kobelev, A.P.; Popkov, V.N.; Polkanov, M.A.; Savkin, A.E.; Varlakov, A.P.; Karlin, S.V.; Stefanovsky, S.V.; Karlina, O.K.; Semenov, K.N.

2003-02-27

172

A brief analysis and description of transuranic wastes in the Subsurface Disposal Area of the radioactive waste management complex at INEL  

SciTech Connect

This document presents a brief summary of the wastes and waste types disposed of in the transuranic contaminated portions of the Subsurface Disposal Area of the radioactive waste management complex at Idaho National Engineering Laboratory from 1954 through 1970. Wastes included in this summary are organics, inorganics, metals, radionuclides, and atypical wastes. In addition to summarizing amounts of wastes disposed and describing the wastes, the document also provides information on disposal pit and trench dimensions and contaminated soil volumes. The report also points out discrepancies that exist in available documentation regarding waste and soil volumes and make recommendations for future efforts at waste characterization. 19 refs., 3 figs., 17 tabs.

Arrenholz, D.A.; Knight, J.L.

1991-08-01

173

Controlled Containment, Radioactive Waste Management in the Netherlands  

SciTech Connect

All radioactive waste produced in The Netherlands is managed by COVRA, the central organization for radioactive waste. The Netherlands forms a good example of a country with a small nuclear power program which will end in the near future. However, radioisotope production, nuclear research and other industrial activities will continue to produce radioactive waste. For the small volume, but broad spectrum of radioactive waste, including TENORM, The Netherlands has developed a management system based on the principles to isolate, to control and to monitor the waste. Long term storage is an essential element of the management system and forms a necessary step in the strategy of controlled containment that will ultimately result in final removal of the waste. Since the waste will remain retrievable for long time new technologies and new disposal options can be applied when available and feasible.

Codee, H.

2002-02-26

174

77 FR 20077 - Request for a License To Export Radioactive Waste  

Federal Register 2010, 2011, 2012, 2013

...Request for a License To Export Radioactive Waste Pursuant to 10 CFR 110...Inc., February 14, 2012, radioactive waste tons of or disposal by...XW019, in the form of ash radioactive waste licensed facility...

2012-04-03

175

Directions in low-level radioactive waste management: A brief history of commercial low-level radioactive waste disposal  

SciTech Connect

This report presents a history of commercial low-level radioactive waste management in the United States, with emphasis on the history of six commercially operated low-level radioactive waste disposal facilities. The report includes a brief description of important steps that have been taken during the 1980s to ensure the safe disposal of low-level waste in the 1990s and beyond. These steps include the issuance of Title 10 Code of Federal Regulations Part 61, Licensing Requirements for the Land Disposal of Radioactive Waste, the Low-Level Radioactive Waste Policy Act of 1980, the Low-Level Radioactive Waste Policy Amendments Act of 1985, and steps taken by states and regional compacts to establish additional disposal sites. 42 refs., 13 figs., 1 tab.

Not Available

1990-10-01

176

Experimental and modelling investigations of the biogeochemistry of gas production from low and intermediate level radioactive waste  

Microsoft Academic Search

The degradation of organic wastes and the corrosion of metallic wastes and steel containers in low and intermediate level radioactive waste (LLW\\/ILW) repositories are important processes that affect repository geochemistry and the speciation and transport of radionuclides. Gas is generated in association with these degradation processes and this has the potential to overpressure the repository, which can promote transport of

Joe Small; Mikko Nykyri; Mika Helin; Ulla Hovi; Tuija Sarlin; Merja Itvaara

2008-01-01

177

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

National Technical Information Service (NTIS)

Sulfur polymer cement has been demonstrated to be superior to portland cement in the stabilization of numerous troublesome low- level radioactive wastes, notably mixed waste fly ash, which contains heavy metals. EG&G Idaho, Inc. conducted full-scale, wast...

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

1992-01-01

178

Cross flow filtration of aqueous radioactive tank wastes  

Microsoft Academic Search

The Tank Focus Area (TFA) of the Department of Energy (DOE) Office of Science and Technology addresses remediation of radioactive waste currently stored in underground tanks. Baseline technologies for treatment of tank waste can be categorized into three types of solid liquid separation: (a) removal of radioactive species that have been absorbed or precipitated, (b) pretreatment, and (c) volume reduction

D. J. McCabe; B. A. Reynolds; T. A. Todd; J. H. Wilson

1997-01-01

179

Nuclear Waste Isolation Means Zero Release of Radioactivity  

Microsoft Academic Search

New understandings of our planet require redefinition of our assumptions about nuclear waste. Isolation of radioactive waste from the biosphere and zero release of radioactivity is discussed in the context of a critique of current radiation standard-setting practices. Zero release requires the end of the nuclear fuel chain. Recommendations toward this goal are offered. Isolation The term \\

Mary Olson

180

High-Level Radioactive Waste: Safe Storage and Ultimate Disposal.  

ERIC Educational Resources Information Center

|Described are problems and techniques for safe disposal of radioactive waste. Degrees of radioactivity, temporary storage, and long-term permanent storage are discussed. Included are diagrams of estimated waste volumes to the year 2000 and of an artist's conception of a permanent underground disposal facility. (SL)|

Dukert, Joseph M.

181

Microbially mediated redox processes in natural analogues for radioactive waste  

Microsoft Academic Search

Natural analogues allow scientists to investigate biogeochemical processes relevant to radioactive waste disposal that occur on time scales longer than those that may be studied by time-limited laboratory experiments. The Palmottu UTh deposit in Finland and the Bangomb natural nuclear reactor in Gabon involve the study of natural uranium, and are both considered natural analogues for subsurface radioactive waste disposal.

Shelley A Haveman; Karsten Pedersen

2002-01-01

182

Early age behaviour of concrete supercontainers for radioactive waste disposal  

Microsoft Academic Search

Various types of radioactive waste were and are produced in Belgium. This waste originates from different producers: nuclear power plants, medical applications, industry, research centre, etc. During the past 25 years several preliminary repository designs were proposed. Today, the cylindrical supercontainer is considered to be the most promising Belgian design on the matter of enclosing the vitrified high level radioactive

Bart Craeye; Geert De Schutter; Hughes Van Humbeeck; Alain Van Cotthem

2009-01-01

183

Melt processing of radioactive waste: A technical overview  

SciTech Connect

Nuclear operations have resulted in the accumulation of large quantities of contaminated metallic waste which are stored at various DOE, DOD, and commercial sites under the control of DOE and the Nuclear Regulatory Commission (NRC). This waste will accumulate at an increasing rate as commercial nuclear reactors built in the 1950s reach the end of their projected lives, as existing nuclear powered ships become obsolete or unneeded, and as various weapons plants and fuel processing facilities, such as the gaseous diffusion plants, are dismantled, repaired, or modernized. For example, recent estimates of available Radioactive Scrap Metal (RSM) in the DOE Nuclear Weapons Complex have suggested that as much as 700,000 tons of contaminated 304L stainless steel exist in the gaseous diffusion plants alone. Other high-value metals available in the DOE complex include copper, nickel, and zirconium. Melt processing for the decontamination of radioactive scrap metal has been the subject of much research. A major driving force for this research has been the possibility of reapplication of RSM, which is often very high-grade material containing large quantities of strategic elements. To date, several different single and multi-step melting processes have been proposed and evaluated for use as decontamination or recycling strategies. Each process offers a unique combination of strengths and weaknesses, and ultimately, no single melt processing scheme is optimum for all applications since processes must be evaluated based on the characteristics of the input feed stream and the desired output. This paper describes various melt decontamination processes and briefly reviews their application in developmental studies, full scale technical demonstrations, and industrial operations.

Schlienger, M.E.; Buckentin, J.M.; Damkroger, B.K.

1997-04-01

184

Defense Waste Processing Facility radioactive operations -- Part 2, Glass making  

SciTech Connect

The Savannah River Site`s Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation`s first and world`s largest vitrification facility. Following a ten year construction period and nearly 3 year non-radioactive test program, the DWPF began radioactive operations in March, 1996. The results of the first 8 months of radioactive operations are presented. Topics include facility production from waste preparation batching to canister filling.

Carter, J.T.; Rueter, K.J.; Ray, J.W.; Hodoh, O.

1996-12-31

185

Significance of radiation effects in solid radioactive waste  

SciTech Connect

Proposed NRC criteria for disposal of high-level nuclear waste require development of waste packages to contain radionuclide for at least 1000 years, and design of repositories to prevent radionuclide release at an annual rate greater than 1 part in 100,000 of the total activity. The high-level wastes that are now temporarily stored as aqueous salts, sludges, and calcines must be converted to high-integrity solid forms that resist deterioration from radiation and other effects of long-term storage. Spent fuel may be encapsulated for similar long-term storage. Candidate waste forms beside the spent fuel elements themselves, include borosilicate and related glasses, mineral-like crystalline ceramics, concrete formulations, and metal-matrix glass or ceramic composites. these waste forms will sustain damage produced by beta-gamma radiation up to 10/sup 12/ rads, by alpha radiation up to 10/sup 19/ particles/g, by internal helium generation greater than about 0.1 atom percent, and by the atom transmutations accompanying radioactive decay. Current data indicate that under these conditions the glass forms suffer only minor volume changes, stored energy deposition, and leachability effects. The crystalline ceramics appear susceptible to the potentially more severe alterations accompanying metamictization and natural analogs of candidate materials are being examined to establish their suitability as waste forms. Helium concentrations in the waste forms are generally below thresholds for severe damage in either glass or crystalline ceramics at low temperatures, but microstructural effects are not well characterized. Transmutation effects remain to be established.

Permar, P H; McDonell, W R

1980-01-01

186

Hydrothermal processing of radioactive combustible waste  

SciTech Connect

Hydrothermal processing has been demonstrated for the treatment of radioactive combustible materials for the US Department of Energy. A hydrothermal processing system was designed, built and tested for operation in a plutonium glovebox. Presented here are results from the study of the hydrothermal oxidation of plutonium and americium contaminated organic wastes. Experiments show the destruction of the organic component to CO{sub 2} and H{sub 2}O, with 30 wt.% H{sub 2}O{sub 2} as an oxidant, at 540 C and 46.2 MPa. The majority of the actinide component forms insoluble products that are easily separated by filtration. A titanium liner in the reactor and heat exchanger provide corrosion resistance for the oxidation of chlorinated organics. The treatment of solid material is accomplished by particle size reduction and the addition of a viscosity enhancing agent to generate a homogeneous pumpable mixture.

Worl, L.A.; Buelow, S.J.; Harradine, D.; Le, L.; Padilla, D.D.; Roberts, J.H.

1998-09-01

187

Emerging Answers in the Management and Disposal of Radioactive Wastes  

Microsoft Academic Search

The National Policy of the United States is safe, permanent, surface or subsurface disposal of non-high-level radioactive waste from the nuclear fuel cycle to ensure long-term containment and isolation from the environment. That policy is contained in the fundamental U.S. laws governing nuclear fuel cycle wastes-the Atomic Energy Act, the Low-Level Radioactive Waste Policy Amendments Act of 1985, and the

L. W. Camper; J. E. Kennedy

2006-01-01

188

Microbial transformations of radioactive wastes and environmental restoration through bioremediation  

NASA Astrophysics Data System (ADS)

Bioremediation stabilizes and reclaims radionuclides and toxic metals from contaminated materials, soils, sediments, or wastes. The mechanism of microbial transformations of the radionuclides and toxic metals commonly found in energy wastes are summarized, and two processes for treating such wastes are described. In one process, anaerobic bacteria are used to concentrate, contain and stabilize the toxic metals and radionuclides in the waste, with a concurrent reduction in its volume. In the second process, the radionuclides and toxic metals are extracted from the wastes with citric acid which is then subjected to biodegradation, followed by photodegradation to recover the metals.

Francis, A. J.

1994-10-01

189

Advanced Test Reactor Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

Microsoft Academic Search

U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Advanced Test Reactor Complex facilities that manage radioactive waste. The radioactive waste management

Lisa Harvego; Brion Bennett

2011-01-01

190

A powder metallurgy approach for production of innovative radioactive waste forms  

SciTech Connect

The feasibility of producing a single metal-matrix composite form rather than two separate forms consisting of a cast metal alloy ingot (such as Type 316SS + Zr) and a ceramic glass-bonded zeolite Na{sub 12}(AlO{sub 2}){sub 12}(SiO{sub 2}){sub 12} has been demonstrated. This powder metallurgy approach consists of mixing the powder of the two separate waste forms together followed by compaction by hot isostatic pressing. Such a radioactive waste form would have the potential advantages of reducing the total waste volume, good thermal conductivity, stability, and surfaces with limited oxide layer formation. 5 refs., 8 figs., 2 tabs.

Keiser, D.D. Jr.; Crawford, D.C. [Argonne National Lab., Idaho Falls, ID (United States); Bhaduri, S. [Univ. of Idaho, Moscow, ID (United States)] [and others

1997-07-01

191

Identification of radioactive mixed wastes in commercial low-level wastes  

Microsoft Academic Search

A literature review and survey were conducted on behalf of the US NRC Division of Waste Management to determine whether any commercial low-level radioactive wastes (LLW) could be considered hazardous as defined by EPA under 40 CFR Part 261. The purpose of the study was to identify broad categories of LLW which may require special management as radioactive mixed waste,

B. S. Bowerman; C. R. Kempf; D. R. MacKenzie; B. Siskind; P. L. Piciulo

1986-01-01

192

Identification of radioactive mixed wastes in commercial low-level wastes  

Microsoft Academic Search

A literature review and survey were conducted on behalf of the US NRC Division of Waste Management to determine whether any commercial low-level radioactive wastes (LLW) could be considered hazardous as defined by EPA under 40 CFR Part 261. The purpose of the study was to identify broad categories of LLW which may require special management as radioactive mixed waste,

B. S. Bowerman; C. R. Kempf; D. R. MacKenzie; B. Siskind; P. L. Piciulo

1985-01-01

193

Reduction of radioactive secondary waste with steam reforming in treatment of waste TBP\\/dodecane  

Microsoft Academic Search

Waste tributyl phosphate (TBP) and normal dodecane generated from R and D activities on recycle of nuclear fuel has been stored in Japan Atomic Energy Agency (JAEA). If it is incinerated, a large quantity of contaminated phosphorous compounds will be generated as radioactive secondary wastes. The objective of this study is to reduce the generation of the radioactive secondary wastes

Tomoyuki Sone; Toshiki Sasaki; Hiromi Yamaguchi

2007-01-01

194

Evaluating detonation possibilities in a Hanford radioactive waste tank  

Microsoft Academic Search

Since the early 1940s, radioactive wastes generated from the defense operations at the Hanford Site have been stored in underground waste storage tanks. During the intervening years, the waste products in some of these tanks have transformed into a potentially hazardous mixture of gases and solids as a result of radiolytic and thermal chemical reactions. One tank in particular, Tank

J. R. Travis; R. K. Fujita; M. C. Ross; J. N. Edwards; J. E. Shepherd

1994-01-01

195

Evaluating detonation possibilities in a Hanford radioactive waste tank  

Microsoft Academic Search

Since the early 1940s, radioactive wastes generated from the defense operations at the Hanford site have been stored in underground waste storage tanks. During the intervening years, the waste products in some of these tanks have transformed into a potentially hazardous mixture of gases and solids as a result of radiolytic and thermal chemical reactions. One tank in particular, tank

J. R. Travis; R. K. Fujita; M. C. Ross; J. N. Edwards; J. E. Shepherd

1994-01-01

196

Evaluation of platinum alloy melters for vitrification of radioactive wastes  

Microsoft Academic Search

A bushing melter constructed of platinum-rhodium is being evaluated for vitrification of special high gamma radioactive wastes for long-term recoverable storage. The basic design parallels that used in the fiberglass industry. Nonradioactive chemical surrogate wastes have been used in the process work. The simulant wastes and glass frit are fed separately to the melter and mixed within the liquefied mass.

1997-01-01

197

Feed Basis for Processing Relatively Low Radioactivity Waste Tanks  

SciTech Connect

This paper presents the characterization of potential feed for processing relatively low radioactive waste tanks. The feed characterization is based on waste characterization data extracted from the waste characterization system. This data is compared to salt cake sample results from Tanks 37, 38 and 41.

Pike, J.A.

2002-07-09

198

Feed Basis for Processing Relatively Low Radioactivity Waste Tanks  

SciTech Connect

This paper presents the characterization of potential feed for processing relatively low radioactive waste tanks. The feed characterization is based on waste characterization data extracted from the waste characterization system. This data is compared to salt cake sample results from Tanks 37, 38, and 41.

Jones (contact), R.T.

2003-02-18

199

Low-level radioactive waste regulation: Science, politics and fear  

SciTech Connect

An inevitable consequence of the use of radioactive materials is the generation of radioactive wastes and the public policy debate over how they will be managed. In 1980, Congress shifted responsibility for the disposal of low-level radioactive wastes from the federal government to the states. This act represented a sharp departure from more than 30 years of virtually absolute federal control over radioactive materials. Though this plan had the enthusiastic support of the states in 1980, it now appears to have been at best a chimera. Radioactive waste management has become an increasingly complicated and controversial issue for society in recent years. This book discusses only low-level wastes, however, because Congress decided for political reasons to treat them differently than high-level wastes. The book is based in part on three symposia sponsored by the division of Chemistry and the Law of the American Chemical Society. Each chapter is derived in full or in part from presentations made at these meetings, and includes: (1) Low-level radioactive wastes in the nuclear power industry; (2) Low-level radiation cancer risk assessment and government regulation to protect public health; and (3) Low-level radioactive waste: can new disposal sites be found.

Burns, M.E. (ed.)

1988-01-01

200

Technical evaluation of proposed Ukrainian Central Radioactive Waste Processing Facility  

SciTech Connect

This technical report is a comprehensive evaluation of the proposal by the Ukrainian State Committee on Nuclear Power Utilization to create a central facility for radioactive waste (not spent fuel) processing. The central facility is intended to process liquid and solid radioactive wastes generated from all of the Ukrainian nuclear power plants and the waste generated as a result of Chernobyl 1, 2 and 3 decommissioning efforts. In addition, this report provides general information on the quantity and total activity of radioactive waste in the 30-km Zone and the Sarcophagus from the Chernobyl accident. Processing options are described that may ultimately be used in the long-term disposal of selected 30-km Zone and Sarcophagus wastes. A detailed report on the issues concerning the construction of a Ukrainian Central Radioactive Waste Processing Facility (CRWPF) from the Ukrainian Scientific Research and Design institute for Industrial Technology was obtained and incorporated into this report. This report outlines various processing options, their associated costs and construction schedules, which can be applied to solving the operating and decommissioning radioactive waste management problems in Ukraine. The costs and schedules are best estimates based upon the most current US industry practice and vendor information. This report focuses primarily on the handling and processing of what is defined in the US as low-level radioactive wastes.

Gates, R.; Glukhov, A.; Markowski, F.

1996-06-01

201

Nuclear waste storage container with metal matrix  

DOEpatents

The invention relates to a storage container for high-level waste having a metal matrix for the high-level waste, thereby providing greater impact strength for the waste container and increasing heat transfer properties.

Sump, Kenneth R. (Kennewick, WA)

1978-01-01

202

Assessment of recycling or disposal alternatives for radioactive scrap metal  

SciTech Connect

The US Department of Energy, Office of Environmental Restoration and Waste Management, is participating with the Organization for Economic Cooperation and Development (OECD) is an evaluation of management alternatives for radioactive scarp metals. For this purpose, Argonne National Laboratory is assessing alternatives for radioactive scrap metals. For this purpose, Argonne National Laboratory is assessing environmental and societal implications of recycling and/or disposal process alternatives (with metal replacement). Findings will be presented in a report from the OECD Task Group. This paper focuses on the radiological risk assessment and dose estimate sensitivity analysis. A ``tiered`` concept for release categories, with and without use restrictions, is being developed. Within the tiers, different release limits may be indicated for specific groupings of radionuclides. Depending on the spectrum of radionuclides that are present and the level of residual activity after decontamination and/or smelting, the scrap may be released for unrestricted public use or for specified public uses, or it may be recycled within the nuclear industry. The conversatism of baseline dose estimates is examined, and both more realistic parameter values and protective measures for workers are suggested.

Murphie, W.E.; Lilly, M.J. III [USDOE Assistant Secretary for Environmental Restoration and Waste Management, Washington, DC (United States). Office of Environmental Restoration; Nieves, L.A.; Chen, S.Y. [Argonne National Lab., IL (United States)

1993-10-01

203

Assessment of public perception of radioactive waste management in Korea.  

SciTech Connect

The essential characteristics of the issue of radioactive waste management can be conceptualized as complex, with a variety of facets and uncertainty. These characteristics tend to cause people to perceive the issue of radioactive waste management as a 'risk'. This study was initiated in response to a desire to understand the perceptions of risk that the Korean public holds towards radioactive waste and the relevant policies and policy-making processes. The study further attempts to identify the factors influencing risk perceptions and the relationships between risk perception and social acceptance.

Trone, Janis R.; Cho, SeongKyung (Myongji University, Korea); Whang, Jooho (Kyung Hee University, Korea); Lee, Moo Yul

2011-11-01

204

40 CFR 268.34 - Waste specific prohibitions-toxicity characteristic metal wastes.  

Code of Federal Regulations, 2013 CFR

...disposal: newly identified characteristic wastes from elemental phosphorus processing; radioactive wastes mixed with EPA Hazardous...2000, newly identified characteristic wastes from elemental phosphorus processing, radioactive waste mixed with D004-D011...

2013-07-01

205

Polyoxometalates for radioactive waste treatment. 1998 annual progress report  

SciTech Connect

'This research is directed towards the use of polyoxoanions of the early transition metals (primarily tungsten) as possible sequestrants and storage matrices for lanthanide, actinide, and technetium species. The latter substances are important radioactive components of tank wastes from spent commercial nuclear fuel, but are present in low proportion by mass. Technetium is a particularly troublesome component because it is highly mobile in groundwater and is volatilized in vitrification processes currently under examination for long-term storage. Scientific goals: synthesis and characterization of new and selective polyoxotungstate complexes of Ln{sup 3+}, An{sup 4+}, UO{sub 2}{sup 2+}; exploration of stable polyoxoanions containing Tc (using, in the first instance, Re as a nonradioactive surrogate); thermal conversion of polytungstate complexes to tungsten bronze materials for their evaluation as inert storage matrices. This report summarizes the results after 20 months of a 3-year project.'

Pope, M.T.

1998-06-01

206

Defense Waste Processing Facility Radioactive Operations - Year Two  

SciTech Connect

The Savannah River Site`s Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation`s first high-level radioactive waste vitrification facility. This waste (130 million liters) which has been stored in carbon steel underground tanks and is now being pretreated, melted into a highly durable borosilicate glass and poured into stainless steel canisters for eventual disposal in a geologic repository. Following a ten-year construction period and nearly three-year nonradioactive test program, the DWPF began radioactive operations in March 1996. The first nine months of radioactive operations have been reported previously. As with any complex technical facility, difficulties were encountered during the transition to radioactive operations. Results of the second year of radioactive operations are presented in this paper. The discussion includes: feed preparation and glass melting, resolution of the melter pouring issues, improvements in processing attainment and throughput, and planned improvements in laboratory attainment and throughput.

Occhipinti, J.E.; Carter, J.T.; Edwards, R.E.; Beck, R.S.; Iverson, D.C.

1998-03-01

207

Hanford Site radioactive mixed waste thermal treatment initiative.  

National Technical Information Service (NTIS)

This paper is a progress report of current Westinghouse Hanford Company engineering activities related to the implementation of a program for the thermal treatment of the Hanford Site radioactive mixed waste. Topics discussed include a site-specific engin...

B. G. Place J. G. Riddelle

1993-01-01

208

Commentary: Radioactive Wastes and Damage to Marine Communities  

ERIC Educational Resources Information Center

|Discusses the effects of radioactive wastes on marine communities, with particular reference to the fitness of populations and the need for field and laboratory studies to provide evidence of ecological change. (JR)|

Wallace, Bruce

1974-01-01

209

Commentary: Radioactive Wastes and Damage to Marine Communities  

ERIC Educational Resources Information Center

Discusses the effects of radioactive wastes on marine communities, with particular reference to the fitness of populations and the need for field and laboratory studies to provide evidence of ecological change. (JR)

Wallace, Bruce

1974-01-01

210

Erosion and Safety of the Underground Disposal of Radioactive Wastes.  

National Technical Information Service (NTIS)

In this report the problem concerning the evaluation of long-term geomorphic stability is discussed, with regard to the influence of possible morphologic modification of topographic surface on the containment of radioactive wastes in deep geological forma...

S. Grauso C. Polizzano

1986-01-01

211

Rock Opening Design and Analyses for Radioactive Waste Repositories.  

National Technical Information Service (NTIS)

The report assesses the uniqueness of the radioactive waste disposal when viewed from the standpoint of design, construction, and operation of underground cavities dedicated for that use. Underground excavations design and construction for mining and civi...

W. C. Lyons K. I. Oravecz B. J. Gallaher D. Buddecke

1978-01-01

212

High-level radioactive waste in Canada. Background paper.  

National Technical Information Service (NTIS)

The disposal of radioactive waste is one of the most challenging environmental problems facing Canada today. Since the Second World War, when Canadian scientists first started to investigate nuclear reactions, there has been a steady accumulation of such ...

R. Fawcett

1993-01-01

213

Solidification of Radioactive Wastes with Cement (A Literature Study).  

National Technical Information Service (NTIS)

The present study is structured according to thematic points of view. Emphasis was laid on a precise description of the behaviour of cement used for the solidification of radioactive waste. By utilizing different additives, processing as well as propertie...

K. Rietmann S. Huwyler C. Caflisch A. Della Casa

1984-01-01

214

Natural diatomite process for removal of radioactivity from liquid waste.  

PubMed

Diatomite has a number of unique physical properties and has found diversified industrial utilization. The filtration characteristics are particularly significant in the purification of liquids. The purpose of this study was to test natural diatomaceous earth (diatomite) as an alternative material that could be used for removal of radioactivity from liquid waste. A pilot-scale column-type device was designed. Natural diatomite samples were ground, sieved and prepared to use as sorption media. In this study, real waste liquid was used as radioactive liquid having special conditions. The liquid waste contained three radionuclides (Cs-137, Cs-134 and Co-60). Following the treatment by diatomite, the radioactivity of liquid waste was reduced from the initial 2.60 Bq/ml to less than 0.40 Bq/ml. The results of this study show that most of the radioactivity was removed from the solution by processing with diatomite. PMID:17049259

Osmanlioglu, Ahmet Erdal

2006-10-16

215

40 CFR 147.3005 - Radioactive waste injection wells.  

Code of Federal Regulations, 2012 CFR

...CONTINUED) STATE, TRIBAL, AND EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS Lands of the Navajo, Ute Mountain Ute, and All Other New Mexico Tribes § 147.3005 Radioactive waste injection wells. Notwithstanding §§...

2012-07-01

216

Monitoring plan for routine organic air emissions at the Radioactive Waste Management Complex Waste Storage Facilities.  

National Technical Information Service (NTIS)

This monitoring plan provides the information necessary to perform routine organic air emissions monitoring at the Waste Storage Facilities located at the Transuranic Storage Area of the Radioactive Waste Management Complex at the Idaho National Engineeri...

K. J. Galloway J. G. Jolley

1994-01-01

217

Evaluation of air effluent and workplace radioactivity monitoring at the Waste Isolation Pilot Plant.  

National Technical Information Service (NTIS)

Improvements are needed in the Waste Isolation Pilot Plant (WIPP) air effluent and workplace radioactivity monitoring prior to receipt of radioactive wastes. This report provides a detailed review Zf radioactivity air monitoring regulatory requirements an...

W. T. Bartlett

1993-01-01

218

76 FR 53980 - Request for a License To Import Radioactive Waste  

Federal Register 2010, 2011, 2012, 2013

...COMMISSION Request for a License To Import Radioactive Waste Pursuant to 10 CFR 110.70...GE Hitachi Nuclear Energy, LLC. Radioactive waste Up to 210 Cobalt- Recycling...Cobalt-60 sources. or storage and radioactive Combined total disposition....

2011-08-30

219

Radioactive waste management criteria in fusion reactor materials selection  

Microsoft Academic Search

Fusion reactors will have to meet both quantitative and qualitative criteria for the disposal and\\/or reuse of radioactive materials. The most important quantitative criteria presently govern the near-surface disposal of radioactive wastes in the United States. This paper discusses the elemental concentration limits for first wall materials if they are to be acceptable as low-level waste. Qualitative comparisons readily understood

J. S. Herring; S. Fetter

1987-01-01

220

Radioactive Liquid Waste Treatment Facility: Environmental Information Document  

SciTech Connect

At Los Alamos National Laboratory (LANL), the treatment of radioactive liquid waste is an integral function of the LANL mission: to assure U.S. military deterrence capability through nuclear weapons technology. As part of this mission, LANL conducts nuclear materials research and development (R&D) activities. These activities generate radioactive liquid waste that must be handled in a manner to ensure protection of workers, the public, and the environment. Radioactive liquid waste currently generated at LANL is treated at the Radioactive Liquid Waste Treatment Facility (RLWTF), located at Technical Area (TA)-50. The RLWTF is 30 years old and nearing the end of its useful design life. The facility was designed at a time when environmental requirements, as well as more effective treatment technologies, were not inherent in engineering design criteria. The evolution of engineering design criteria has resulted in the older technology becoming less effective in treating radioactive liquid wastestreams in accordance with current National Pollutant Discharge Elimination System (NPDES) and Department of Energy (DOE) regulatory requirements. Therefore, to support ongoing R&D programs pertinent to its mission, LANL is in need of capabilities to efficiently treat radioactive liquid waste onsite or to transport the waste off site for treatment and/or disposal. The purpose of the EID is to provide the technical baseline information for subsequent preparation of an Environmental Impact Statement (EIS) for the RLWTF. This EID addresses the proposed action and alternatives for meeting the purpose and need for agency action.

Haagenstad, H.T.; Gonzales, G.; Suazo, I.L. [Los Alamos National Lab., NM (United States)

1993-11-01

221

Office of Civilian Radioactive Waste Management annual report to Congress  

SciTech Connect

This seventh Annual Report to Congress by the Office of Civilian Radioactive Waste Management (OCRWM) describes activities and expenditures of the Office during fiscal years (FY) 1989 and 1990. In November 1989, OCRWM is responsible for disposing of the Nation`s spent nuclear fuel and high-level radioactive waste in a manner that protects the health and safety of the public and the quality of the environment. To direct the implementation of its mission, OCRWM has established the following objectives: (1) Safe and timely disposal: to establish as soon as practicable the ability to dispose of radioactive waste in a geologic repository licensed by the NRC. (2) Timely and adequate waste acceptance: to begin the operation of the waste management system as soon as practicable in order to obtain the system development and operational benefits that have been identified for the MRS facility. (3) Schedule confidence: to establish confidence in the schedule for waste acceptance and disposal such that the management of radioactive waste is not an obstacle to the nuclear energy option. (4) System flexibility: to ensure that the program has the flexibility necessary for adapting to future circumstances while fulfilling established commitments. To achieve these objectives, OCRWM is developing a waste management system consisting of a geologic repository for permanent disposed deep beneath the surface of the earth, a facility for MRS, and a system for transporting the waste.

NONE

1990-12-01

222

Greater-than-Class C low-level waste characterization. Appendix F: Greater-than-Class C low-level radioactive waste light water reactor projections  

SciTech Connect

This study characterizes potential greater-than-Class C low-level radioactive waste streams, estimates the amounts of waste generated, and estimates their radionuclide content and distribution. Several types of low-level radioactive wastes produced by light water reactors were identified in an earlier study as being potential greater-than-Class C low-level waste, including specific activated metal components and certain process wastes in the form of cartridge filters and decontamination resins. Light water reactor operating parameters and current management practices at operating plants were reviewed and used to estimate the amounts of potential greater-than-Class C low-level waste generated per fuel cycle. The amounts of routinely generated activated metal components and process waste were estimated as a function of fuel cycle. Component-specific radionuclide content and distribution was calculated for activated metals components. Empirical data from actual low-level radioactive waste streams were used to estimate radionuclide content and distribution for process wastes. The greater-than-Class C low-level waste volumes that could be generated through plant closure were also estimated, along with volumes and activities for potential greater-than-Class C activated metals generated at decommissioning.

Tuite, P.; Tuite, K.; Levin, A.; O`Kelley, M.

1991-08-01

223

State-of-the-art report on low-level radioactive waste treatment  

SciTech Connect

An attempt is made to identify the main sources of low-level radioactive wastes that are generated in the United States. To place the waste problem in perspective, rough estimates are given of the annual amounts of each generic type of waste that is generated. Most of the wet solid wastes arise from the cleanup of gaseous and liquid radioactive streams prior to discharge or recycle. The treatment of the process streams and the secondary wet solid wastes thus generated is described for each type of government or fuel cycle installation. Similarly, the institutional wet wastes are also described. The dry wastes from all sources have smilar physical and chemical characteristics in that they can be classified as compactible, noncompactible, combustible, noncombustible, or combinations thereof. The various treatment options for concentrated or solid wet wastes and for dry wastes are discussed. Among the dry-waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting, and shredding. Organic materials can usually be incinerated or, in some cases, biodegraded. The filter sludges, spent resins, incinerator ashes, and concentrated liquids are usually solidified in cement, urea-formaldehyde, or unsaturated polyester resins prior to burial. Asphalt has not yet been used as a solidificaton agent in the United States, but it probably will be used in the near future. The treatment of radioactive medical and bioresearch wastes is described, but the waste from radiochenmical, pharmaceutical, and other industries is not well defined at the present time. Recovery of waste metals and treatment of hazardous contaminated wastes are discussed briefly. Some areas appearing to need more research, development, and demonstration are specifically pointed out.

Kibbey, A.H.; Godbee, H.W.

1980-09-01

224

Monitoring plan for routine organic air emissions at the Radioactive Waste Management Complex Waste Storage Facilities  

Microsoft Academic Search

This monitoring plan provides the information necessary to perform routine organic air emissions monitoring at the Waste Storage Facilities located at the Transuranic Storage Area of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The Waste Storage Facilities include both the Type I and II Waste Storage Modules. The plan implements a dual method approach where two

K. J. Galloway; J. G. Jolley

1994-01-01

225

Low-level radioactive waste disposal technologies used outside the United States  

Microsoft Academic Search

Low-level radioactive waste (LLW) disposal technologies are an integral part of the waste management process. In the United States, commercial LLW disposal is the responsibility of the State or groups of States (compact regions). The United States defines LLW as all radioactive waste that is not classified as spent nuclear fuel, high- level radioactive waste, transuranic waste, or by-product material

K. J. Templeton; S. J. Mitchell; P. M. Molton; I. W. Leigh

1994-01-01

226

Radionuclide characterization studies of radioactive waste produced at high-energy accelerators  

NASA Astrophysics Data System (ADS)

The European Laboratory for Particle Physics (CERN) has been operating accelerators for high-energy physics both on Swiss and French territory for over 50 years. Due to the interaction of the particle beams with matter, the accelerator components and the surroundings become activated and shall be treated as radioactive waste once the end of their operational lifetime is reached. For disposal towards the final repositories the radioactive waste legislation of both CERN Host-States requires the knowledge of the radionuclide inventory. This paper discusses the studies that are carried out at CERN for the characterization of the metallic radioactive waste produced every year in the several high-energy accelerators. The radionuclide inventory as well as the specific activity of radioactive waste originating from accelerators varies depending on the accelerated beam, on the location of the material with respect to the beam losses and the decay time already elapsed. The approach proposed at CERN is based on an estimate of the specific activity per radionuclide with the Monte-Carlo code FLUKA, by simulating the radiation environment to which the radioactive waste was exposed during its operational lifetime. This method has been validated for the CERN ISOLDE facility by both ?-spectrometry and Monte-Carlo simulation of the target. The use of this method in those cases where the irradiation conditions are not known with sufficient precision requires careful extrapolation based on additional dose-rate and gamma-spectrometry measurements.

Ulrici, L.; Brugger, M.; Otto, Th.; Roesler, S.

2006-06-01

227

76 FR 58543 - Draft Policy Statement on Volume Reduction and Low-Level Radioactive Waste Management  

Federal Register 2010, 2011, 2012, 2013

...and Low-Level Radioactive Waste Management AGENCY: Nuclear Regulatory...and Low-Level Radioactive Waste Management that updates the 1981 Policy...Management Programs, Division of Waste Management and Environmental...

2011-09-21

228

25 CFR 170.903 - Who notifies tribes of the transport of radioactive waste?  

Code of Federal Regulations, 2010 CFR

...notifies tribes of the transport of radioactive waste? 170.903 Section 170...Provisions Hazardous and Nuclear Waste Transportation § 170.903...notifies tribes of the transport of radioactive waste? The Department of...

2010-04-01

229

25 CFR 170.903 - Who notifies tribes of the transport of radioactive waste?  

Code of Federal Regulations, 2010 CFR

...notifies tribes of the transport of radioactive waste? 170.903 Section 170...Provisions Hazardous and Nuclear Waste Transportation § 170.903...notifies tribes of the transport of radioactive waste? The Department of...

2009-04-01

230

Determination of noble metals in Savannah River Site high-level radioactive sludge  

SciTech Connect

High-level radioactive sludge at the Savannah River Site (SRS) will be processed at the Defense Waste Processing Facility (DWPF) into durable borosilicate glass wasteforms. The sludges are analyzed for elemental content before processing to ensure compatibility with the glass-making processes. Noble metal fission products in sludge, can under certain conditions, cause problems in the glass melter. Therefore, reliable noble metal determinations are important. The scheme used to measure noble metals in SRS sludges consists of dissolving sludge with hot aqua regia followed by determinations with inductively coupled plasma-atomic emission spectroscopy (ICP-AES) and ICP-Mass Spectroscopy (ICP-MS) techniques. ICP-MS is the preferred method for measuring trace levels of noble metals in SRS radioactive waste because of superior sensitivity. Analytical results are presented for the two major types of SRS sludge.

Coleman, C.J.; Kinard, W.F.; Bibler, N.E.; Bickford, D.F.; Ramsey, W.G.

1990-12-31

231

Rock opening design and analyses for radioactive waste repositories  

Microsoft Academic Search

The report assesses the uniqueness of the radioactive waste disposal when viewed from the standpoint of design, construction, and operation of underground cavities dedicated for that use. Underground excavations design and construction for mining and civil engineering projects are reviewed and their application to the waste repository problem are considered. The particular subjects addressed in some detail are underground layouts,

W. C. Lyons; K. I. Oravecz; B. J. Gallaher; D. Buddecke

1978-01-01

232

High-level radioactive waste from light-water reactors  

Microsoft Academic Search

The production of radioactive nuclei during the operation of a light-water reactor is traced, and their decay history is followed. The potential environmental impacts of this waste are calculated and shown to be comparable to those of other materials we produce. Assuming deep burial, it is shown that there are important time delays which prevent the waste from reaching the

Bernard Cohen

1977-01-01

233

TREATMENT OF LOW-LEVEL AQUEOUS RADIOACTIVE WASTES  

Microsoft Academic Search

S>A review is given on various methods for the treatment of low-level ; aqueous radioactive wastes, and the waste disposal system at Latina, Italy, is ; described. The plant is designed to treat fuel element cooling pond water ; together with other low-active streams arising on the site, producing clean water ; that can be used again on the site,

Cartwright

1962-01-01

234

Strategy for Radioactive Waste Disposal in Crystalline Rocks  

Microsoft Academic Search

A strategy for waste disposal is proposed in which the repository would be situated in a crystalline rock mass beneath a blanket of sedimentary rocks whose ground-water flow characteristics are well understood. Such an approach exemplifies the concept of multiple barriers to the isolation of radioactive wastes from the biosphere. This strategy has the advantages that (i) ground-water flow within

John D. Bredehoeft; Tidu Maini

1981-01-01

235

ADSORPTION OF RADIOACTIVE WASTES BY SAVANNAH RIVER PLANT SOIL  

Microsoft Academic Search

The adsorption of radioisotopes on soil was investigated in the ; laboratory to determine the behavior of lowlevel radioactive waste solutions ; discharged to the ground. Strontium, cesium, and plutonium distributions between ; soil and waste solution were studied. The effects of cation concentration and ; acidity were determined. The results of the distribution experiments, and ; material balance considerations,

W. E. PROUT

1958-01-01

236

FOAMING IN RADIOACTIVE WASTE TREATMENT AND IMMOBILIZATION PROCESSES  

EPA Science Inventory

The physical mechanisms of the formation of foam in radioactive waste treatment and waste immobilization processes are poorly understood. The objective of this research is to develop a basic understanding of the mechanisms that produce foaming, to identify the key parameters whic...

237

Process for immobilizing radioactive boric acid liquid wastes  

SciTech Connect

A method is described for immobilizing radioactive boric acid waste solutions comprising: neutralizing a boric acid waste solution containing radionuclides with calcium hydroxide and forming a precipitate, evaporating the precipitate to near dryness, and firing the dry precipitate to form a calcium borate glass product containing the radionuclides.

Greenhalgh, W.O.

1986-06-17

238

Radioactive Waste Storage Materials: Their alpha Recoil Aging  

Microsoft Academic Search

Ion implantation experiments suggest that the accumulation of alpha -recoil damage in radioactive waste storage materials, which behave like solid-state track detectors, plays a drastic role in their long-term degradation. The understanding of alpha -recoil ``aging,'' overlooked in earlier studies, offers new guidelines for improving waste storage conditions.

J. C. Dran; M. Maurette; J. C. Petit

1980-01-01

239

Metal, mineral waste processing and secondary recovery  

Microsoft Academic Search

Approximately 40 million tons of precious metals chemical wastes are produced in the United States every year. An estimated five percent of these wastes are being reused\\/recycled to recover the precious and critical metals they contain. The rest of these chemical wastes are disposed of by the methods incineration, dumping at sea and dumping on land. In this paper, an

1987-01-01

240

Discussions about safety criteria and guidelines for radioactive waste management.  

PubMed

In Japan, the clearance levels for uranium-bearing waste have been established by the Nuclear Safety Commission (NSC). The criteria for uranium-bearing waste disposal are also necessary; however, the NSC has not concluded the discussion on this subject. Meanwhile, the General Administrative Group of the Radiation Council has concluded the revision of its former recommendation 'Regulatory exemption dose for radioactive solid waste disposal', the dose criteria after the institutional control period for a repository. The Standardization Committee on Radiation Protection in the Japan Health Physics Society (The Committee) also has developed the relevant safety criteria and guidelines for existing exposure situations, which are potentially applicable to uranium-bearing waste disposal. A new working group established by The Committee was initially aimed at developing criteria and guidelines specifically for uranium-bearing waste disposal; however, the aim has been shifted to broader criteria applicable to any radioactive wastes. PMID:21531746

Yamamoto, Masafumi

2011-04-29

241

Monte Carlo simulations of radioactive waste embedded into polymer  

NASA Astrophysics Data System (ADS)

Radioactive waste is generated from the nuclear applications and it should properly be managed according to the regulations set by the regulatory authority. Poly(carbonate urethane) and poly(bisphenol a-co-epichlorohydrin) are radiation-resistant polymers and they are possible candidate materials that can be used in the radioactive waste management. In this study, maximum allowable waste activity that can be embedded into these polymers and dose rate distribution of the waste drum (containing waste and the polymer matrix) were found via Monte Carlo simulations. The change of mechanical properties of above-mentioned polymers was simulated and their variations within the waste drum were determined for 15, 30 and 300 years after embedding.

zdemir, Tongu; Usanmaz, Ali

2009-09-01

242

Treatment and Stabilization of Potentially Pyrophoric Radioactive Metal Chips and Turnings  

Microsoft Academic Search

As part of the continuing mission to decontaminate, decommission, and restore environmental quality at multiple sites throughout the U.S. Department of Energy (US DOE) nuclear complex, approximately 2,000 containers of potentially pyrophoric radioactive metal chips and turnings, weighing over 192,000 kilograms have been identified. These wastes, mostly depleted uranium (DU) and thorium metals, must be treated to remove or immobilize

B. R. Crocker; R. Grondin; T. Yarbrough

2006-01-01

243

Industrial-Scale Processes For Stabilizing Radioactively Contaminated Mercury Wastes  

SciTech Connect

This paper describes two industrial-scaled processes now being used to treat two problematic mercury waste categories: elemental mercury contaminated with radionuclides and radioactive solid wastes containing greater than 260-ppm mercury. The stabilization processes were developed by ADA Technologies, Inc., an environmental control and process development company in Littleton, Colorado. Perma-Fix Environmental Services has licensed the liquid elemental mercury stabilization process to treat radioactive mercury from Los Alamos National Laboratory and other DOE sites. ADA and Perma-Fix also cooperated to apply the >260-ppm mercury treatment technology to a storm sewer sediment waste collected from the Y-12 complex in Oak Ridge, TN.

Broderick, T. E.; Grondin, R.

2003-02-24

244

Emerging Answers in the Management and Disposal of Radioactive Wastes  

SciTech Connect

The National Policy of the United States is safe, permanent, surface or subsurface disposal of non-high-level radioactive waste from the nuclear fuel cycle to ensure long-term containment and isolation from the environment. That policy is contained in the fundamental U.S. laws governing nuclear fuel cycle wastes-the Atomic Energy Act, the Low-Level Radioactive Waste Policy Amendments Act of 1985, and the recently passed National Defense Authorization Act for Fiscal Year 2005 (NDAA), among others. The U.S. has been largely successful in implementing this policy to date and most of the low-level radioactive waste (LLRW) generated by NRC licensees has been safely disposed, rather than stored. Only greater-than-class C (GTCC) LLRW has been without a disposal option. At the same time, the U.S. program for radioactive waste disposal can be improved in a number of ways to enhance safety, to better utilize risk information in decision-making, to improve the efficiency and effectiveness of the overall program, and to enhance openness. This paper will address four 'emerging answers' that aid in moving the country towards the goal of safe, permanent disposal for all types of non-high level radioactive waste generated in the nuclear fuel cycle. (authors)

Camper, L.W.; Kennedy, J.E. [U.S. Nuclear Regulatory Commission Mail Stop T-7-J-8, Washington DC 20555 (United States)

2006-07-01

245

Greater-than-Class C low-level radioactive waste characterization. Appendix A-3: Basis for greater-than-Class C low-level radioactive waste light water reactor projections  

SciTech Connect

This study characterizes low-level radioactive waste types that may exceed Class C limits at light water reactors, estimates the amounts of waste generated, and estimates radionuclide content and distribution within the waste. Waste types that may exceed Class C limits include metal components that become activated during operations, process wastes such as cartridge filters and decontamination resins, and activated metals from decommissioning activities. Operating parameters and current management practices at operating plants are reviewed and used to estimate the amounts of low-level waste exceeding Class C limits that is generated per fuel cycle, including amounts of routinely generated activated metal components and process waste. Radionuclide content is calculated for specific activated metals components. Empirical data from actual low-level radioactive waste are used to estimate radionuclide content for process wastes. Volumes and activities are also estimated for decommissioning activated metals that exceed Class C limits. To estimate activation levels of decommissioning waste, six typical light water reactors are modeled and analyzed. This study does not consider concentration averaging.

Mancini, A.; Tuite, P.; Tuite, K.; Woodberry, S.

1994-09-01

246

System for chemically digesting low level radioactive, solid waste material  

DOEpatents

An improved method and system for chemically digesting low level radioactive, solid waste material having a high through-put. The solid waste material is added to an annular vessel (10) substantially filled with concentrated sulfuric acid. Concentrated nitric acid or nitrogen dioxide is added to the sulfuric acid within the annular vessel while the sulfuric acid is reacting with the solid waste. The solid waste is mixed within the sulfuric acid so that the solid waste is substantilly fully immersed during the reaction. The off gas from the reaction and the products slurry residue is removed from the vessel during the reaction.

Cowan, Richard G. (Kennewick, WA); Blasewitz, Albert G. (Richland, WA)

1982-01-01

247

Data base for radioactive waste management: impacts analyses methodology report  

SciTech Connect

This document is prepared in three volumes and provides part of the technical support to the draft environmental impact statement (NUREG-0782) on a proposed regulation, 10CFR Part 61, setting forth licensing requirements for land disposal of low level radioactive waste. Volume 3 provides a methodology for analyzing the impacts of handling and disposing of low level waste based upon consideration of alternative waste forms, disposal facility design and operating practices, disposal facility environmental characteristics, and institutional control considerations.

Oztunali, O.I.; Re, G.C.; Moskowitz, P.M.; Picazo, E.D.; Pitt, C.J.

1981-11-01

248

Managing low-level radioactive waste in Massachusetts. Final report  

Microsoft Academic Search

As one of the country's largest generators of low-level radioactive waste, Massachusetts has begun independently seeking solutions to the questions surrounding low-level waste management issues. The Massachusetts Department of Public Health, Radiation Control Program, obtained funding from the U.S. Department ofEnergy through EG and G, Idaho, Inc. to develop a low-level waste management strategy for the Commonwealth. The Working Group

S. R. Bander; M. E. Goldstein

1983-01-01

249

Commercial low-level radioactive waste disposal in the US  

SciTech Connect

Why are 11 states attempting to develop new low-level radioactive waste disposal facilities? Why is only on disposal facility accepting waste nationally? What is the future of waste disposal? These questions are representative of those being asked throughout the country. This paper attempts to answer these questions in terms of where we are, how we got there, and where we might be going.

Smith, P.

1995-10-01

250

Siting a radioactive waste facility; A pathways analysis case study  

Microsoft Academic Search

A radioactive waste disposal facility was proposed to be sited in Oregon. The waste being considered contained 250 pCi\\/g of uranium consisting of U-234, U-235, U-236 and U-238 isotopes. No Ra-226 or Th-230 were specified to be present in the waste. As part of the siting effort, the proposed facility had to be qualified with regard to meeting requirements for

G. A. Holton; K. R. Meyer; H. R. Meyer

1987-01-01

251

Greater-confinement disposal of low-level radioactive wastes  

Microsoft Academic Search

Low-level radioactive wastes include a broad spectrum of wastes that have different radionuclide concentrations, half-lives, and physical and chemical properties. Standard shallow-land burial practice can provide adequate protection of public health and safety for most low-level wastes, but a small volume fraction (about 1%) containing most of the activity inventory (approx.90%) requires specific measures known as ''greater-confinement disposal'' (GCD). Different

L. E. Trevorrow; T. L. Gilbert; C. Luner; P. A. Merry-Libby; N. K. Meshkov; C. Yu

1985-01-01

252

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

SciTech Connect

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

Dominick, J

2008-12-18

253

Radioactive waste management information for 1993 and record-to-date  

SciTech Connect

This document presents detailed data, bar graphs, and pie charts on volume, radioactivity, isotopic identity, origin, and decay status of radioactive waste for the calendar year 1993. It also summarizes the radioactive waste data records compiled from 1952 to present for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Radioactive Waste Management Information System.

Taylor, K.A.

1994-07-01

254

Radioactive waste management information for 1996 and record-to-date  

SciTech Connect

This document presents detailed data, bar graphs, and pie charts on volume, radioactivity, isotopic identity, origin, and status of radioactive waste for calendar year 1996. It also summarizes the radioactive waste data records compiled from 1952 to present for the Idaho National Engineering and Environmental Laboratory (INEEL). The data presented are from the INEEL Radioactive Waste Management Information System.

French, D.L.; Lisee, D.J.; Taylor, K.A.

1997-07-01

255

A methodology for evaluating the toxicity of radioactive waste and its application to the radioactive waste generated in Pennsylvania  

SciTech Connect

Communicating with the public on the risks of low-level radioactive waste disposal is difficult due to the lack of comparisons that are understandable to the public. This paper presents a methodology for analyzing the intrinsic toxicity of radionuclides in waste and comparing it to that for soil or other wastes that may contain naturally-occurring radionuclides. The intrinsic toxicity of each radionuclide is normalized by dividing its specific activity in the waste by an appropriate ingestion risk standard, such as the U.S. EPA proposed drinking water limits. To illustrate the usefulness of this method, it was used to analyze Pennsylvania`s commercial low-level radioactive waste inventory. The results are presented along with an indication of the usefulness of this method for screening purposes to analyze and identify problematic constituents in various waste streams. 15 refs., 11 figs.

Dornsife, W.P. [Pennsylvania Bureau of Radiation Protection, Harrisburg, PA (United States)

1995-08-01

256

Remote ignitability analysis of high-level radioactive waste  

SciTech Connect

The Idaho Chemical Processing Plant (ICPP), was used to reprocess nuclear fuel from government owned reactors to recover the unused uranium-235. These processes generated highly radioactive liquid wastes which are stored in large underground tanks prior to being calcined into a granular solid. The Resource Conservation and Recovery Act (RCRA) and state/federal clean air statutes require waste characterization of these high level radioactive wastes for regulatory permitting and waste treatment purposes. The determination of the characteristic of ignitability is part of the required analyses prior to calcination and waste treatment. To perform this analysis in a radiologically safe manner, a remoted instrument was needed. The remote ignitability Method and Instrument will meet the 60 deg. C. requirement as prescribed for the ignitability in method 1020 of SW-846. The method for remote use will be equivalent to method 1020 of SW-846.

Lundholm, C.W.; Morgan, J.M.; Shurtliff, R.M.; Trejo, L.E.

1992-09-01

257

Process for the encapsulation and stabilization of radioactive, hazardous and mixed wastes  

DOEpatents

The present invention provides a method for encapsulating and stabilizing radioactive, hazardous and mixed wastes in a modified sulfur cement composition. The waste may be incinerator fly ash or bottom ash including radioactive contaminants, toxic metal salts and other wastes commonly found in refuse. The process may use glass fibers mixed into the composition to improve the tensile strength and a low concentration of anhydrous sodium sulfide to reduce toxic metal solubility. The present invention preferably includes a method for encapsulating radioactive, hazardous and mixed wastes by combining substantially anhydrous wastes, molten modified sulfur cement, preferably glass fibers, as well as anhydrous sodium sulfide or calcium hydroxide or sodium hydroxide in a heated double-planetary orbital mixer. The modified sulfur cement is preheated to about 135.degree..+-.5.degree. C., then the remaining substantially dry components are added and mixed to homogeneity. The homogeneous molten mixture is poured or extruded into a suitable mold. The mold is allowed to cool, while the mixture hardens, thereby immobilizing and encapsulating the contaminants present in the ash.

Colombo, Peter (Patchogue, NY); Kalb, Paul D. (Wading River, NY); Heiser, III, John H. (Bayport, NY)

1997-11-14

258

Radioactive waste disposal in simulated peat bog repositories  

SciTech Connect

The Low Level Radioactive Waste Policy Act of 1980 and the Low Level Radioactive Waste Policy Amendments Act of 1985 have required state governments to be responsible for providing low-level waste (LLW) disposal facilities in their respective areas. Questions are (a) is the technology sufficiently advanced to ensure that radioactive wastes can be stored for 300 to 1000 yr without entering into any uncontrolled area. (b) since actual experience does not exist for nuclear waste disposal over this time period, can the mathematical models developed be tested and verified using unequivocal data. (c) how can the public perception of the problem be addressed and the potential risk assessment of the hazards be communicated. To address the technical problems of nuclear waste disposal in the acid precipitation regions of the Northern Hemisphere, a project was initiated in 1984 to evaluate an alternative method of nuclear waste disposal that may not rely completely on engineered barriers to protect the public. Certain natural biogeochemical systems have been retaining deposited materials since the last Ice Age (12,000 to 15,000 yr). It is the authors belief that the biogeochemical system of wetlands and peat bogs may provide an example of an analogue for a nuclear waste repository system that can be tested and verified over a sufficient time period, at least for the LLW disposal problem.

Schell, W.R.; Massey, C.D.

1987-01-01

259

Science and technology for disposal of radioactive tank wastes  

SciTech Connect

One of the legacies of the Cold War is a huge stockpile of radioactive wastes generated by over 40 years of nuclear weapons production. Safe treatment and disposal of these wastes, together with the associated problems of facility decommissioning and site clean-up, represents one of the largest and most complex environmental challenges of the present-day. Amongst these nuclear wastes is a wide variety of radioactive liquids, sludges and slurries created as waste by-products from the processing of spent nuclear fuel to extract enriched uranium and plutonium for bomb manufacture. Their liquid state, high level of radioactivity and the fact that they generally are stored in underground tanks (hence the term tank wastes), many of which are known to be leaking, makes their treatment and disposal all the more urgent. Despite its name, the book does not really discuss in any detail the final disposal of tank wastes. Of all the papers, only a few explicitly mention disposal of the wastes to a geological repository. The vast majority of the papers actually discuss pre-disposal treatment and solidification issues. What happens to the waste after they have been processed, minimized and solidified is an equally important issue and one that the book sadly fails to address.

Schulz, W.W.; Lombardo, N.J. [eds.

1998-07-01

260

Radioactive material inventory control at a waste characterization facility  

SciTech Connect

Due to the recent introduction of more stringent Department of Energy (DOE) regulations and requirements pertaining to nuclear and criticality safety, the control of radioactive material inventory has emerged as an important facet of operations at DOE nuclear facilities. In order to comply with nuclear safety regulations and nuclear criticality requirements, radioactive material inventories at each nuclear facility have to be maintained below limits specified for the facility in its safety authorization basis documentation. Exceeding these radioactive material limits constitutes a breach of the facility`s nuclear and criticality safety envelope and could potentially result in an accident, cause a shut-down of the facility, and bring about imminent regulatory repercussions. The practice of maintaining control of radioactive material, especially sealed and unsealed sources, is commonplace and widely implemented; however, the requirement to track the entire radioactivity inventory at each nuclear facility for the purpose of ensuring nuclear safety is a new development. To meet the new requirements, the Applied Radiation Measurements Department at Oak Ridge National Laboratory (ORNL) has developed an information system, called the {open_quotes}Radioactive Material Inventory System{close_quotes} (RMIS), to track the radioactive material inventory at an ORNL facility, the Waste Examination and Assay Facility (WEAF). The operations at WEAF, which revolve around the nondestructive assay and nondestructive examination of waste and related research and development activities, results in an ever-changing radioactive material inventory. Waste packages and radioactive sources are constantly being brought in or taken out of the facility; hence, use of the RMIS is necessary to ensure that the radioactive material inventory limits are not exceeded.

Yong, L.K.; Chapman, J.A.; Schultz, F.J. [Oak Ridge National Laboratory, TN (United States)

1996-06-01

261

Radiation safety requirements for radioactive waste management in the framework of a quality management system  

Microsoft Academic Search

The Center for Radiation Protection and Hygiene (CPHR) is the institution responsible for the management of radioactive wastes generated from nuclear applications in medicine, industry and research in Cuba. Radioactive Waste Management Service is provided at a national level and it includes the collection and transportation of radioactive wastes to the Centralized Waste Management Facilities, where they are characterized, segregated,

M. M. Salgado; J. C. Benitez; R. Pernas; N. Gonzalez

2007-01-01

262

Field survey of the shallow land low-level radioactive waste burial site near Beatty, Nevada  

Microsoft Academic Search

High resolution gamma-ray spectrometry was used to determine radioactivity levels in surface soil at the site as part of an effort to confirm the boundaries of existing waste burial trenches, locate any additional radioactive wastes beyond the established burial area, characterize the distribution of radionuclides around the waste burial site, and determine whether movement of radioactivity from unearthed waste drums

H. L. Nielson; N. A. Wogman; L. J. Kirby

1981-01-01

263

Site selection for low and intermediate level radioactive waste disposal facility in Korea  

Microsoft Academic Search

The radioactive waste can be classified into low and intermediate level waste (LILW), spent fuel (SF) and high level waste according to the level of the emitted radioactivity in Korea.Currently radioactive waste is temporarily stored in the four nuclear power plant sites, where the LILW and SF are expected to be saturated from 2008 and 2016, respectively. Therefore the construction

Si-Tae Yun

2008-01-01

264

SOLID RADIOACTIVE WASTE TREATMENT INITIATIVES FOR NUCLEAR SUBMARINE DECOMMISSIONING WASTES UNDER THE AMEC PROGRAM  

Microsoft Academic Search

The volume of solid radioactive waste (SRW) generated from decommissioning Russia's nuclear submarines far exceeds existing SRW management capabilities of the Russian Northern Fleet. Inadequate management of this waste poses a substantial threat for pollution of the fragile Arctic environment. The Arctic Military Environmental Cooperation (AMEC) Project 1.3 has assessed waste treatment options, selected technologies, and is now designing and

Andrew Griffith

2001-01-01

265

Radioactive liquid waste generation goals at the ICPP  

SciTech Connect

Processes at ICPP generating hazardous radioactive liquid wastes (which are sent to the tank farm) include NWCF, PEW evaporator, LET&D, tank farm, fuel storage operations, etc. In May 1994, the INEL Radioactive Liquid Waste Management Plan was issued but not implemented. Waste generation goals have been reviewed and updated in this report (details are given in appendix). A meeting was held to determine the new waste generation goals and best approach to reaching them. Waste streams were individually analyzed in this meeting and several adjustments made both during the meeting and following the meeting. The information was adjusted and modeling completed to determine the waste reduction achieved (spreadsheets are included in appendix). Results of this update indicate that there has been a significant reduction in the waste generation goals from 2 years ago. If the updated baseline goals are met, a 35% waste reduction will be achieved; this coupled with increased calcination rate, will enable the waste in the tank farm to be processed by 2012; however a program is needed to ensure these waste goals are met. A monitoring and reporting function in conjunction with company level incentives will fill this need; a logic diagram of this monitoring program is given.

Tripp, J.L.

1996-07-01

266

Stirring system for radioactive waste water storage tank  

SciTech Connect

A stirring system for 100-m[sup 3] radioactive liquid waste tanks was constructed to unify radioactive concentrations in the tank. The stirring system is effective in certifying that the radioactive concentrations in the tanks are less than the legal limits before they are drained away as waste liquid. This system is composed of discharge units, pipe lines, and a controller. The performance of the system was assessed by comparing the calculated red ink and [sup 32]P concentrations with those monitored at six locations in the tanks. The concentration reached equilibrium after stirring 60 o 120 min with discharge units equipped with six fixed openings configured in differing directions. Residual chlorine in city water used for dilution occasionally bleached the red ink and reduced its concentration. The adsorption of [sup 32]P by slime on the walls of the tanks storing actual waste water lowered the equilibrium concentration.

Ogata, Yoshimune; Nishizawa, Kunihide (Nagoya Univ. (Japan). Radioisotope Research Center)

1999-07-01

267

Commission operation. National Low-Level Radioactive Waste Management Program  

NASA Astrophysics Data System (ADS)

Since Congress enacted the Low-Level Radioactive Waste Policy Act, the states have prepared to meet their responsibilities for management of low-level radioactive waste by entering into regional compacts. This option document is intended to provide a framework for the operation of a compact commission formed as the governing body of a low-level radioactive waste compact. The document is designed to be easily modified to meet the needs of various regional compacts. The ideas and format presented were taken in general from the Federal Administrative procedures Act, various state administrative procedures, and the state regulatory agencies' rules of procedure. Requirements of filing, time frames, and standard language are written from a legal perspective.

1984-09-01

268

[Problems of safety regulation under radioactive waste management in Russia].  

PubMed

Analysis of the requirements of Federal Law N 190 "About radioactive waste management and incorporation of changes into some legislative acts of the Russian Federation", as well as normative-legislative documents actual and planned to be published related to provision of radiation protection of the workers and the public have been done. Problems of safety regulation raised due to different approaches of Rospotrebnadzor, FMBA of Russia, Rostekhnadzor and Minprirody with respect to classification and categorization of the radioactive wastes, disposal, exemption from regulatory control, etc. have been discussed in the paper. Proposals regarding improvement of the system of safety regulation under radioactive waste management and of cooperation of various regulatory bodies have been formulated. PMID:23210184

Monastyrskaia, S G; Kochetkov, O A; Barchukov, V G; Kuznetsova, L I

2012-01-01

269

Proceedings: Radioactive Low Level Waste Management Workshop  

SciTech Connect

This report presents the proceedings of an EPRI workshop on low level waste management. The workshop was the fifth in a series to aid utility personnel in assessing technologies for decommissioning nuclear power plants. This workshop focused on specific aspects of low level waste management as they relate to nuclear plant decommissioning. Workshop information will help utilities assess benefits of waste management, select technologies for their individual projects, and reduce decommissioning costs.

None

2000-05-01

270

Long-term Stewardship of Mixed Wastes: Passive Reactive Barriers for Simultaneous In Situ Remediation of Chlorinated Solvent, Heavy Metal and Radioactive  

SciTech Connect

This project report addresses one part of a 3-way collaboration between researchers (Drs. Robin Gerlach and Al Cunningham) at Montana State University's (MSU's) Center for Biofilm Engineering (CBE), (Dr. Brent Peyton at) the WSU/NSF IGERT Center for Multiphase Environmental Research (CMER) at Washington State University (WSU), and (Drs. William Apel and Frank Roberto at) the Biotechnology Department at the INEEL. Each part of this project is funded under a different contract with the Science Division of the US Department of Energy. The project is designed to evaluate the possibility to develop a subsurface remediation technology for mixed wastes at Department of Energy sites using a group of common soil bacteria of the genus Cellulomonas. We are seeking to gain a better understanding of microbial transformation of chromium, uranium, and carbon tetrachloride by Cellulomonas spp. in simulated subsurface environments.

Gerlach, Robin

2005-06-01

271

Advanced radioactive waste compaction techniques: Final report  

SciTech Connect

The purpose of this test program is to provide definitive information on the volume reduction capabilities of conventional compactors used in the nuclear industry for the treatment of dry active waste and the effects of preshredding on compaction. The test program presents comprehensive data on compacted densities of dry active waste collected at five facilities generating this waste and using conventional compactors. Waste materials presently classified as ''non-compactable'' which would lend themselves to preshredding and compaction are identified. An ALARA evaluation of shredding operations and an economic evaluation of preshredding prior to compaction are also presented. 32 figs., 72 tabs.

Volodzko, M.; McGrath, R.N.; Kinsman, J.F.; Palo, W.J.

1988-08-01

272

Radioactive waste management in the former USSR. Volume 3  

SciTech Connect

Radioactive waste materials--and the methods being used to treat, process, store, transport, and dispose of them--have come under increased scrutiny over last decade, both nationally and internationally. Nuclear waste practices in the former Soviet Union, arguably the world`s largest nuclear waste management system, are of obvious interest and may affect practices in other countries. In addition, poor waste management practices are causing increasing technical, political, and economic problems for the Soviet Union, and this will undoubtedly influence future strategies. this report was prepared as part of a continuing effort to gain a better understanding of the radioactive waste management program in the former Soviet Union. the scope of this study covers all publicly known radioactive waste management activities in the former Soviet Union as of April 1992, and is based on a review of a wide variety of literature sources, including documents, meeting presentations, and data base searches of worldwide press releases. The study focuses primarily on nuclear waste management activities in the former Soviet Union, but relevant background information on nuclear reactors is also provided in appendixes.

Bradley, D.J.

1992-06-01

273

Apparatus for the processing of solid mixed waste containing radioactive and hazardous materials  

DOEpatents

Apparatus for the continuous heating and melting of a solid mixed waste bearing radioactive and hazardous materials to form separate metallic, slag and gaseous phases for producing compact forms of the waste material to facilitate disposal includes a copper split water-cooled (cold) crucible as a reaction vessel for receiving the waste material. The waste material is heated by means of the combination oaf plasma torch directed into the open upper portion of the cold crucible and an electromagnetic flux produced by induction coils disposed about the crucible which is transparent to electromagnetic fields. A metallic phase of the waste material is formed in a lower portion of the crucible and is removed in the form of a compact ingot suitable for recycling and further processing. A glass-like, non-metallic slag phase containing radioactive elements is also formed in the crucible and flows out of the open upper portion of the crucible into a slag ingot mold for disposal. The decomposition products of the organic and toxic materials are incinerated and converted to environmentally safe gases in the melter.

Gotovchikov, Vitaly T. (Moscow, RU); Ivanov, Alexander V. (Moscow, RU); Filippov, Eugene A. (Moscow, RU)

1999-03-16

274

10 CFR 72.108 - Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste...  

Code of Federal Regulations, 2010 CFR

... Spent fuel, high-level radioactive waste, or reactor-related greater...NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER... Spent fuel, high-level radioactive waste, or reactor-related...

2009-01-01

275

FINAL REPORT. POLYOXOMETALATES FOR RADIOACTIVE WASTE TREATMENT  

EPA Science Inventory

The research was directed primarily towards the use of polyoxometalate complexes for separation of lanthanide, actinide, and technetium species from aqueous waste solutions, such as the Hanford Tank Wastes. Selective binding of these species responsible for much of the high level...

276

Uncertainty associated with radioactive waste chacteristics  

Microsoft Academic Search

To clarify uncertainty in predictions of the quantity, radionuclide inventory and activity of waste from the Krsko nuclear power plant, and to illuminate its role in related policy-making, we made a scenario analysis in order to find out the variation in waste characteristics if the plant operates five years shorter or longer than anticipated, or if it uses fuel of

Branko Kontic; Matjaz Ravnik; Peter Stegnar; Burton C. Kross

2000-01-01

277

Advanced Test Reactor Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables.  

National Technical Information Service (NTIS)

U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, a...

B. Bennett L. Harvego

2011-01-01

278

Research and Education Campus Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables.  

National Technical Information Service (NTIS)

U.S. Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, a...

B. Bennett L. Harvego

2011-01-01

279

Materials and Security Consolidation Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables.  

National Technical Information Service (NTIS)

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and ac...

2011-01-01

280

Central Facilities Area Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables.  

National Technical Information Service (NTIS)

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and ac...

B. Bennett L. Harvego

2011-01-01

281

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables.  

National Technical Information Service (NTIS)

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and ac...

2011-01-01

282

The Defense Waste Processing Facility: Two Years of Radioactive Operation  

SciTech Connect

The Defense Waste Processing Facility (DWPF) at the Savannah River Site in Aiken, SC is currently immobilizing high level radioactive sludge waste in borosilicate glass. The DWPF began vitrification of radioactive waste in May, 1996. Prior to that time, an extensive startup test program was completed with simulated waste. The DWPF is a first of its kind facility. The experience gained and data collected during the startup program and early years of operation can provide valuable information to other similar facilities. This experience involves many areas such as process enhancements, analytical improvements, glass pouring issues, and documentation/data collection and tracking. A summary of this experience and the results of the first two years of operation will be presented.

Marra, S.L. [Westinghouse Savannah River Company, AIKEN, SC (United States); Gee, J.T.; Sproull, J.F.

1998-05-01

283

Review of the radioactive waste management system in Nigeria.  

PubMed

The management of radioactive waste in Nigeria from early 1960 to date is reviewed. As in many developing countries, waste management in Nigeria has been shown to be ineffective. The factors that are responsible for this ineffectiveness are identified and discussed. The steps being taken by and the opportunities available to the newly established Nigerian Nuclear Regulatory Authority towards addressing this problem of ineffectiveness are discussed. The efforts of this newly set up body towards managing the resultant radioactive wastes that will be generated during the use of a reactor and an accelerator that will soon be commissioned in Nigeria are also mentioned. Likely ways of further addressing the problems militating against waste management in developing countries are suggested. PMID:12729418

Ogundare, F O

2003-03-01

284

Nuclear safety in handling radioactive wastes containing fissile materials  

Microsoft Academic Search

Nuclear safety in disposal and reprocessing of solid and liquid radioactive wastes produced during the production of nuclear\\u000a reactor fuel elements was investigated. The results of this work made it possible to determine the parameters which must be\\u000a limited in handling wastes in order to avoid the occurrence of a self-maintaining fission chain reaction. The numerical values\\u000a of these parameters

V. S. Vnukov; O. V. Sichkaruk; L. I. Chkuaseli

2000-01-01

285

Method of encapsulating solid radioactive waste material for storage  

DOEpatents

High-level radioactive wastes are encapsulated in vitreous carbon for long-term storage by mixing the wastes as finely divided solids with a suitable resin, formed into an appropriate shape and cured. The cured resin is carbonized by heating under a vacuum to form vitreous carbon. The vitreous carbon shapes may be further protected for storage by encasement in a canister containing a low melting temperature matrix material such as aluminum to increase impact resistance and improve heat dissipation.

Bunnell, Lee Roy (Kennewick, WA); Bates, J. Lambert (Richland, WA)

1976-01-01

286

Leveraging Radioactive Waste Disposal at WIPP for Science  

Microsoft Academic Search

Salt mines are radiologically much quieter than other underground environments because of ultra-low concentrations of natural radionuclides (U, Th, and K) in the host rock; therefore, the Waste Isolation Pilot Plant (WIPP), a government-owned, 655m deep geologic repository that disposes of radioactive waste in thick salt near Carlsbad, New Mexico, has for the last 15 years hosted highly radiation-sensitive experiments.

N. T. Rempe

2008-01-01

287

Modeling of radioactive transport for decommissioned nuclear reactor waste  

Microsoft Academic Search

Technological advances have safeguarded the quality of our lives, but many of these developments have led to improper management and uncontrolled disposal of hazardous and radioactive wastes. The introduction of these waste by-products into our complex and interconnected natural environment has resulted in the migration of contaminants into life-sustaining resources: air, water, and land. The U.S. Department of Energy (DOE)

W. J. Martin; G. Whelan

1994-01-01

288

Risk analysis of radioactive waste management systems in Germany  

Microsoft Academic Search

Within the scope of a system study, ''Radioactive wastes in the Federal Republic of Germany,'' performed from 1974 through 1976, the questions of risk assessment were investigated. A risk analysis of a high-level waste (HLW) management system was performed. The results of the HLW tank storage are that the risk expectation value is 700 nJ\\/kg x RBE (7 x 10⁻⁵

Wingender

1978-01-01

289

Control of high level radioactive waste-glass melters  

Microsoft Academic Search

A necessary step in Defense Waste Processing Facility (DWPF) melter feed preparation for the immobilization of High Level Radioactive Waste (HLW) is reduction of Hg(II) to Hg(0), permitting steam stripping of the Hg. Denitrition and associated NOx evolution is a secondary effect of the use of formic acid as the mercury-reducing agent. Under certain conditions the presence of transition or

D. F. Bickford; C. J. Coleman; C. L. W. Hsu; R. E. Eibling

1990-01-01

290

Novel Solvent for the Simultaneous recovery of Radioactive Nuclides from Liquid Radioactive Wastes  

DOEpatents

The present invention relates to solvents, and methods, for selectively extracting and recovering radionuclides, especially cesium and strontium, rare earths and actinides from liquid radioactive wastes. More specifically, the invention relates to extracting agent solvent compositions comprising complex organoboron compounds, substituted polyethylene glycols, and neutral organophosphorus compounds in a diluent. The preferred solvent comprises a chlorinated cobalt dicarbollide, diphenyl-dibutylmethylenecarbamoylphosphine oxide, PEG-400, and a diluent of phenylpolyfluoroalkyl sulfone. The invention also provides a method of using the invention extracting agents to recover cesium, strontium, rare earths and actinides from liquid radioactive waste.

Romanovskiy, Valeriy Nicholiavich; Smirnov, Lgor V.; Babain, Vasiliy A.; Todd, Terry A.; Brewer, Ken N.

1999-10-07

291

LLNL radioactive waste management plan as per DOE Order 5820. 2  

SciTech Connect

The following aspects of LLNL's radioactive waste management plan are discussed: program administration; description of waste generating processes; radioactive waste collection, treatment, and disposal; sanitary waste management; site 300 operations; schedules and major milestones for waste management activities; and environmental monitoring programs (sampling and analysis).

Not Available

1984-12-10

292

CONCEPTUAL DATA MODELING OF THE INTEGRATED DATABASE FOR THE RADIOACTIVE WASTE MANAGEMENT  

SciTech Connect

A study of a database system that can manage radioactive waste collectively on a network has been carried out. A conceptual data modeling that is based on the theory of information engineering (IE), which is the first step of the whole database development, has been studied to manage effectively information and data related to radioactive waste. In order to establish the scope of the database, user requirements and system configuration for radioactive waste management were analyzed. The major information extracted from user requirements are solid waste, liquid waste, gaseous waste, and waste related to spent fuel. The radioactive waste management system is planning to share information with associated companies.

Park, H.S; Shon, J.S; Kim, K.J; Park, J.H; Hong, K.P; Park, S.H

2003-02-27

293

Design and Construction of Deinococcus radiodurans for Biodegradation of Organic Toxins at Radioactive DOE Waste Sites  

SciTech Connect

Immense volumes of radioactive waste, generated from nuclear weapons production during the Cold War, were disposed directly to the ground. The current expense of remediating these polluted sites is driving the development of alternative remediation strategies using microorganisms. The bacterium Deinococcus radiodurans is the most radiation resistant organism known and can grow in highly irradiating (>60 Gray/h) environments (1). Numerous microorganisms (e.g., Pseudomonas sp.) have been described, and studied in detail, for their ability to transform and degrade a variety of organic pollutants (e.g., toluene), present at many radioactive DOE waste sites. Detoxification of the organic toxins at these sites is an important goal in remediating or stabilizing contaminated sites as well as preventing their further dissemination. The aim of this project is to engineer strains of D. radiodurans that are capable of degrading organic/aromatic hydrocarbons present in radioactive mixed waste sites--sites that contain mixtures of toxic organic compounds, radionuclides and heavy metals. Conventional bioremediating organisms are unable to survive at many of these sites because of their sensitivity to radiation. Generally, microorganisms are sensitive to the damaging effects of ionizing radiation, and most of the bacteria currently being studied as candidates for bioremediation are no exception. For example, Pseudomonas sp. is very sensitive to radiation (more sensitive than E. coli) and is not suited to remediate radioactive wastes. Therefore, radiation resistant microorganisms that can remediate toxic organic compounds need to be found in nature or engineered in the laboratory to address this problem.

Daly, Michael J.; Fredrickson, James K.; Wackett, Lawrence P.

1999-06-01

294

Metal, mineral waste processing and secondary recovery  

SciTech Connect

Approximately 40 million tons of precious metals chemical wastes are produced in the United States every year. An estimated five percent of these wastes are being reused/recycled to recover the precious and critical metals they contain. The rest of these chemical wastes are disposed of by the methods incineration, dumping at sea and dumping on land. In this paper, an attempt is made to review the research work published during 1985-1986 on metal, mineral waste processing, secondary recovery and safe disposal.

Reddy, R.G.

1987-04-01

295

Results of field testing of radioactive waste forms using lysimeters  

SciTech Connect

The Field Lysimeter Investigation: Low-Level Waste Data Base Development Program is obtaining informaiton on the performance of radioactive waste in a disposal environment. Waste forms fabricated using ion-exchange resins from EPICOR-II prefilters employed in the cleanup of the Three Mile Island (TMI) Nuclear Power Station are being tested to develop a low-level waste data base and to obtain information on survivability of waste forms in a disposal environment. In this paper, radionuclide releases from waste forms in the first six years of sampling are presented and discussed. Application of lysimeter data to use in performance assessment models is presented. Initial results from use of data in a performance assessment model are discussed.

McConnell, J.W., Jr.; Rogers, R.D. [Idaho National Engineering Lab., Idaho Falls, ID (United States); Jastrow, J.D. [Argonne National Lab., IL (United States); Wickliff, D.S. [Oak Ridge National Lab., TN (United States)

1992-08-01

296

Results of field testing of radioactive waste forms using lysimeters  

SciTech Connect

The Field Lysimeter Investigation: Low-Level Waste Data Base Development Program is obtaining informaiton on the performance of radioactive waste in a disposal environment. Waste forms fabricated using ion-exchange resins from EPICOR-II prefilters employed in the cleanup of the Three Mile Island (TMI) Nuclear Power Station are being tested to develop a low-level waste data base and to obtain information on survivability of waste forms in a disposal environment. In this paper, radionuclide releases from waste forms in the first six years of sampling are presented and discussed. Application of lysimeter data to use in performance assessment models is presented. Initial results from use of data in a performance assessment model are discussed.

McConnell, J.W., Jr.; Rogers, R.D. (Idaho National Engineering Lab., Idaho Falls, ID (United States)); Jastrow, J.D. (Argonne National Lab., IL (United States)); Wickliff, D.S. (Oak Ridge National Lab., TN (United States))

1992-01-01

297

Low-level radioactive waste technology: a selected, annotated bibliography  

SciTech Connect

This annotated bibliography of 447 references contains scientific, technical, economic, and regulatory information relevant to low-level radioactive waste technology. The bibliography focuses on environmental transport, disposal site, and waste treatment studies. The publication covers both domestic and foreign literature for the period 1952 to 1979. Major chapters selected are Chemical and Physical Aspects; Container Design and Performance; Disposal Site; Environmental Transport; General Studies and Reviews; Geology, Hydrology and Site Resources; Regulatory and Economic Aspects; Transportation Technology; Waste Production; and Waste Treatment. Specialized data fields have been incorporated into the data file to improve the ease and accuracy of locating pertinent references. Specific radionuclides for which data are presented are listed in the Measured Radionuclides field, and specific parameters which affect the migration of these radionuclides are presented in the Measured Parameters field. In addition, each document referenced in this bibliography has been assigned a relevance number to facilitate sorting the documents according to their pertinence to low-level radioactive waste technology. The documents are rated 1, 2, 3, or 4, with 1 indicating direct applicability to low-level radioactive waste technology and 4 indicating that a considerable amount of interpretation is required for the information presented to be applied. The references within each chapter are arranged alphabetically by leading author, corporate affiliation, or title of the document. Indexes are provide for (1) author(s), (2) keywords, (3) subject category, (4) title, (5) geographic location, (6) measured parameters, (7) measured radionuclides, and (8) publication description.

Fore, C.S.; Vaughan, N.D.; Hyder, L.K.

1980-10-01

298

75 FR 74104 - Request for a License To Export Radioactive Waste  

Federal Register 2010, 2011, 2012, 2013

...NUCLEAR REGULATORY COMMISSION Request for a License To Export Radioactive Waste Pursuant to 10 CFR 110.70 (b) ``Public Notice...EnergySolutions, August 27, Radioactive waste Not to exceed Return to two Germany. 2010,...

2010-11-30

299

75 FR 74107 - Request for a License To Import Radioactive Waste  

Federal Register 2010, 2011, 2012, 2013

...NUCLEAR REGULATORY COMMISSION Request for a License To Import Radioactive Waste Pursuant to 10 CFR 110.70(b) ``Public Notice...EnergySolutions, August 27, Radioactive waste 1,000 tons Incineration for Germany. 2010,...

2010-11-30

300

77 FR 20078 - Request for a License To Import Radioactive Waste  

Federal Register 2010, 2011, 2012, 2013

...NUCLEAR REGULATORY COMMISSION Request for a License To Import Radioactive Waste Pursuant to 10 CFR 110.70 (b) ``Public Notice...Perma-Fix Northwest Richland, Radioactive waste Up to 500 tons of Thermal Mexico. Inc.,...

2012-04-03

301

Study on the Policy for the Radioactive Waste Treatment and Disposal.  

National Technical Information Service (NTIS)

In this report, the establishment of the policy for the safe long-term isolation of radioactive wastes from human environment is studied in three scopes: radioactive waste management in the radioisotope application industries; foundation plan for the Radi...

H. H. Park I. S. Suh H. Y. Kim Y. H. Cho P. I. Juhn

1985-01-01

302

Remote automated material handling of radioactive waste containers  

SciTech Connect

To enhance personnel safety, improve productivity, and reduce costs, the design team incorporated a remote, automated stacker/retriever, automatic inspection, and automated guidance vehicle for material handling at the Enhanced Radioactive and Mixed Waste Storage Facility - Phase V (Phase V Storage Facility) on the Hanford Site in south-central Washington State. The Phase V Storage Facility, scheduled to begin operation in mid-1997, is the first low-cost facility of its kind to use this technology for handling drums. Since 1970, the Hanford Site`s suspect transuranic (TRU) wastes and, more recently, mixed wastes (both low-level and TRU) have been accumulating in storage awaiting treatment and disposal. Currently, the Hanford Site is only capable of onsite disposal of radioactive low-level waste (LLW). Nonradioactive hazardous wastes must be shipped off site for treatment. The Waste Receiving and Processing (WRAP) facilities will provide the primary treatment capability for solid-waste storage at the Hanford Site. The Phase V Storage Facility, which accommodates 27,000 drum equivalents of contact-handled waste, will provide the following critical functions for the efficient operation of the WRAP facilities: (1) Shipping/Receiving; (2) Head Space Gas Sampling; (3) Inventory Control; (4) Storage; (5) Automated/Manual Material Handling.

Greager, T.M.

1994-09-01

303

Natural Safety Storage of Radioactive Waste  

Microsoft Academic Search

The public acceptance of an increase program of nuclear energy requires an openly and straight forward discussion, in an understandable\\u000a way of the main issues against nuclear energy as: nuclear accidents, proliferation of nuclear weapons and safety storage of\\u000a nuclear waste. Regarding this last issue, there are doubts concerning stability of geological sites to storage nuclear waste\\u000a as well as

Miguel Balczar-Garca; Jess Hernn Flores-Ruiz; Pablo Pea; Arturo Lpez

304

Fusion fuel cycle solid radioactive wastes  

Microsoft Academic Search

Eight conceptual deuterium-tritium fueled fusion power plant designs have been analyzed to identify waste sources, materials and quantities. All plant designs include the entire D-T fuel cycle within each plant. Wastes identified include radiation-damaged structural, moderating, and fertile materials; getter materials for removing corrosion products and other impurities from coolants; absorbents for removing tritium from ventilation air; getter materials for

B. F. Gore; J. D. Kaser; T. J. Kabele

1978-01-01

305

78 FR 9746 - Request To Amend a License To Export Radioactive Waste  

Federal Register 2010, 2011, 2012, 2013

...Request To Amend a License To Export Radioactive Waste Pursuant to 10 CFR 110.70...Diversified Scientific Class A radioactive Up to a maximum Return of non- Canada...Class A appropriate varying combinations radioactive disposition. Amend which was...

2013-02-11

306

Radioactive and mixed waste - risk as a basis for waste classification. Symposium proceedings No. 2  

SciTech Connect

The management of risks from radioactive and chemical materials has been a major environmental concern in the United states for the past two or three decades. Risk management of these materials encompasses the remediation of past disposal practices as well as development of appropriate strategies and controls for current and future operations. This symposium is concerned primarily with low-level radioactive wastes and mixed wastes. Individual reports were processed separately for the Department of Energy databases.

NONE

1995-06-21

307

Summary of radioactive solid waste received in the 200 Areas during calendar year 1995  

SciTech Connect

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1995. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, liquid waste data are not included in this document. This annual report provides a summary of the radioactive solid waste received in the both the 200-East and 200-West Areas during the calendar year 1995.

Hladek, K.L.

1996-06-06

308

Materials and Fuels Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Fuels Complex facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-09-01

309

Materials and Security Consolidation Complex Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Materials and Security Consolidation Center facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facility-specific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Not Listed

2011-09-01

310

Central Facilities Area Facilities Radioactive Waste Management Basis and DOE Manual 435.1-1 Compliance Tables  

SciTech Connect

Department of Energy Order 435.1, 'Radioactive Waste Management,' along with its associated manual and guidance, requires development and maintenance of a radioactive waste management basis for each radioactive waste management facility, operation, and activity. This document presents a radioactive waste management basis for Idaho National Laboratory's Central Facilities Area facilities that manage radioactive waste. The radioactive waste management basis for a facility comprises existing laboratory-wide and facilityspecific documents. Department of Energy Manual 435.1-1, 'Radioactive Waste Management Manual,' facility compliance tables also are presented for the facilities. The tables serve as a tool for developing the radioactive waste management basis.

Lisa Harvego; Brion Bennett

2011-11-01

311

High level radioactive waste management facility design criteria  

Microsoft Academic Search

This paper discusses the engineering systems for the structural design of the Defense Waste Processing Facility (DWPF) at the Savannah River Site (SRS). At the DWPF, high level radioactive liquids will be mixed with glass particles and heated in a melter. This molten glass will then be poured into stainless steel canisters where it will harden. This process will transform

N. A. Sheikh; S. R. Salaymeh

1993-01-01

312

Proceedings of the specialists' meeting on radioactive wastes management.  

National Technical Information Service (NTIS)

The specialist research meeting on radioactive waste management was held in the Research Reactor Institute, Kyoto University, on November 13 and 14, 1990. This meeting has been held annually in the last several years. The meeting has taken up the topics r...

K. Higashi K. Shimoura

1991-01-01

313

Proceedings: EPRI International Decommissioning and Radioactive Waste Workshop at Dounreay  

SciTech Connect

This report presents the proceedings of an EPRI international workshop on decommissioning and radioactive waste management. EPRI initiated this continuing workshop series to aid utility personnel in assessing the technologies utilized in the decommissioning of nuclear power plants and facilities. The information presented will help individual utilities assess the benefits of the various programs, including their potential to reduce decommissioning costs.

None

2003-01-01

314

Method of storing radioactive wastes using modified tobermorite  

DOEpatents

A new cation exchanger is a modified tobermorite containing aluminum isomorphously substituted for silicon and containing sodium or potassium. The exchanger is selective for lead, rubidium, cobalt and cadmium and is selective for cesium over calcium or sodium. The tobermorites are compatable with cement and are useful for the long-term fixation and storage of radioactive nuclear wastes.

Komarneni, Sridhar (State College, PA); Roy, Della M. (State College, PA)

1985-01-01

315

Radioactive Waste...The Problem and Some Possible Solutions  

ERIC Educational Resources Information Center

|Nuclear safety is a highly technical and controversial subject that has caused much heated debate and political concern. This article examines the problems involved in managing radioactive wastes and the techniques now used. Potential solutions are suggested and the need for international cooperation is stressed. (Author/MA)|

Olivier, Jean-Pierre

1977-01-01

316

Mathematical modeling of a radioactive waste disposal system  

Microsoft Academic Search

In order to establish the safety of a disposl system for high-level radioactive waste, the system must be shown to satisfy radiological safety criteria imposed by regulatory agencies. In Canada, for example, the regulatory policy includes a quantitative limit on radiological risk to an individual for a period of 10,000 years following disposal. Mathematical modeling of the performance of the

K. W. Dormuth

1992-01-01

317

Disposal of Radioactive Waste at Hanford Creates Problems  

ERIC Educational Resources Information Center

Radioactive storage tanks at the Hanford facility have developed leaks. The situation is presently considered safe, but serious. A report from the National Academy of Science has recommended that the wastes be converted to stable solids and stored at another site on the Hanford Reservation. (Author/MA)

Chemical and Engineering News, 1978

1978-01-01

318

Quantitative Assessment Personnel Training Efficiency in Management of Radioactive Waste  

SciTech Connect

This paper describes quantitative parameters of training efficiency for the personnel working in the area of radioactive waste management. We formulate the basis for the independent parameters of an integrated training process. It is shown that training efficiency can be described by a characteristic numerical figure, which is the generalized mark of the training efficiency. (authors)

Batyukhnova, O.G.; Dmitriev, S.A.; Puzanov, Y.V.; Semenova, I.V. [SUE SIA 'Radon', The 7-th Rostovsky Lane 2/14, Moscow, 119121 (Russian Federation); Ojovan, M.I. [Immobilisation Science Laboratory, University of Sheffield, Sir Robert Hadfield Building, Mappin Street, S1 3JD (United Kingdom)

2006-07-01

319

Biotransformation of uranium and other actinides in radioactive wastes  

Microsoft Academic Search

Microorganisms affect the solubility, bioavailability, and mobility of actinides in radioactive wastes. Under appropriate conditions, actinides are solubilized or stabilized by the direct enzymatic or indirect nonenzymatic actions of microorganisms. Biotransformation of various forms of uranium (ionic, inorganic, and organic complexes) by aerobic and anaerobic microorganisms has been extensively studied, whereas limited information is available on other important actinides (Th,

A. J. Francis

1998-01-01

320

Geologic storage of radioactive waste: field studies in Sweden  

Microsoft Academic Search

Access to a gran itic rock mass in an iron ore mine in Sweden provided a unique opportunity for underground experiments related to the geologic disposal of radioactive waste. These field tests demonstrated the importance of hydrogeology and the difficulties in predicting in the thermomechanical behavior of fractured granitic rocks. To characterize a site fully, measurements made from the surface

P. A. Witherspoon; N. G. W. Cook; J. E. Gale

1981-01-01

321

International Surveillance Mechanism for Sea Dumping of Radioactive Waste  

ERIC Educational Resources Information Center

|The OECD consultation and surveillance mechanism is discussed in detail in this article. Four phases are identified and examined: (1) Notification, (2) Consultation, (3) Supervision, (4) Post-operation. This system is designed to provide the safest possible conditions for sea dumping of radioactive wastes. (MA)|

OECD Observer, 1977

1977-01-01

322

Disposal of Radioactive Waste at Hanford Creates Problems  

ERIC Educational Resources Information Center

|Radioactive storage tanks at the Hanford facility have developed leaks. The situation is presently considered safe, but serious. A report from the National Academy of Science has recommended that the wastes be converted to stable solids and stored at another site on the Hanford Reservation. (Author/MA)|

Chemical and Engineering News, 1978

1978-01-01

323

Update on Radioactive Waste Management in the UK.  

National Technical Information Service (NTIS)

This paper provides a brief background to the current position in the United Kingdom (UK) and provides an update on the various developments and initiatives within the field of radioactive waste management that have been taking place during 2002/03. These...

J. Dalton A. McCall

2003-01-01

324

ANNUAL REPORT. ACTINIDE-ALUMINATE SPECIATION IN ALKALINE RADIOACTIVE WASTE  

EPA Science Inventory

Highly alkaline radioactive waste tanks contain a number of transuranic species, in particular U, Np, Pu, and Am-the exact forms of which are currently unknown. Knowledge of actinide speciation under highly alkaline conditions is essential towards understanding and predicting the...

325

Ion-exchange material and method of storing radioactive wastes  

DOEpatents

A new cation exchanger is a modified tobermorite containing aluminum isomorphously substituted for silicon and containing sodium or potassium. The exchanger is selective for lead, rubidium, cobalt, and cadmium and is selective for cesium over calcium or sodium. The tobermorites are compatible with cement and are useful for the long-term fixation and storage of radioactive nuclear wastes.

Komarneni, S.; Roy, D.M.

1983-10-31

326

Radioactive wastes from uranium mining enterprises and their environmental effects  

Microsoft Academic Search

content in the ore and the activity of the geochemical processes occurring in the deposit prior to mining, particularly natural leaching resulting from the shift in the equilibrium of uranium with regard to its decay products [i]. The level of radioactivity of the wastes from the exploitation of known uranium deposits is usually low, especially if it is compared with

V. N. Mosinets

1991-01-01

327

Give The Public Something, Something More Interesting Radioactive Waste.  

National Technical Information Service (NTIS)

In the Netherlands the policy to manage radioactive waste is somewhat different from that in other countries, although the practical outcome is not much different. Long-term, i.e. at least 100 years, storage in above ground engineered structures of all wa...

H. D. K. Codee

2003-01-01

328

Mitigation of plant penetration into radioactive waste utilizing herbicides  

SciTech Connect

This paper describes the use of herbicides as an effective method of precluding plant root penetration into buried radioactive wastes. The discussed surface applications are selective herbicides to control broadleaf vegetation in grasses; nonselective herbicides, which control all vegetation; and slow-release forms of these herbicides to prolong effectiveness.

Cox, G.R.

1982-01-01

329

303-K Radioactive mixed-waste storage facility closure plan.  

National Technical Information Service (NTIS)

The Hanford Site, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials. The 303-K Radioactive Mixed-Waste Storage Facility (303-K Facility) has been used since 1943 to store various radi...

1990-01-01

330

Locating a Radioactive Waste Repository in the Ring of Fire  

NASA Astrophysics Data System (ADS)

The scientific, technical, and sociopolitical challenges of finding a secure site for a geological repository for radioactive wastes have created a long and stony path for many countries. Japan carried out many years of research and development before taking its first steps in site selection. The Nuclear Waste Management Organization of Japan (NUMO) began looking for a high-level waste repository site (HLW, vitrified residue from reprocessing power reactor fuel) 2 years ago. Over the next 10-20 years, NUMO hopes to find a site to dispose of ~20,000 tons of HLW in a robustly engineered repository constructed at a depth of several hundred meters.

Apted, Mick; Berryman, Kelvin; Chapman, Neil; Cloos, Mark; Connor, Chuck; Kitayama, Kazumi; Sparks, Steve; Tsuchi, Hiroyuki

2004-11-01

331

Stability of radioactive waste glasses assessed from hydration thermodynamics  

SciTech Connect

Assessment of the geologic performance of radioactive waste glasses requires extrapolation of finite tests to very long times. Hydration thermodynamics provides a means to compare the stability of waste glasses to natural analogues and to ancient synthetic glasses. The glass composition is separated into structural components of known free energy of hydration. These are then summed to provide a discrete measure of the stability of a given glass to aqueous attack. Hydration thermodynamics can be used to extend the results of laboratory tests of Savannah River waste glass to the repository environment. 15 references, 3 figures, 1 table.

Plodinec, M J; Jantzen, C M; Wicks, G G

1983-01-01

332

77 FR 52073 - Request To Amend a License To Export Radioactive Waste  

Federal Register 2010, 2011, 2012, 2013

...Request To Amend a License To Export Radioactive Waste Pursuant to 10 CFR 110.70...27, 2012, July 31, 2012, XW012/ radioactive total of 5,500 materials and/or...11005699. waste including tons or about radioactive various 1,000 tons waste that is...

2012-08-28

333

Dewatering of liwuid radioactive wastes in thin-film rotary evaporators  

Microsoft Academic Search

A sizable amount of liquid radioactive waste of different levels of radioactivity is formed during the operation of an atomic power plant and during reprocessing of spent nuclear fuel. Current concepts for handling such wastes require reliable isolation of them from the biosphere. At present, bituminization and cementation for medium- and low-level liquid radioactive waste and vitrification for high- and

A. S. Nikiforov; V. I. Vlasov; V. I. Davydov; P. G. Dobrygin; A. I. Kachurin; O. A. Krivyakov; D. A. Kukiev; A. S. Polyakov; V. F. Savelev; S. N. Filippov

1989-01-01

334

Radioactive Waste Management Information for 1991 and Record-to-Date  

SciTech Connect

This document presents detailed data, bar graphs, and pie charts on volume, radioactivity, isotopic identity, origin, and decay status of radioactive waste for the calendar year 1991. It also summarizes the radiative waste data records compiled from 1952 to present for the Idaho National Engineering Laboratory (INEL). The data presented are from the INEL Radioactive Waste Management Information System.

Litteer, D.L.; Peterson, C.N.; Sims, A.M.

1993-04-01

335

Nuclear power and radioactive waste: a sub-seabed disposal option  

Microsoft Academic Search

The radioactive waste disposal programs of most countries are still focused on investigation of land-based geologic formations as possible containment media for radioactive wastes. Important discoveries in geological oceanography and amazing advances in ocean engineering over the past decade have, however, led several countries to investigate another promising possibility for geologic disposal of radioactive waste--isolation within the deep seabed or

Deese

1978-01-01

336

Modelling Sequential BIOsphere Systems under CLIMate Change for Radioactive Waste Disposal. Project BIOCLIM  

Microsoft Academic Search

The BIOCLIM project (Modelling Sequential BIOsphere systems under CLIMate change for Radioactive Waste Disposal) is part of the EURATOM fifth European framework programme. The project was launched in October 2000 for a three -year period. It is coordinated by ANDRA, the French national radioactive waste management agency. The project brings together a number of European radioactive waste management organisations that

D. Texier; P. Degnan; M. F. Loutre; G. Lematre; M. Thorne

337

Radioactive waste acceptance team and generator interface yields successful implementation of waste acceptance criteria  

SciTech Connect

The Fernald Environmental Management Project has developed a successful Low Level Waste Shipping Program in compliance with the Nevada Test Site Defense Waste Acceptance Criteria, Certification, and Transfer Requirements, NVO-325, Revision 1. This shipping program is responsible for the successful disposal of more than 4 million cubic feet of Low Level Waste over the past decade. The success of the Fernald Low Level Waste Shipping Program is due to the generator program staff working closely with the DOE-NV Radioactive Waste Acceptance Program Team to achieve win/win situations. The teamwork is the direct result of dedicated, proactive professionals working together toward a common objective: the safe disposition of low level radioactive waste. The growth and development of this program has many lessons learned to share with the low level waste generating community. The recognition of reciprocal interests enables consistently high annual volumes of Fernald waste disposal at the Nevada Test Site without incident. The large volumes successfully disposed serve testimony to the success of the program which is equally important to all Nevada Test Site and Fernald stakeholders. The Fernald approach to success is currently being shared with other low-level waste generators through DOE-NV sponsored outreach programs. This paper introduces examples of Fernald Environmental Restoration Management Corporation contributions to the DOE-NV Radioactive Waste Acceptance Program outreach initiatives. These practices are applicable to other low level waste disposal programs whether federal, commercial, domestic or international.

Rowe, J.G. [Fernald Environmental Restoration Management Corp., Cincinnati, OH (United States); Griffin, W.A.; Rast, D.M. [USDOE, Washington, DC (United States)

1996-02-01

338

Advanced radioactive waste-glass melters  

SciTech Connect

During pilot scale operations of the Scale Glass Melter for the US Department of Energy a team of engineers and scientists was formed to assess the need for continued melter design development to support the Defense Waste Processing Facility (DWPF), and prioritize future efforts. Recently this has taken on new importance because of selection of the DWPF Melter design as the reference for the Hanford Waste Vitrification Project (HWVP), and increased interest at the West Valley Demonstration Project on melter life and replacement. Results of the study are summarized, and goals produced by the study are compared to the results of current programs at the Savannah River Laboratory (SRL).

Bickford, D.F.

1990-01-01

339

Advanced radioactive waste-glass melters  

SciTech Connect

During pilot scale operations of the Scale Glass Melter for the US Department of Energy a team of engineers and scientists was formed to assess the need for continued melter design development to support the Defense Waste Processing Facility (DWPF), and prioritize future efforts. Recently this has taken on new importance because of selection of the DWPF Melter design as the reference for the Hanford Waste Vitrification Project (HWVP), and increased interest at the West Valley Demonstration Project on melter life and replacement. Results of the study are summarized, and goals produced by the study are compared to the results of current programs at the Savannah River Laboratory (SRL).

Bickford, D.F.

1990-12-31

340

Novel Solvent for the Simultaneous recovery of Radioactive Nuclides from Liquid Radioactive Wastes  

Microsoft Academic Search

The present invention relates to solvents, and methods, for selectively extracting and recovering radionuclides, especially cesium and strontium, rare earths and actinides from liquid radioactive wastes. More specifically, the invention relates to extracting agent solvent compositions comprising complex organoboron compounds, substituted polyethylene glycols, and neutral organophosphorus compounds in a diluent. The preferred solvent comprises a chlorinated cobalt dicarbollide, diphenyl-dibutylmethylenecarbamoylphosphine oxide,

Valeriy Nicholiavich Romanovskiy; Lgor V. Smirnov; Vasiliy A. Babain; Terry A. Todd; Ken N. Brewer

1999-01-01

341

Defense Waste Processing Facility -- Radioactive operations -- Part 3 -- Remote operations  

SciTech Connect

The Savannah River Site`s Defense Waste Processing Facility (DWPF) near Aiken, South Carolina is the nation`s first and world`s largest vitrification facility. Following a ten year construction period and nearly three years of non-radioactive testing, the DWPF began radioactive operations in March 1996. Radioactive glass is poured from the joule heated melter into the stainless steel canisters. The canisters are then temporarily sealed, decontaminated, resistance welded for final closure, and transported to an interim storage facility. All of these operations are conducted remotely with equipment specially designed for these processes. This paper reviews canister processing during the first nine months of radioactive operations at DWPF. The fundamental design consideration for DWPF remote canister processing and handling equipment are discussed as well as interim canister storage.

Barnes, W.M.; Kerley, W.D.; Hughes, P.D.

1997-06-01

342

Radiation chemistry of polymeric components of radioactive waste  

SciTech Connect

The presentation covers fragments of research on the role of radiation chemistry in radioactive waste management. Radioactive waste often contains polymeric materials contaminated with actinides, which exhibit a activity for thousands of years. Rules of safety of transportation and environmental security of permanent storage demand the understanding of radiation chemistry of typical waste matrices. Due to a slow decay and a short range of penetration of a emitters, the experiments with actinides are not easy. 'Therefore, accelerated experiments have been performed using 10 MeV electrons of high intensity. That way chemical effects proceeding over thousands of years could be reduced to minutes in the laboratory. Simulation of the effect of a-radiolysis on polymers by low LET radiation is justified, because low LET radiation produces multi-ionization spurs resulting in the same chemistry as high LET radiation.

Dziewinski, J. J. (Jacek J.); Zagorski, Z. (Zbigniew)

2002-01-01

343

Iraq liquid radioactive waste tanks maintenance and monitoring program plan.  

SciTech Connect

The purpose of this report is to develop a project management plan for maintaining and monitoring liquid radioactive waste tanks at Iraq's Al-Tuwaitha Nuclear Research Center. Based on information from several sources, the Al-Tuwaitha site has approximately 30 waste tanks that contain varying amounts of liquid or sludge radioactive waste. All of the tanks have been non-operational for over 20 years and most have limited characterization. The program plan embodied in this document provides guidance on conducting radiological surveys, posting radiation control areas and controlling access, performing tank hazard assessments to remove debris and gain access, and conducting routine tank inspections. This program plan provides general advice on how to sample and characterize tank contents, and how to prioritize tanks for soil sampling and borehole monitoring.

Dennis, Matthew L.; Cochran, John Russell; Sol Shamsaldin, Emad (Iraq Ministry of Science and Technology)

2011-10-01

344

RETENTION OF SULFATE IN HIGH LEVEL RADIOACTIVE WASTE GLASS  

SciTech Connect

High level radioactive wastes are being vitrified at the Savannah River Site for long term disposal. Many of the wastes contain sulfate at concentrations that can be difficult to retain in borosilicate glass. This study involves efforts to optimize the composition of a glass frit for combination with the waste to improve sulfate retention while meeting other process and product performance constraints. The fabrication and characterization of several series of simulated waste glasses are described. The experiments are detailed chronologically, to provide insight into part of the engineering studies used in developing frit compositions for an operating high level waste vitrification facility. The results lead to the recommendation of a specific frit composition and a concentration limit for sulfate in the glass for the next batch of sludge to be processed at Savannah River.

Fox, K.

2010-09-07

345

Nuclear waste: our radioactive hot potato  

Microsoft Academic Search

Nuclear industry inevitably produces nuclear waste, whose prudent, prompt and economic disposal is important to the national welfare. Technological problems of containment and isolation have apparently been solved. Underground or geologic disposal sites have the potential form permanent isolation, with salt, basalt, granite, shale, and tuff currently receiving principal attention as repository host rocks. Bedded salt deposits may offer the

Conselman

1984-01-01

346

Radioactive waste disposal in the marine environment  

Microsoft Academic Search

In order to find the optimal solution to waste disposal problems, it is necessary to make comparisons between disposal media. It has become obvious to many within the scientific community that the single medium approach leads to over protection of one medium at the expense of the others. Cross media comparisons are being conducted in the Department of Energy ocean

D. R. Anderson

1981-01-01

347

1978 radioactive waste tank inspection program  

Microsoft Academic Search

The 1978 tank inspection program was completed with inspections through all 158 accessible annulus risers on the double-wall tanks using at least one photographic technique at each riser. No unusual conditions were noted. Inspections were begun on tanks 25 to 28 which are in the late stages of construction; they will be completed during 1979. Eleven waste tank interior inspections

R. L. Boyleston; M. A. Knowles; J. A. Baldwin; F. G. McNatt

1979-01-01

348

Hydrothermal oxidation of radioactive combustible waste  

Microsoft Academic Search

A hydrothermal processing system was designed, built and tested for treatment of transuranic combustible material. The operation is performed in a plutonium glovebox. Presented in this paper are results from the study of the hydrothermal oxidation of plutonium and americium contaminated organic wastes. The use of thermal liquefaction, via pyrolysis, to prepare solid materials for hydrothermal processing was tested and

L. A Worl; S. J Buelow; D. M Harradine; R Lanning; D. D Padilla; J. H Roberts; X Shao

2000-01-01

349

Radioactive waste management and the nuclear fuel cycle. Volume 4, No. 3, waste management organizations  

Microsoft Academic Search

This special issue of the Journal: Radioactive Waste Management and the Nuclear Fuel Cycle, is a collection of papers describing the management organizations and nuclear waste programs in six European countries, the United States, and the IAEA. European countries included are Switzerland, Sweden, France, Belgium, Italy, and the United Kingdom. Collectively,the papers present a comprehensive background, with history of the

1984-01-01

350

10 CFR 72.108 - Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste...  

Code of Federal Regulations, 2010 CFR

...fuel, high-level radioactive waste, or reactor-related greater than Class C waste transportation...HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE...fuel, high-level radioactive waste, or reactor-related greater than Class C waste...

2009-01-01

351

10 CFR 72.108 - Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste...  

Code of Federal Regulations, 2010 CFR

...fuel, high-level radioactive waste, or reactor-related greater than Class C waste transportation...HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE...fuel, high-level radioactive waste, or reactor-related greater than Class C waste...

2010-01-01

352

Integrating natural and social sciences to inspire public confidence in radioactive waste policy case study - Committee on radioactive waste management  

SciTech Connect

Integrating Natural and Social Sciences to Inspire Public Confidence in Radioactive Waste Policy Case Study: Committee on Radioactive Waste Management Implementing effective long-term radioactive waste management policy is challenging, and both UK and international experience is littered with policy and programme failures. Policy must not only be underpinned by sound science and technical rationale, it must also inspire the confidence of the public and other stakeholders. However, in today's modern society, communities will not simply accept the word of scientists for setting policy based purely on technical grounds. This is particularly so in areas where there are significant social and ethical issues, such as radioactive waste disposal. To develop and implement effective policy, governments, waste owners and implementing bodies must develop processes which effectively integrate both complex technical and scientific issues, with equally challenging social and ethical concerns. These integrating processes must marry often intricate technical issues with broad public and stakeholder engagement programmes, in programmes which can expect the highest levels of public scrutiny, and must invariably be delivered within challenging time and budget constraints. This paper considers a model for how such integrating processes can be delivered. The paper reviews, as a case study, how such challenges were overcome by the Committee on Radioactive Waste Management (CoRWM), which, in July 2006, made recommendations to the UK government for the establishment of a long-term radioactive waste policy. Its recommendations were underpinned by sound science, but also engendered public confidence through undertaking the largest and most significant deliberative public and stakeholder engagement programme on a complex policy issue in the UK. Effective decision-making was enabled through the integration of both proven and bespoke methodologies, including Multi-criteria Decision Analysis and Holistic assessments, coupled with an overarching deliberative approach. How this was managed and delivered to programme demonstrates how important effective integration of different issues, interests and world views can be achieved, and the paper looks forward to how the continued integration of both natural and social sciences is essential if public confidence is to be maintained through implementation stages. This paper will be particularly relevant to governments, waste owners and implementing bodies who are responsible for developing and implementing policy. (author)

Usher, Sam [AMEC Nuclear NNC (United Kingdom)

2007-07-01

353

Gas generation phenomena in radioactive waste transportation packaging  

SciTech Connect

The interaction of radiation from radioactive materials with the waste matrix can lead to the deterioration of the waste form resulting in the possible formation of gaseous species. Depending on the type and characteristics of the radiation source, the generation of hydrogen may predominate. Since the interaction of alpha particles with the waste form results in significant energy transfer, other gases such as carbon oxides, methane, nitrogen oxides, oxygen, water, and helium are possible. The type of gases produced from the waste forms is determined by the mechanisms involved in the waste degradation. For transuranic wastes, the identified degradation mechanisms are reported to be caused by radiolysis, thermal decomposition or dewatering, chemical corrosion, and bacterial action. While all these mechanisms may be responsible for the buildup of gases during the storage of wastes, radiolysis and thermal decomposition appear to be the main contributors during waste transport operations. In this paper, the authors provide a review of applicable gas generation data resulting from the degradation of various waste forms under conditions typical for transport. The effects of radiolytic and thermal degradation mechanisms will be discussed in the context of transportation safety.

Nigrey, P.J.

1997-11-01

354

Lessons Learned from Radioactive Waste Storage and Disposal Facilities  

SciTech Connect

The safety of radioactive waste disposal facilities and the decommissioning of complex sites may be predicated on the performance of engineered and natural barriers. For assessing the safety of a waste disposal facility or a decommissioned site, a performance assessment or similar analysis is often completed. The analysis is typically based on a site conceptual model that is developed from site characterization information, observations, and, in many cases, expert judgment. Because waste disposal facilities are sited, constructed, monitored, and maintained, a fair amount of data has been generated at a variety of sites in a variety of natural systems. This paper provides select examples of lessons learned from the observations developed from the monitoring of various radioactive waste facilities (storage and disposal), and discusses the implications for modeling of future waste disposal facilities that are yet to be constructed or for the development of dose assessments for the release of decommissioning sites. Monitoring has been and continues to be performed at a variety of different facilities for the disposal of radioactive waste. These include facilities for the disposal of commercial low-level waste (LLW), reprocessing wastes, and uranium mill tailings. Many of the lessons learned and problems encountered provide a unique opportunity to improve future designs of waste disposal facilities, to improve dose modeling for decommissioning sites, and to be proactive in identifying future problems. Typically, an initial conceptual model was developed and the siting and design of the disposal facility was based on the conceptual model. After facility construction and operation, monitoring data was collected and evaluated. In many cases the monitoring data did not comport with the original site conceptual model, leading to additional investigation and changes to the site conceptual model and modifications to the design of the facility. The following cases are discussed: commercial LLW disposal facilities; uranium mill tailings disposal facilities; and reprocessing waste storage and disposal facilities. The observations developed from the monitoring and maintenance of waste disposal and storage facilities provide valuable lessons learned for the design and modeling of future waste disposal facilities and the decommissioning of complex sites.

Esh, David W.; Bradford, Anna H. [U.S. Nuclear Regulatory Commission, Two White Flint North, MS T7J8, 11545 Rockville Pike, Rockville, MD 20852 (United States)

2008-01-15

355

Conversion of radioactive and hazardous chemical wastes into borosilicate glass using the glass material oxidation and dissolution system  

Microsoft Academic Search

A new vitrification process has been invented. The Glass Material Oxidation and Dissolution System (GMODS) allows direct conversion of radioactive and hazardous chemical wastes to borosilicate glass. GMODS directly converts metals, ceramics and amorphous solids to glass, oxidizes organics with the residue converted to glass, and converts halides (such as chlorides) to borosilicate glass and a secondary sodium halide stream.

C. W. Forsberg; E. C. Beahm; G. W. Parker; K. R. Elam

1996-01-01

356

Improving radioactive waste management: an overview of the Environmental Protection Agency's low-activity waste effort.  

PubMed

Radioactive waste disposal in the United States is marked by a fragmented regulatory system, with requirements that often focus on the origin or statutory definition of the waste, rather than the hazard of the material in question. It may be possible to enhance public protection by moving toward a system that provides disposal options appropriate for the hazard presented by the waste in question. This paper summarizes aspects of an approach focusing on the potential use, with appropriate conditions, of Resource Conservation and Recovery Act Subtitle-C hazardous waste landfills for disposal of "low-activity" wastes and public comments on the suggested approach. PMID:17033466

Schultheisz, Daniel J; Czyscinski, Kenneth S; Klinger, Adam D

2006-11-01

357

Method for acid oxidation of radioactive, hazardous, and mixed organic waste materials  

Microsoft Academic Search

The present invention is directed to a process for reducing the volume of low level radioactive and mixed waste to enable the waste to be more economically stored in a suitable repository, and for placing the waste into a form suitable for permanent disposal. The invention involves a process for preparing radioactive, hazardous, or mixed waste for storage by contacting

Robert A. Pierce; James R. Smith; William G. Ramsey; Connie A. Cicero-Herman; Dennis F. Bickford

1999-01-01

358

Development and demonstration of solvent extraction processes for the separation of radionuclides from acidic radioactive waste  

Microsoft Academic Search

The presence of long-lived radionuclides presents a challenge to the management of radioactive wastes. Immobilization of these radionuclides must be accomplished prior to long-term, permanent disposal. Separation of the radionuclides from the waste solutions has the potential of significantly decreasing the costs associated with the immobilization and disposal of the radioactive waste by minimizing waste volumes. Several solvent extraction processes

J. D. Law; K. N. Brewer; R. S. Herbst; T. A. Todd; D. J. Wood

1999-01-01

359

Integrating Modeling and Monitoring for the Radioactive Waste Management Complex  

SciTech Connect

United States Department of Energy Order 435.1, Radioactive Waste Management, includes requirements for assessing the long-term performance of radioactive waste disposal facilities and also for environmental monitoring of the performance of those facilities throughout the time of institutional control. It is also specified that performance assessment and composite analysis modeling should be integrated with environmental monitoring in order to provide a means to assess the adequacy of the assumptions that were made for the modeling. This paper describes the development of action levels, which are expected concentrations at different locations in the subsurface based on modeling conducted for the performance assessment and composite analysis for the low-level waste disposal facility at the Radioactive Waste Management Complex at the Idaho National Engineering and Environmental Laboratory. First year comparisons of measured concentrations with the action level have shown that migration appears to be occurring at a much lower rate than predicted by the models. This supports the conclusion that the modeling is conservative and conclusions based on the modeling are likewise conservative.

Seitz, Roger Ray; Mccarthy, James Michael; Keck, Karen Nina

2002-08-01

360

A robotic inspector for low-level radioactive waste  

SciTech Connect

The Department of Energy has low-level radioactive waste stored in warehouses at several facilities. Weekly visual inspections are required. A mobile robot inspection system, ARIES (Autonomous Robotic Inspection Experimental System), has been developed to survey and inspect the stored drums. The robot will travel through the three- foot wide aisles of drums stacked four high and perform a visual inspection, normally performed by a human operator, making decisions about the condition of the drums and maintaining a database of pertinent information about each drum. This mobile robot system will improve the quality of inspection, generate required reports, and relieve human operators from low-level radioactive exposure.

Byrd, J.S.; Pettus, R.O. [South Carolina Univ., Columbia, SC (United States). Dept. of Electrical and Computer Engineering

1996-06-01

361

Porous Matrixes for Immobilization of Radioactive Wastes  

SciTech Connect

The process was studied and the technology developed to obtain a highly porous coke based material with the solid dispersed filler (zirconium dioxide); properties and technological characteristics of the material were investigated. Technological process was developed for the fabrication of products out of the highly porous high melting compound (zirconium carbide). Technology for the fabrication of products out of the highly porous high melting compound bypassing the necessity of obtaining the dry radioactive feed powders and allows producing the material with a wide range of compositions and properties. In this paper we describe a technological process for the fabrication of materials, assuming the impregnation of a porous zirconium carbide form by the liquid highly concentrated solution of actinides followed by the decomposition of the obtained product during the thermal treatment to form stable oxides. We are investigating the properties of the final form as a possible target in a nuclear reactors to use neutrons to burn up the actinides. (authors)

Ershov, B.G.; Minaev, A.A.; Afonin, M.M.; Kuznetsov, D.G. [Institute of Physical Chemistry and Electrochemisrty, Russian Academy of Sciences, Moscow (Russian Federation)

2007-07-01

362

Stainless steel-zirconium alloy waste forms for metallic fission products and actinides during treatment of spent nuclear fuel  

SciTech Connect

Stainless steel-zirconium waste form alloys are being developed for the disposal of metallic wastes recovered from spent nuclear fuel using an electrometallurgical process developed by Argonne National Laboratory. The metal waste form comprises the fuel cladding, noble metal fission products and other metallic constituents. Two nominal waste form compositions are being developed: (1) stainless steel-15 wt% zirconium for stainless steel-clad fuels. The noble metal fission products are the primary source of radiation and their contribution to the waste form radioactivity has been calculated. The disposition of actinide metals in the waste alloys is also being explored. Simulated waste form alloys were prepared to study the baseline alloy microstructures and the microstructural distribution of noble metals and actinides, and to evaluate corrosion performance.

McDeavitt, S.M.; Abraham, D.P.; Park, J.-Y. [Argonne National Lab., IL (United States); Keiser, D.D. Jr. [Argonne National Lab., Idaho Falls, ID (United States)

1996-07-01

363

FINAL REPORT. FOAMING AND ANTIFOAMING IN RADIOACTIVE WASTE PRETREATMENT AND IMMOBILIZATION  

EPA Science Inventory

Radioactive waste treatment processes usually involve concentration of radionuclides before waste can be immobilized by storing it in stable solid form. Foaming is observed at various stages of waste processing like sludge chemical processing and melter operations. Hence, the obj...

364

Summary of radioactive solid waste received in the 200 Areas during calendar year 1990  

SciTech Connect

Westinghouse Hanford Company manages and operates the Hanford Site 200 Areas radioactive solid waste storage and disposal facilities for the US Department of Energy-Richland Operations Office under contract AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Areas radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1990. This report does not include solid radioactive wastes in storage or disposal in other areas or facilities such as the underground tank farms. Unless packaged within the scope of Hanford Site radioactive solid waste acceptance criteria, liquid waste data are not included in this document. 10 refs., 1 tab.

Anderson, J.D.; McCann, D.C.; Poremba, B.E.

1991-04-01

365

Greater-confinement disposal of low-level radioactive wastes  

SciTech Connect

Low-level radioactive wastes include a broad spectrum of wastes that have different radionuclide concentrations, half-lives, and physical and chemical properties. Standard shallow-land burial practice can provide adequate protection of public health and safety for most low-level wastes, but a small volume fraction (about 1%) containing most of the activity inventory (approx.90%) requires specific measures known as ''greater-confinement disposal'' (GCD). Different site characteristics and different waste characteristics - such as high radionuclide concentrations, long radionuclide half-lives, high radionuclide mobility, and physical or chemical characteristics that present exceptional hazards - lead to different GCD facility design requirements. Facility design alternatives considered for GCD include the augered shaft, deep trench, engineered structure, hydrofracture, improved waste form, and high-integrity container. Selection of an appropriate design must also consider the interplay between basic risk limits for protection of public health and safety, performance characteristics and objectives, costs, waste-acceptance criteria, waste characteristics, and site characteristics. This paper presents an overview of the factors that must be considered in planning the application of methods proposed for providing greater confinement of low-level wastes. 27 refs.

Trevorrow, L.E.; Gilbert, T.L.; Luner, C.; Merry-Libby, P.A.; Meshkov, N.K.; Yu, C.

1985-01-01

366

The management of radioactive wastes in the UK  

SciTech Connect

The safe management and disposal of radioactive wastes is clearly a necessary requirement for the future development of nuclear energy. The nuclear program in the United Kingdom has evolved over the past 40 years, and the management of wastes arising from the industry has been developed in parallel. Strategy is in place for the management of all categories of waste, i.e., low-, intermediate-, and high-level wastes, and good progress is being made on the facilities for the conditioning of these wastes and their eventual disposal. Low-level wastes (LLW) will be compacted and the compacts grouted into steel containers prior to being disposed of in shallow engineered vaults at the Drigg disposal site near Sellafield. Intermediate-level wastes (ILW) arising from reprocessing operations and elsewhere will be encapsulated in cement in 500-{ell} stainless steel drums (or other containers) at Sellafield. High-level liquid waste from reprocessing operations, which has hitherto been stored in concentrated form in high-integrity tanks, is now being vitrified at Sellafield, and the canisters of glass will be stored for at least 50 years prior to final disposal.

Wilkinson, W.L. (British Nuclear Fuels Ltd., Risley (England))

1991-01-01

367

Transportation functions of the Civilian Radioactive Waste Management System  

SciTech Connect

Within the framework of Public Law 97.425 and provisions specified in the Code of Federal Regulations, Title 10 Part 961, the US Department of Energy has the responsibility to accept and transport spent fuel and high-level waste from various organizations which have entered into a contract with the federal government in a manner that protects the health and safety of the public and workers. In implementing these requirements, the Office of Civilian Radioactive Waste Management (OCRWM) has, among other things, supported the identification of functions that must be performed by a transportation system (TS) that will accept the waste for transport to a federal facility for storage and/or disposal. This document, through the application of system engineering principles, identifies the functions that must be performed to transport waste under this law.

Shappert, L.B. (ed.); Attaway, C.R.; Pope, R.B. (Oak Ridge National Lab., TN (United States)); Best, R.E.; Danese, F.L. (Science Applications International Corp., Oak Ridge, TN (United States)); Dixon, L.D. (Dixon (L.D.), Martinez, GA (United States)); Jones, R.H. (Jones (R.H.), Los Gatos, CA (United States)); Klimas, M.J. (USDOE Chicago Operations Office, Argonne, IL (United States)); Peterson, R.W

1992-03-01

368

USING STATISTICAL PROCESS CONTROL TO MONITOR RADIOACTIVE WASTE CHARACTERIZATION AT A RADIOACTIVE FACILITY  

SciTech Connect

Two facilities for storing spent nuclear fuel underwater at the Hanford site in southeastern Washington State being removed from service, decommissioned, and prepared for eventual demolition. The fuel-storage facilities consist of two separate basins called K East (KE) and K West (KW) that are large subsurface concrete pools filled with water, with a containment structure over each. The basins presently contain sludge, debris, and equipment that have accumulated over the years. The spent fuel has been removed from the basins. The process for removing the remaining sludge, equipment, and structure has been initiated for the basins. Ongoing removal operations generate solid waste that is being treated as required, and then disposed. The waste, equipment and building structures must be characterized to properly manage, ship, treat (if necessary), and dispose as radioactive waste. As the work progresses, it is expected that radiological conditions in each basin may change as radioactive materials are being moved within and between the basins. It is imperative that these changing conditions be monitored so that radioactive characterization of waste is adjusted as necessary.

WESTCOTT, J.L.

2006-11-15

369

USING STATISTICAL PROCESS CONTROL TO MONITOR RADIOACTIVE WASTE CHARACTERIZATION AT A RADIOACTIVE FACILITY  

SciTech Connect

Two facilities for storing spent nuclear fuel underwater at the Hanford site in southeastern Washington State are being removed from service, decommissioned, and prepared for eventual demolition. The fuel-storage facilities consist of two separate basins called K East (KE) and K West (KW) that are large subsurface concrete pools filled with water, with a containment structure over each. The basins presently contain sludge, debris, and equipment that have accumulated over the years. The spent fuel has been removed from the basins. The process for removing the remaining sludge, equipment, and structure has been initiated for the basins. Ongoing removal operations generate solid waste that is being treated as required, and then disposed. The waste, equipment and building structures must be characterized to properly manage, ship, treat (if necessary), and dispose as radioactive waste. As the work progresses, it is expected that radiological conditions in each basin may change as radioactive materials are being moved within and between the basins. It is imperative that these changing conditions be monitored so that radioactive characterization of waste is adjusted as necessary.

WESTCOTT, J.L.; JOCHEN; PREVETTE

2007-01-02

370

Radioactive waste management plan for the PBMR (Pty) Ltd fuel plant  

Microsoft Academic Search

The Pebble Bed Modular Reactor (Pty) Ltd Fuel Plant (PFP) radioactive waste management plan caters for waste from generation, processing through storage and possible disposal. Generally, the amount of waste that will be generated from the PFP is Low and Intermediate Level Waste. The waste management plan outlines all waste streams and the management options for each stream. It also

Mosidi E. Makgae

2009-01-01

371

Summary of radioactive solid waste received in the 200 Areas during calendar year 1992  

SciTech Connect

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Field Office, under contract DE-AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1991. This report does not include solid radioactive wastes in storage or disposed of in other areas or facilities such as the underground tank farms, or backlog wastes. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, (WHC 1988), liquid waste data are not included in this document.

Anderson, J.D.; Hagel, D.L.

1992-05-01

372

Spent Fuel and High-Level Radioactive Waste Transportation Report  

SciTech Connect

This publication is intended to provide its readers with an introduction to the issues surrounding the subject of transportation of spent nuclear fuel and high-level radioactive waste, especially as those issues impact the southern region of the United States. It was originally issued by SSEB in July 1987 as the Spent Nuclear Fuel and High-Level Radioactive Waste Transportation Primer, a document patterned on work performed by the Western Interstate Energy Board and designed as a ``comprehensive overview of the issues.`` This work differs from that earlier effort in that it is designed for the educated layman with little or no background in nuclear waste Issues. In addition. this document is not a comprehensive examination of nuclear waste issues but should instead serve as a general introduction to the subject. Owing to changes in the nuclear waste management system, program activities by the US Department of Energy and other federal agencies and developing technologies, much of this information is dated quickly. While this report uses the most recent data available, readers should keep in mind that some of the material is subject to rapid change. SSEB plans periodic updates in the future to account for changes in the program. Replacement pages will be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list.

Not Available

1992-03-01

373

DEVELOPMENT OF GLASS MATRICES FOR HLW RADIOACTIVE WASTES  

SciTech Connect

Vitrification is currently the most widely used technology for the treatment of high level radioactive wastes (HLW) throughout the world. Most of the nations that have generated HLW are immobilizing in either borosilicate glass or phosphate glass. One of the primary reasons that glass has become the most widely used immobilization media is the relative simplicity of the vitrification process, e.g. melt waste plus glass forming frit additives and cast. A second reason that glass has become widely used for HLW is that the short range order (SRO) and medium range order (MRO) found in glass atomistically bonds the radionuclides and governs the melt properties such as viscosity, resistivity, sulphate solubility. The molecular structure of glass controls contaminant/radionuclide release by establishing the distribution of ion exchange sites, hydrolysis sites, and the access of water to those sites. The molecular structure is flexible and hence accounts for the flexibility of glass formulations to waste variability. Nuclear waste glasses melt between 1050-1150 C which minimizes the volatility of radioactive components such as Tc{sup 99}, Cs{sup 137}, and I{sup 129}. Nuclear waste glasses have good long term stability including irradiation resistance. Process control models based on the molecular structure of glass have been mechanistically derived and have been demonstrated to be accurate enough to control the world's largest HLW Joule heated ceramic melter in the US since 1996 at 95% confidence.

Jantzen, C.

2010-03-18

374

Pilot studies to achieve waste minimization and enhance radioactive liquid waste treatment at the Los Alamos National Laboratory Radioactive Liquid Waste Treatment Facility  

SciTech Connect

The Radioactive and Industrial Wastewater Science Group manages and operates the Radioactive Liquid Waste Treatment Facility (RLWTF) at the Los Alamos National Laboratory (LANL). The RLWTF treats low-level radioactive liquid waste generated by research and analytical facilities at approximately 35 technical areas throughout the 43-square-mile site. The RLWTF treats an average of 5.8 million gallons (21.8-million liters) of liquid waste annually. Clarifloculation and filtration is the primary treatment technology used by the RLWTF. This technology has been used since the RLWTF became operable in 1963. Last year the RLWTF achieved an average of 99.7% removal of gross alpha activity in the waste stream. The treatment process requires the addition of chemicals for the flocculation and subsequent precipitation of radionuclides. The resultant sludge generated during this process is solidified in drums and stored or disposed of at LANL.

Freer, J.; Freer, E.; Bond, A. [and others

1996-07-01

375

Office of Civilian Radioactive Waste Management annual report to Congress  

SciTech Connect

This sixth Annual Report to Congress by the Office of Civilian Radioactive Waste Management (OCRWM) describes activities and expenditures of the Office during fiscal year 1988. An epilogue chapter reports significant events from the end of the fiscal year on September 30, 1988 through March 1989. The Nuclear Waste Policy Amendments Act (NWPA) of 1987 made significant changes to the NWPA relating to repository siting and monitored retrievable storage and added new provisions for the establishment of several institutional entities with which OCRWM will interact. Therefore, a dominant theme throughout this report is the implementation of the policy focus and specific provisions of the Amendments Act. 50 refs., 8 figs., 4 tabs.

NONE

1989-12-01

376

Metal poisons for criticality in waste streams  

Microsoft Academic Search

Many of the wastes from processing fissile materials contain metals that may serve as neutron poisons. It would be advantageous to the criticality evaluation of these wastes to demonstrate that the poisons remain with the fissile materials and to demonstrate an always safe poison-to-fissile ratio. The first task, demonstrating that the materials stay together, is the job of the chemist;

T. G. Williamson; A. Q. Goslen

1996-01-01

377

Defense waste processing facility radioactive operations. Part 1 - operating experience  

SciTech Connect

The Savannah River Site`s Defense Waste Processing Facility (DWPF) near Aiken, SC is the nation`s first and the world`s largest vitrification facility. Following a ten year construction program and a 3 year non-radioactive test program, DWPF began radioactive operations in March 1996. This paper presents the results of the first 9 months of radioactive operations. Topics include: operations of the remote processing equipment reliability, and decontamination facilities for the remote processing equipment. Key equipment discussed includes process pumps, telerobotic manipulators, infrared camera, Holledge{trademark} level gauges and in-cell (remote) cranes. Information is presented regarding equipment at the conclusion of the DWPF test program it also discussed, with special emphasis on agitator blades and cooling/heating coil wear. 3 refs., 4 figs.

Little, D.B.; Gee, J.T.; Barnes, W.M.

1997-12-31

378

Characterization of radioactive-waste drum contents using real-time x-radiography  

SciTech Connect

Low-level transuranic (TRU) waste is stored in a retrievable manner at the Radioactive Waste Management Complex (RWMC) operated by EG and G Idaho, Inc., for the Department of Energy. The waste, consisting of contaminated rags, paper, plastic, laboratory glassware, tools, scrap metal, wood, electrical components and parts, sludges, etc., is packed in various sized sealed containers, including 55 gallon drums. Waste which can be accurately characterized will be sent to the Waste Isolation Pilot Plant (WIPP) in New Mexico for long term storage if it is certified to meet the WIPP waste acceptance criteria. EG and G Idaho, Inc. is planning to install a real-time x-ray system designed for the automated and semi-automated examination of low-level TRU waste containers including 30, 55, and 83 gallon drums, 4 x 4 x 7 foot plywood boxes, and 4 x 5 x 6 foot metal bins during 1982. This system, designed for production, is capable of examining up to 20,000 waste containers per year using automated container handling, and features real-time x-ray imaging with a 420 kV, 10 ma constant potential source, digital image processing equipment, and video taping facilities (every container examination is required to be taped, for archival documentation). Work planned for the near future involves tests using real-time neutron radiography for waste characterization as a complement to real-time x-ray radiography. Ultimately, the NDE examinations will be combined with automated nondestructive assay (NDA) techniques for complete characterization of a given waste container's contents.

Barna, B.A.; Bishoff, J.R.; Reinhardt, W.W.

1982-01-01

379

Uncertainty analysis for geologic disposal of radioactive waste  

NASA Astrophysics Data System (ADS)

The incorporation and representation of uncertainty in the analysis of the consequences and risk associated with the geologic disposal of high-level radioactive waste are discussed. Such uncertainty has three primary components: process modeling uncertainty, model input data uncertainty, and scenario uncertainty. The following topics are considered in connection with the preceding components: propagation of uncertainty in the modeling of a disposal site, sampling of input data for models, and uncertainty associated with model output.

Cranwell, R. N.; Helton, J. C.

380

Remote radioactive waste drum inspection with an autonomous mobile robot  

SciTech Connect

An autonomous mobile robot is being developed to perform remote surveillance and inspection task on large numbers of stored radioactive waste drums. The robot will be self guided through narrow storage aisles and record the visual image of each viewable drum for subsequent off line analysis and archiving. The system will remove the personnel from potential exposure to radiation, perform the require inspections, and improve the ability to assess the long term trends in drum conditions.

Heckendorn, F.M.; Ward, C.R.; Wagner, D.G.

1992-01-01

381

Remote radioactive waste drum inspection with an autonomous mobile robot  

SciTech Connect

An autonomous mobile robot is being developed to perform remote surveillance and inspection task on large numbers of stored radioactive waste drums. The robot will be self guided through narrow storage aisles and record the visual image of each viewable drum for subsequent off line analysis and archiving. The system will remove the personnel from potential exposure to radiation, perform the require inspections, and improve the ability to assess the long term trends in drum conditions.

Heckendorn, F.M.; Ward, C.R.; Wagner, D.G.

1992-11-01

382

Results of a radioactive waste course for high school teachers  

Microsoft Academic Search

A week-long three-credit graduate-level course was taught in the summer of 1991 for high school science and social science teachers. Instruction was at the layperson's level, and no prior knowledge was presumed. The objectives of the course were to present factual information about radioactive waste, measure recipient's changes in perception about this topic, and measure the effect of the course

S. E. Binney; B. Dodd; J. C. Ringle

1992-01-01

383

Summary review of rock mechanics workshop on radioactive waste disposal  

Microsoft Academic Search

Presentations, critiques and recommendations for the disposal of commercial radioactive waste based upon an analysis of the information presented at the Rock Mechanics Review\\/Workshop, Denver, Colorado, December 16-17, 1976 are summarized. The workshop, comprised of both formal and informal sessions, with about 50 participants, was hosted by RE\\/SPEC Inc. and Dr. Paul F. Gnirk, President and was sponsored by the

N. L. Carter; R. E. Goodman; R. H. Merrill

1977-01-01

384

Deep borehole disposal of high-level radioactive waste  

Microsoft Academic Search

Preliminary evaluation of deep borehole disposal of high-level radioactive waste and spent nuclear fuel indicates the potential for excellent long-term safety performance at costs competitive with mined repositories. Significant fluid flow through basement rock is prevented, in part, by low permeabilities, poorly connected transport pathways, and overburden self-sealing. Deep fluids also resist vertical movement because they are density stratified. Thermal

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

2009-01-01

385

Geohazards due to technologically enhanced natural radioactive wastes  

NASA Astrophysics Data System (ADS)

Human activities can modify naturally occurring radioactive material (NORM) into technologically enhanced naturally occurring radioactive material (TENORM) as a result of industrial activities. Most of these industries do not intend to work with radioactive material a priori. However, whenever a uranium- or thorium-bearing mineral is exploited, NORM-containing by-products and TENORM-contaminated wastes are created. The industrial use of NORM can result in non-negligible radiation exposure of workers and members of the public, exceeding by far the radiation exposure from nuclear technologies. For decades, millions of tons of NORM have been released into the environment without adequate control or even with the lack of any control. Various technologies have been developed for the control of NORM wastes. The paper discusses the merits and limitations of different NORM-waste management techniques, such as Containment, Immobilization, Dilution/Dispersion, Natural Attenuation, Separation, and - as an alternative - Cleaner Technologies. Each of these methods requires a comprehensive risk-benefit-cost analysis.

Steinhusler, Friedrich

2010-10-01

386

Analysis of low-level wastes. Review of hazardous waste regulations and identification of radioactive mixed wastes. Final report  

Microsoft Academic Search

Regulations governing the management and disposal of hazardous wastes have been promulgated by the US Environmental Protection Agency under authority of the Resource Conservation and Recovery Act. These were reviewed and compared with the available information on the properties and characteristics of low-level radioactive wastes (LLW). In addition, a survey was carried out to establish a data base on the

B. S. Bowerman; C. R. Kempf; D. R. MacKenzie; B. Siskind; P. L. Piciulo

1985-01-01

387

WASTE CONTAINER AND WASTE PACKAGE PERFORMANCE MODELING TO SUPPORT SAFETY ASSESSMENT OF LOW AND INTERMEDIATE-LEVEL RADIOACTIVE WASTE DISPOSAL  

Microsoft Academic Search

Prior to subsurface burial of low- and intermediate-level radioactive wastes, a demonstration that disposal of the wastes can be accomplished while protecting the health and safety of the general population is required. The long-time frames over which public safety must be insured necessitates that this demonstration relies, in part, on computer simulations of events and processes that will occur in

Terrence Sullivan

2004-01-01

388

Method for electrochemical decontamination of radioactive metal  

DOEpatents

A decontamination method for stripping radionuclides from the surface of stainless steel or aluminum material comprising the steps of contacting the metal with a moderately acidic carbonate/bicarbonate electrolyte solution containing sodium or potassium ions and thereafter electrolytically removing the radionuclides from the surface of the metal whereby radionuclides are caused to be stripped off of the material without corrosion or etching of the material surface.

Ekechukwu, Amy A. (Augusta, GA)

2008-06-10

389

Radioactive waste management system: Project Decision Schedule; Revision 1  

SciTech Connect

This is the first revision of the Project Decision Schedule (PDS) for the Civilian Radioactive Waste Management Program. The status date for milestones in the PDS is as of April 1991. This revision replaces the original PDS issued in March 1986. The PDS, which is required by Section 114(e) of the Nuclear Waste Policy Act (NWPA) of 1982, as amended, is to portray the optimum way to attain the operation of the repository. The PDS includes a description of objectives and a sequence of deadlines for all Federal agencies that are required to take action in achieving this goal. The activity deadlines in this issue of the PDS are based on the Nuclear Waste Policy Amendments Act of 1987 and the Office of Civilian Radioactive Waste Management`s Program Schedule Baseline. The Program Schedule Baseline supports the Secretary of Energy`s Report to Congress on Reassessment of the Civilian Radioactive Waste Management Program, November 1989. That report, among other things, contains the results of a comprehensive review of the schedule for repository-related activities, including a realistic assessment of activity durations and past experience. This schedule shows a significant slip for the expected start of repository operations -- from the year 2003 to approximately 2010. To promote the Department of Energy`s ability to achieve the new milestones and goals, the Secretary of Energy announced an action plan that centers on gaining access to the Yucca Mountain candidate site to continue the scientific investigations needed to evaluate the site`s suitability for a repository and on establishing integrated Monitored Retrievable Storage with a target for spent fuel acceptance in 1998. 5 figs., 6 tabs.

NONE

1991-06-01

390

Civilian radioactive waste management program plan. Revision 2  

SciTech Connect

This revision of the Civilian Radioactive Waste Management Program Plan describes the objectives of the Civilian Radioactive Waste management Program (Program) as prescribed by legislative mandate, and the technical achievements, schedule, and costs planned to complete these objectives. The Plan provides Program participants and stakeholders with an updated description of Program activities and milestones for fiscal years (FY) 1998 to 2003. It describes the steps the Program will undertake to provide a viability assessment of the Yucca Mountain site in 1998; prepare the Secretary of Energy`s site recommendation to the President in 2001, if the site is found to be suitable for development as a repository; and submit a license application to the Nuclear Regulatory Commission in 2002 for authorization to construct a repository. The Program`s ultimate challenge is to provide adequate assurance to society that an operating geologic repository at a specific site meets the required standards of safety. Chapter 1 describes the Program`s mission and vision, and summarizes the Program`s broad strategic objectives. Chapter 2 describes the Program`s approach to transform strategic objectives, strategies, and success measures to specific Program activities and milestones. Chapter 3 describes the activities and milestones currently projected by the Program for the next five years for the Yucca Mountain Site Characterization Project; the Waste Acceptance, Storage and Transportation Project; ad the Program Management Center. The appendices present information on the Nuclear Waste Policy Act of 1982, as amended, and the Energy Policy Act of 1992; the history of the Program; the Program`s organization chart; the Commission`s regulations, Disposal of High-Level Radioactive Wastes in geologic Repositories; and a glossary of terms.

NONE

1998-07-01

391

Radioactive wastes dispersed in stabilized ash cements  

SciTech Connect

One of the most widely-used methods for the solidification/stabilization of low-level radwaste is by incorporation into Type-I/II ordinary portland cement (OPC). Treating of OPC with supercritical fluid carbon dioxide (SCCO{sub 2}) has been shown to significantly increase the density, while simultaneously decreasing porosity. In addition, the process significantly reduces the hydrogenous content, reducing the likelihood of radiolytic decomposition reactions. This, in turn, permits increased actinide loadings with a concomitant reduction in disposable waste volume. In this article, the authors discuss the combined use of fly-ash-modified OPC and its treatment with SCCO{sub 2} to further enhance immobilization properties. They begin with a brief summary of current cement immobilization technology in order to delineate the areas of concern. Next, supercritical fluids are described, as they relate to these areas of concern. In the subsequent section, they present an outline of results on the application of SCCO{sub 2} to OPC, and its effectiveness in addressing these problem areas. Lastly, in the final section, they proffer their thoughts on why they believe, based on the OPC results, that the incorporation of fly ash into OPC, followed by supercritical fluid treatment, can produce highly efficient wasteforms.

Rubin, J.B.; Taylor, C.M.V.; Sivils, L.D.; Carey, J.W.

1997-12-31

392

Summary of radioactive solid waste received in the 200 Areas during calendar year 1988  

SciTech Connect

Westinghouse Hanford Company manages and operates the Hanford Sites 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy-Richland Operations Office under contract AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1988. 1 tab.

Anderson, J.D.; McCann, D.C.; Poremba, B.E.

1989-04-01

393

10 CFR 72.128 - Criteria for spent fuel, high-level radioactive waste, reactor-related greater than Class C waste...  

Code of Federal Regulations, 2010 CFR

...fuel, high-level radioactive waste, reactor-related greater than Class C waste...HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE...fuel, high-level radioactive waste, reactor-related greater than Class C...

2009-01-01

394

10 CFR 72.128 - Criteria for spent fuel, high-level radioactive waste, reactor-related greater than Class C waste...  

Code of Federal Regulations, 2010 CFR

...fuel, high-level radioactive waste, reactor-related greater than Class C waste...HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE...fuel, high-level radioactive waste, reactor-related greater than Class C...

2010-01-01

395

The performance assessment impacts of disposal of high-moisture, low-level radioactive waste at the Nevada Test Site  

SciTech Connect

A panel of independent scientists was convened by the Department of Energy to assess the performance impacts of disposal of low-level radioactive waste from the Fernald Environmental Management Project. This waste stream was involved in a transportation incident in December 1997. A resulting outgrowth of investigations of the transportation incident was the recognition that the waste was transported and disposed in stress-fractured metal boxes and some of the waste contained excess moisture (high volumetric water contents). The panel was charged with determining whether disposal of this waste in the Area 5 radioactive waste management site on the Nevada Test Site has impacted the conclusions of the completed performance assessment. Three questions were developed by the panel to assess performance impacts: (1) the performance impacts of reduced container integrity, (2) the impact of reduced container integrity on subsidence of waste in the disposal pits and (3) the performance impacts of excess moisture. No performance or subsidence impacts were noted from disposal of the Fernald waste. The impacts of excess moisture were assessed through simulation modeling of the movement of moisture in the vadose zone assuming high water contents (wet waste) for different percentages of the waste inventory. No performance impacts were noted for either the base-case scenario (ambient conditions) or a scenario involving subsidence and flooding of the waste cells. The absence of performance impacts results form the extreme conservatism used in the Area 5-performance assessment and the robust nature of the disposal site.

Crowe, B.M.; Hansen, W. [Los Alamos National Lab., NM (United States); Hechnova, A. [Univ. of Nevada, Las Vegas, NV (United States). Harry Reid Center of Environmental Studies; Jacobson, R. [Desert Research Inst., Reno, NV (United States); Voss, C. [Golder Associates, Inc. (United States); Waters, R. [Sandia National Labs., Albuquerque, NM (United States); Sully, M.; Levitt, D. [Bechtel Nevada, Las Vegas, NV (United States)

1999-03-01

396

Metal recycling from scrap and waste materials  

Microsoft Academic Search

Out of a total U.K. consumption of 2.5 million tonnes per annum of nonferrous metals, as much as 33% is recovered from scrap. The structure of the industry which makes this important contribution to the economy is briefly outlined, and the technology is described by which the various nonferrous metals are recovered in reusable form from waste materials. Data on

A. W. Fletcher

1976-01-01

397

An evaluation of air effluent and workplace radioactivity monitoring at the Waste Isolation Pilot Plant  

Microsoft Academic Search

Improvements are needed in the Waste Isolation Pilot Plant (WIPP) air effluent and workplace radioactivity monitoring prior to receipt of radioactive wastes. This report provides a detailed review Zf radioactivity air monitoring regulatory requirements and related facility design requirements. Air monitoring data, supplied by the Westinghouse Isolation Division, are analyzed. The WIPP Final Safety Analysis Report (FSAR) requires that the

Bartlett

1993-01-01

398

A survey of radioactive waste disposal arrangements in UK hospitals and medical research institutions  

Microsoft Academic Search

The disposal of radioactive waste into the environment is of public interest. The individual discharges of radionuclides from medical institutions are relatively small but the number of such discharges are quite large and the levels of radioactivity discharged to the environment may be readily measured. The aim of this survey is to demonstrate the variation in the radioactive waste that

S. Batchelor; C. Baldock; J. E. Saunders

1991-01-01

399

Autoclave inactivation of infectious radioactive laboratory waste contained within a charcoal filtration system  

Microsoft Academic Search

A model system was developed previously for disposal of solid laboratory waste that is both radioactive and heat sensitive, e.g., HIV. A double polypropylene bag with charcoal vent filter and absorbent was designed to meet requirements for both steam sterilization and disposal as solid radioactive waste. Earlier work demonstrated the effective containment of radioactive gases by the filter and inactivation

Margaret C. Stinson; Barbara L. Green; Charles J. Marquardt; Alan M. Ducatman

1991-01-01

400

Method for ultimate disposition of borate containing radioactive wastes by vitrification  

US Patent & Trademark Office Database

Method for the ultimate disposition of radioactive wastes by vitrification, in which weak to medium radioactive waste concentrates from borate-containing radioactive liquids are mixed with added glass-forming materials, maximally in a ratio of 1:3, and the mixture heated to obtain a glass-forming melt.

Bege; Dietmar (Erlangen, DE); Faust; Hans-Joachim (Grossgeschaid, DE); Puthawala; Anwer (Erlangen, DE); Stu/ nkel; Helmut (Erlangen, DE)

1984-01-03

401

10 CFR 72.108 - Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste...  

Code of Federal Regulations, 2013 CFR

...high-level radioactive waste, or reactor-related greater than Class C waste...108 Section 72.108 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED...HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C...

2013-01-01

402

Method for recovering metals from waste  

DOEpatents

A method for recovering metals from metals-containing wastes, and vitrifying the remainder of the wastes for disposal. Metals-containing wastes such as circuit boards, cathode ray tubes, vacuum tubes, transistors and so forth, are broken up and placed in a suitable container. The container is heated by microwaves to a first temperature in the range of approximately 300.degree.-800.degree. C. to combust organic materials in the waste, then heated further to a second temperature in the range of approximately 1,000.degree.-1,550.degree. C. at which temperature glass formers present in the waste will cause it to melt and vitrify. Low-melting-point metals such as tin and aluminum can be recovered after organics combustion is substantially complete. Metals with higher melting points, such as gold, silver and copper, can be recovered from the solidified product or separated from the waste at their respective melting points. Network former-containing materials can be added at the start of the process to assist vitrification.

Wicks, George G. (North Augusta, SC); Clark, David E. (Gainesville, FL); Schulz, Rebecca L. (Gainesville, FL)

1998-01-01

403

Method for recovering metals from waste  

DOEpatents

A method for recovering metals from metals-containing wastes, and vitrifying the remainder of the wastes for disposal. Metals-containing wastes such as circuit boards, cathode ray tubes, vacuum tubes, transistors and so forth, are broken up and placed in a suitable container. The container is heated by microwaves to a first temperature in the range of approximately 300-800.degree. C. to combust organic materials in the waste, then heated further to a second temperature in the range of approximately 1,000-1,550.degree. C. at which temperature glass formers present in the waste will cause it to melt and vitrify. Low-melting-point metals such as tin and aluminum can be recovered after organics combustion is substantially complete. Metals with higher melting points, such as gold, silver and copper, can be recovered from the solidified product or separated from the waste at their respective melting points. Network former-containing materials can be added at the start of the process to assist vitrification.

Wicks, George G. (North Augusta, SC); Clark, David E. (Gainesville, FL); Schulz, Rebecca L. (Gainesville, FL)

2000-01-01

404

Method for recovering metals from waste  

DOEpatents

A method is described for recovering metals from metals-containing wastes, and vitrifying the remainder of the wastes for disposal. Metals-containing wastes such as circuit boards, cathode ray tubes, vacuum tubes, transistors and so forth, are broken up and placed in a suitable container. The container is heated by microwaves to a first temperature in the range of approximately 300--800 C to combust organic materials in the waste, then heated further to a second temperature in the range of approximately 1,000--1,550 C at which temperature glass formers present in the waste will cause it to melt and vitrify. Low-melting-point metals such as tin and aluminum can be recovered after organics combustion is substantially complete. Metals with higher melting points, such as gold, silver and copper, can be recovered from the solidified product or separated from the waste at their respective melting points. Network former-containing materials can be added at the start of the process to assist vitrification. 2 figs.

Wicks, G.G.; Clark, D.E.; Schulz, R.L.

1998-12-01

405

Glass matrices for vitrification of radioactive waste - an Update on R & D Efforts  

NASA Astrophysics Data System (ADS)

Radioactive waste gets generated at different stages of nuclear fuel cycle like mining/milling, fuel fabrication, reactor operation, reprocessing of spent fuel and the production & application of radioisotopes for various industrial, medical and research purposes. High Level radioactive Waste (HLW) is generated during reprocessing of spent nuclear fuel and it contains most of the radioactivity present in entire fuel cycle. Vitrification of HLW in borosilicate matrix is being practiced using induction heated metallic melters at industrial scale plants at Tarapur and Trombay [1]. The nature of HLW largely depends on off - reactor cooling of spent nuclear fuel, its type and burn - up, and reprocessing flow sheet. In view of varying characteristics, processing of HLW at Tarapur and Trombay has offered a wide spectrum of challenges in terms of development of matrices and characterization to accommodate compositional changes in waste. The present paper summarizes details of extensive R and D efforts made in the Department of Atomic Energy towards development and characterization of glass formulations for immobilization of HLW.

Raj, Kanwar; Kaushik, C. P.

2009-07-01

406

Evaluation of platinum alloy melters for vitrification of radioactive wastes  

SciTech Connect

A bushing melter constructed of platinum-rhodium is being evaluated for vitrification of special high gamma radioactive wastes for long-term recoverable storage. The basic design parallels that used in the fiberglass industry. Nonradioactive chemical surrogate wastes have been used in the process work. The simulant wastes and glass frit are fed separately to the melter and mixed within the liquefied mass. Several different frits have been used, and temperatures have been varied to assess the effects on the quality of the product glasses. Melt temperatures >1500{degrees}C are typical, and significant effects on the material of construction are evident. Analyses of the Pt-Rh materials have been used to emphasize the need to set limits in the operating parameters to avoid unacceptable changes in properties of the bushing as a container.

Jenkins, C.F. [Westinghouse Savannah River Co., Aiken, SC (United States)

1997-12-01

407

Separation processes for high-level radioactive waste treatment  

SciTech Connect

During World War II, production of nuclear materials in the United States for national defense, high-level waste (HLW) was generated as a byproduct. Since that time, further quantities of HLW radionuclides have been generated by continued nuclear materials production, research, and the commercial nuclear power program. In this paper HLW is defined as the highly radioactive material resulting from the processing of spent nuclear fuel. The HLW is the liquid waste generated during the recovery of uranium and plutonium in a fuel processing plant that generally contains more than 99% of the nonvolatile fission products produced during reactor operation. Since this paper deals with waste separation processes, spent reactor fuel elements that have not been dissolved and further processed are excluded.

Sutherland, D.G.

1992-11-01

408

Monitoring technologies for ocean disposal of radioactive waste  

SciTech Connect

The feasibility of using carefully selected subseabed locations to permanently isolate high level radioactive wastes at ocean depths greater than 4000 meters is discussed. Disposal at several candidate subseabed areas is being studied because of the long term geologic stability of the sediments, remoteness from human activity, and lack of useful natural resources. While the deep sea environment is remote, it also poses some significant challenges for the technology required to survey and monitor these sites, to identify and pinpoint container leakage should it occur, and to provide the environmental information and data base essential to determining the probable impacts of any such occurrence. Objectives and technical approaches to aid in the selective development of advanced technologies for the future monitoring of nuclear low level and high level waste disposal in the deep seabed are presented. Detailed recommendations for measurement and sampling technology development needed for deep seabed nuclear waste monitoring are also presented.

Triplett, M.B.; Solomon, K.A.; Bishop, C.B.; Tyce, R.C.

1982-01-01

409

Heavy metals, organics and radioactivity in soil of western Serbia  

Microsoft Academic Search

Western Serbia is a region well-known for potato production. Concentrations of selected metals, polycyclic aromatic hydrocarbons (PAHs) and radioactivity were measured in the soil in order to evaluate the quality and characteristics. The examined soils (Luvisol and Pseudogley) showed unsuitable agrochemical characteristics (acid reaction, low content of organic matter and potassium). Some samples contained Ni, Mn and Cr above the

Goran Dugalic; Dragana Krstic; Miodrag Jelic; Dragoslav Nikezic; Biljana Milenkovic; Mira Pucarevic; Tijana Zeremski-Skoric

2010-01-01

410

A Challenge for Radioactive Waste Management: Memory Preservation  

SciTech Connect

ANDRA, the French National Radioactive Waste Management Agency, is responsible for managing all radioactive waste in France over the long term. In the case of short-lived waste for which disposal facilities have a life expectancy of a few centuries, the Agency has set up a system for preserving the memory of those sites. Based on the historical analysis on a comparable timescale and on an appraisal of information-conservation means, a series of regulatory as well as technical provisions was made in order to ensure that sound information be transmitted to future generations. Requirements associated to the provisions deal mostly with legibility and a clear understanding of the information that must be decrypted and understood at least during the lifetime of the facilities (i.e., a few centuries). It must therefore be preserved throughout the same period. Responses to the requirements will be presented notably on various information-recording media, together with the information-diffusion strategy to the different authorities and structures within French society. A concrete illustration of the achievements made so far is the Centre de la Manche Disposal Facility, which was closed down in 1994 and is currently in its post-closure monitoring phase since 2003. In the case of deep geological repositories for long-lived radioactive waste, preserving memory takes a different aspect. First of all, timescales are much longer and are counted in hundreds of thousands of years. It is therefore much more difficult to consider how to maintain the richness of the information over such time periods than it is for short-lived waste. Both the nature and the form of the information to be transmitted must be revised. It would be risky indeed to base memory preservation over the long term on similar mechanisms beyond 1,000 years. Based on the heritage of a much more ancient history, we must seek to find appropriate means in order to develop surface markers and even more to ensure their conservation over compatible timescales with those of deep geological repositories. It will also be necessary, in the light of the experiments and efforts made in order to decrypt the messages written on rupestral paintings or in pyramids, find suitable expression means that will help, not the next few generations, but much more future generations, to grasp the meaning of what we aim at transmitting them. This paper presents the state of the French reflection on memory preservation and transmission over the very long term, for timescales consistent with the long-lived radioactive geological waste disposal projects. (author)

Charton, P.; Ouzounian, G. [Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA), 92 - Chatenay Malabry (France)

2008-07-01

411

CHARACTERIZATION OF HIGH PHOSPHATE RADIOACTIVE TANK WASTE AND SIMULANT DEVELOPMENT  

SciTech Connect

A sample of high-level radioactive tank waste was characterized to provide a basis for developing a waste simulant. The simulant is required for engineered-scaled testing of pretreatment processes in a non-radiological facility. The waste material examined was derived from the bismuth phosphate process, which was the first industrial process implemented to separate plutonium from irradiated nuclear fuel. The bismuth phosphate sludge is a complex mixture rich in bismuth, iron, sodium, phosphorus, silicon, and uranium. The form of phosphorus in this particular tank waste material is of specific importance because that is the primary component (other than water-soluble sodium salts) that must be removed from the high-level waste solids by pretreatment. This work shows unequivocally that the phosphorus present in this waste material is not present as bismuth phosphate. Rather, the phosphorus appears to be incorporated mostly into an amorphous iron(III) phosphate species. The bismuth in the sludge solids is best described as bismuth ferrite, BiFeO3. Infrared spectral data, microscopy, and thermal analysis data are presented to support these conclusions. The behavior of phosphorus during caustic leaching of the bismuth phosphate sludge solids is also discussed.

Lumetta, Gregg J.; McNamara, Bruce K.; Buck, Edgar C.; Fiskum, Sandra K.; Snow, Lanee A.

2009-10-15

412

A MODULAR STORE FOR DRUMS OF RADIOACTIVE WASTE  

SciTech Connect

Currently, the United Kingdom has no facility for the disposal of any waste above the low level category, indicating that all intermediate and high level waste, apart from spent fuel, has to be stored on the site of origin. To meet this storage requirement, nuclear sites are resorting to converting existing buildings or contemplating the construction of dedicated facilities, resulting in considerable cost implications. These financing aspects not only concern the construction strategy but also impinge on the ultimate decommissioning costs associated with each particular nuclear site. This paper reports on an investigation to apply the commercially available interlocking hollow block system to the design of a store for drums of radioactive waste. This block system can be quickly, and cost effectively, erected and filled with a choice of dense material. Later, the store can be dismantled with a minimum of disposable radioactive waste and the complete facility re - erected at another location if required, considerably reducing both capital construction and decommissioning costs. The investigation also encompassed a detailed review of the equipment required to place the drums of waste into the store, resulting in a scheme for a remotely operated vehicle that did not rely on umbilical control cables. The drum handler design included for 100% redundancy of all functions, meaning that whichever component failed, the handler was always recoverable to effect the necessary repair. The ultimate aim of the waste drum store review was to produce a facility that was as safe as a conventionally constructed unit, but at a lower overall building and decommissioning cost.

Sims, J.; Holden, G.

2003-02-27

413

Microcomputer spreadsheets for radioactive waste management and shielding analysis  

SciTech Connect

The report describes several desktop computer applications for use in radioactive waste management and radiation engineering analyses. TMI-2 engineers identified eight calculational tasks that could be facilitated by use of microcomputer spreadsheet software. For each case, appropriate calculations and frequently used data on isotopes and materials were built into the six spreadsheet templates for calculating and thirty-one data sets. The spreadsheets are distributed on diskette to avoid the need for re-input by the user. The applications include: (1) calculation of radioactive decay for a specific time interval for often found radionuclides and their daughter radioisotopes; (2) determination of the disposability of a waste container by calculating the 10CFR61 sum-of-the-fractions concentrations; (3) estimation of the cost of a waste disposal campaign; (4) projection of the rate of hydrogen gas generation in waste liners; (5) calculation of the dose rate from a point source; and (6) inferring the radioisotopic contents of a waste container from the external radiation, and vice versa. This set of microcomputer spreadsheet applications was selected for inclusion as part of EPRI's task of transferring technology developed at TMI-2 to the industry. Waste management is a concern to all plant operators. Microcomputers are used for a variety of evaluation and recordkeeping tasks. Increasing their usefulness to engineers by tools such as these spreadsheets serves to relieve analysts of calculational tasks. As the report provides background and development histories, and the spreadsheets are presented on diskette, the product can be used as a training tool as well.

Negin, C.A.; Worku, G.; Urland, C.S.; Deltete, C.P.

1986-09-01

414

Summary of radioactive solid waste received in the 200 areas during calendar year 1997  

SciTech Connect

Waste Management Federal Services of Hanford Inc. manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office under contract DE-AC06-87RL10930. These facilities include storage areas and disposal sites for radioactive solid waste. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1997. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Cafeteria, liquid waste data are not included in this document.

Hagel, D.L.

1998-06-25

415

A Probabilistic Performance Assessment Study of Potential Low-Level Radioactive Waste Disposal Sites in Taiwan  

Microsoft Academic Search

For several years now, Taiwan has been engaged in a process to select a low-level radioactive waste (LLW) disposal site. Taiwan is generating LLW from operational and decommissioning wastes associated with nuclear power reactors, as well as research, industrial, and medical radioactive wastes. The preliminary selection process has narrowed the search to four potential candidate sites. These sites are to

R. G. Knowlton; B. W. Arnold; P. D. Mattie; M. Kuo; N. Tien

2006-01-01

416

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

SciTech Connect

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

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

1999-08-01

417

Analysis of shallow soil moisture flux adjacent to the Area 5 radioactive waste management site  

Microsoft Academic Search

Hazardous waste requires significant isolation from the biosphere. Shallow land burial of radioactive waste is currently employed at Area 5 of the Nevada Test Site to prevent release of impounded radioactive materials. Soil covers have been proposed to limit the infiltration of precipitation into the waste. Appropriate design for these covers depends on knowledge of infiltration in the soils intended

William Albright; Scott Tyler; Sam Hokett

1997-01-01

418

Mixing Effects on the Precipitation and Cross Flows Filtration of a Hanford Simulated Precipitated Radioactive Waste  

Microsoft Academic Search

As part of the River Protection Project at Hanford, Washington, Bechtel National, Inc. has been contracted by the United States Department of Energy to design a Waste Treatment and Immobilization Plant to stabilize liquid radioactive waste. Because of its experience with radioactive waste stabilization, the Savannah River Technology Center of the Westinghouse Savannah River Company is working with Bechtel National

2004-01-01

419

Metal-ion recycle technology for metal electroplating waste waters  

SciTech Connect

As a result of a collaboration with Boeing Aerospace, the authors have begun a program to identify suitable treatments or to develop new treatments for electroplating baths. The target baths are mixed-metal or alloy baths that are being integrated into the Boeing electroplating complex. These baths, which are designed to replace highly toxic chromium and cadmium baths, contain mixtures of two metals, either nickel-tungsten, nickel-zinc, or zinc-tin. This report reviews the literature and details currently available on emerging technologies that could affect recovery of metals from electroplating baths under development by Boeing Aerospace. This literature survey summarizes technologies relevant to the recovery of metals from electroplating processes. The authors expanded the scope to investigate single metal ion recovery technologies that could be applied to metal ion recovery from alloy baths. This review clearly showed that the electroplating industry has traditionally relied on precipitation and more recently on electrowinning as its waste treatment methods. Despite the almost ubiquitous use of precipitation to remove contaminant metal ions from waste electroplating baths and rinse waters, this technology is clearly no longer feasible for the electroplating industry for several reasons. First, disposal of unstabilized sludge is no longer allowed by law. Second, these methods are no longer adequate as metal-removal techniques because they cannot meet stringent new metal discharge limits. Third, precious resources are being wasted or discarded because these methods do not readily permit recovery of the target metal ions. As a result, emerging technologies for metal recovery are beginning to see application to electroplating waste recycle. This report summarizes current research in these areas. Included are descriptions of various membrane technologies, such as reverse osmosis and ultrafiltration, ion exchange and chelating polymer technology, and electrodialysis.

Sauer, N.N.; Smith, B.F.

1993-06-01

420

78 FR 53793 - Request To Amend a License To Export Radioactive Waste  

Federal Register 2010, 2011, 2012, 2013

...REGULATORY COMMISSION Request To Amend a License To Export Radioactive Waste Pursuant to 10 CFR 110.70 (b) ``Public Notice...Foreign XW012/04..................... radioactive tons of low- Consignee(s).'' No other...

2013-08-30

421

76 FR 56489 - Request for a License To Export Radioactive Waste  

Federal Register 2010, 2011, 2012, 2013

...NUCLEAR REGULATORY COMMISSION Request for a License To Export Radioactive Waste Pursuant to 10 CFR 110.70 (b) ``Public Notice...Duratek Services, Inc., August Class A radioactive Radionuclide Non-conforming Canada. 17, 2011,...

2011-09-13

422

78 FR 53793 - Request To Amend a License To Import Radioactive Waste  

Federal Register 2010, 2011, 2012, 2013

...REGULATORY COMMISSION Request To Amend a License To Import Radioactive Waste Pursuant to 10 CFR 110.70 (b) ``Public Notice...No IW022/04..................... radioactive tons of low- other changes to the existing...

2013-08-30

423

78 FR 9747 - Request To Amend A License To Import; Radioactive Waste  

Federal Register 2010, 2011, 2012, 2013

...REGULATORY COMMISSION Request To Amend A License To Import; Radioactive Waste Pursuant to 10 CFR 110.70 (b) ``Public Notice...Diversified Scientific Class A radioactive Up to 378,000 Volume reduction...... Canada...

2013-02-11

424

Bonding material containing ashes after domestic waste incineration for cementation of radioactive waste  

SciTech Connect

It is known that cement minerals hydration is accompanied with heat emission. Heat of hardening influences formation of a cement compound structure and its properties. It is important to reduce the heat quantity at continuous cementation of waste and filling of compartments of a repository or containers by a cement grout. For reduction of heating, it is necessary to use cement of mineral additives (fuel ashes, slag and hydraulic silica). Properties of ashes after domestic waste incineration can be similar to ones of fly fuel ashes. However, ash after domestic waste incineration is toxic industrial waste as it contains toxic elements (As, Cd, Hg, Pb, Sb, Zn). Utilization of secondary waste (slag and ash) of combustion plants is an important environmental approach to solving cities' issues. Results of the research have shown that ashes of combustion plants can be used for radioactive waste conditioning. Co-processing of toxic and radioactive waste is ecologically and economically effective. At SIA 'Radon', experimental batches of cement compositions are used for cementation of oil containing waste. (authors)

Dmitriev, S.A.; Varlakov, A.P.; Gorbunova, O.A.; Arustamov, A.E.; Barinov, A.S. [Moscow Scientific and Industrial Association 'Radon', 7th Rostovsky Lane 2/14, 119121, Moscow (Russian Federation)

2007-07-01

425

Low-level radioactive waste volume reduction and stabilization technologies resource manual: National Low-Level Radioactive Waste Management Program  

SciTech Connect

This manual on volume reduction and stabilization technologies is intended to serve as a resource document to policy personnel at the state or regional level. The manual provides concise descriptions of currently available and promising methods of volume reduction and stabilization of low-level radioactive waste. Technologies in this manual include cement solidification, bituminization, evaporation, incineration, high-integrity containerization, shredding, and compaction and supercompaction. Each technology is discussed in detail in relation to how the technology works, its suitability for specific waste types, volume reduction factors typically obtainable, costs, its applicability to treatment of mixed waste, its commercial availability and its history of use. An annotated bibliography is included to allow for further independent research on the technologies. 78 refs., 19 figs., 34 tabs.

Not Available

1988-12-01

426

Summary of radioactive solid waste received in the 200 Areas during calendar year 1989  

SciTech Connect

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy-Richland Operations Office under contract AC06-87RL10930. These facilities include radioactive solid waste disposal sites and radioactive solid waste storage areas. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities since startup in 1944 through calendar year 1989. This report does not include solid radioactive wastes in storage or disposal in other facilities or areas such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, liquid waste data is not included in this document. 1 tab.

Anderson, J.D.; McCann, D.C.; Poremba, B.E.

1990-04-01

427

Method for acid oxidation of radioactive, hazardous, and mixed organic waste materials  

DOEpatents

The present invention is directed to a process for reducing the volume of low level radioactive and mixed waste to enable the waste to be more economically stored in a suitable repository, and for placing the waste into a form suitable for permanent disposal. The invention involves a process for preparing radioactive, hazardous, or mixed waste for storage by contacting the waste starting material containing at least one organic carbon-containing compound and at least one radioactive or hazardous waste component with nitric acid and phosphoric acid simultaneously at a contacting temperature in the range of about 140.degree. C. to about 210 .degree. C. for a period of time sufficient to oxidize at least a portion of the organic carbon-containing compound to gaseous products, thereby producing a residual concentrated waste product containing substantially all of said radioactive or inorganic hazardous waste component; and immobilizing the residual concentrated waste product in a solid phosphate-based ceramic or glass form.

Pierce, Robert A. (Aiken, SC); Smith, James R. (Corrales, NM); Ramsey, William G. (Aiken, SC); Cicero-Herman, Connie A. (Aiken, SC); Bickford, Dennis F. (Folly Beach, SC)

1999-01-01

428

Characteristics of wasteform composing of phosphate and silicate to immobilize radioactive waste salts.  

PubMed

In the radioactive waste management, metal chloride wastes from a pyrochemical process is one of problematic wastes not directly applicable to a conventional solidification process. Different from a use of minerals or a specific phosphate glass for immobilizing radioactive waste salts, our research group applied an inorganic composite, SAP (SiO(2)-Al(2)O(3)-P(2)O(5)), to stabilize them by dechlorination. From this method, a unique wasteform composing of phosphate and silicate could be fabricated. This study described the characteristic of the wasteform on the morphology, chemical durability, and some physical properties. The wasteform has a unique "domain-matrix" structure which would be attributed to the incompatibility between silicate and phosphate glass. At higher amounts of chemical binder, "P-rich phase encapsulated by Si-rich phase" was a dominant morphology, but it was changed to be Si-rich phase encapsulated by P-rich phase at a lower amount of binder. The domain and subdomain size in the wasteform was about 0.5-2 ?m and hundreds of nm, respectively. The chemical durability of wasteform was confirmed by various leaching test methods (PCT-A, ISO dynamic leaching test, and MCC-1). From the leaching tests, it was found that the P-rich phase had ten times lower leach-resistance than the Si-rich phase. The leach rates of Cs and Sr in the wasteform were about 10(-3)g/m(2) day, and the leached fractions of them were about 0.04% and 0.06% at 357 days, respectively. Using this method, we could stabilize and solidify the waste salt to form a monolithic wasteform with good leach-resistance. Also, the decrease of waste volume by the dechlorination approach would be beneficial in the final disposal cost, compared with the present immobilization methods for waste salt. PMID:21288037

Park, Hwan-Seo; Cho, In-Hak; Eun, Hee Chul; Kim, In-Tae; Cho, Yong Zun; Lee, Han-Soo

2011-02-02

429

Fifty years of federal radioactive waste management: Policies and practices  

SciTech Connect

This report provides a chronological history of policies and practices relating to the management of radioactive waste for which the US Atomic Energy Commission and its successor agencies, the Energy Research and Development Administration and the Department of Energy, have been responsible since the enactment of the Atomic Energy Act in 1946. The defense programs and capabilities that the Commission inherited in 1947 are briefly described. The Commission undertook a dramatic expansion nationwide of its physical facilities and program capabilities over the five years beginning in 1947. While the nuclear defense activities continued to be a major portion of the Atomic Energy Commission`s program, there was added in 1955 the Atoms for Peace program that spawned a multiplicity of peaceful use applications for nuclear energy, e.g., the civilian nuclear power program and its associated nuclear fuel cycle; a variety of industrial applications; and medical research, diagnostic, and therapeutic applications. All of these nuclear programs and activities generated large volumes of radioactive waste that had to be managed in a manner that was safe for the workers, the public, and the environment. The management of these materials, which varied significantly in their physical, chemical, and radiological characteristics, involved to varying degrees the following phases of the waste management system life cycle: waste characterization, storage, treatment, and disposal, with appropriate transportation linkages. One of the benefits of reviewing the history of the waste management program policies and practices if the opportunity it provides for identifying the lessons learned over the years. Examples are summarized at the end of the report and are listed in no particular order of importance.

Bradley, R.G.

1997-04-01

430

Regulatory Approaches for Solid Radioactive Waste Storage in Russia  

SciTech Connect

The Russian Navy under the Arctic Military Environmental Cooperation (AMEC) Program has designated the Polyarninsky Shipyard as the regional recipient for solid radioactive waste (SRW) pretreatment and storage facilities. Waste storage technologies include containers and lightweight modular storage buildings. The prime focus of this paper is solid radioactive waste storage options based on the AMEC mission and Russian regulatory standards. The storage capability at the Polyarninsky Shipyard in support of Mobile Pretreatment Facility (MPF) operations under the AMEC Program will allow the Russian Navy to accumulate/stage the SRW after treatment at the MPF. It is anticipated that the MPF will operate for 20 years. This paper presents the results of a regulatory analysis performed to support an AMEC program decision on the type of facility to be used for storage of SRW. The objectives the study were to: analyze whether a modular storage building (MSB), referred in the standards as a lightweight building, would comply with the Russian SRW storage building standard, OST 95 10517-95; analyze the Russian SRW storage pad standard OST 95 10516-95; and compare the two standards, OST 95 10517-95 for storage buildings and OST 95 10516-95 for storage pads.

Griffith, A.; Testov, S.; Diaschev, A.; Nazarian, A.; Ustyuzhanin, A.

2003-02-26

431

Polyfunctional microspherical materials for long-term disposal of liquid radioactive wastes  

Microsoft Academic Search

The possibility of immobilizing liquid radioactive wastes into polyfunctional microspherical materials of the block and powdered\\u000a types is demonstrated. These materials are intended for reprocessing radioactive wastes of different compositions and make\\u000a it possible to perform a multistage process of conditioning radioactive wastes under relatively mild conditions (at temperatures\\u000a below 1000C) with the conversion of water-soluble cesium and strontium compounds

T. A. Vereshchagina; N. N. Anshits; O. M. Sharonova; N. G. Vasileva; S. N. Vereshchagin; N. N. Shishkina; E. V. Fomenko; A. G. Anshits

2008-01-01

432

Improvements in Container Management of Transuranic and Low-Level Radioactive Waste Stored at the Central Waste Complex at Hanford  

Microsoft Academic Search

The Central Waste Complex (CWC) is the interim storage facility for Resource Conservation and Recovery Act (RCRA) mixed waste, transuranic waste, transuranic mixed waste, low-level and low-level mixed radioactive waste at the Department of Energy's (DOE's) Hanford Site. The majority of the waste stored at the facility is retrieved from the low-level burial grounds in the 200 West Area at

E. Uytioco; P. A. Baynes; K. B. Bailey; D. E. McKenney

2008-01-01

433

FINAL DISPOSAL OF RADIOACTIVE WASTE IN GERMANY: PLAN APPROVAL PROCESS OF KONRAD MINE AND ACCEPTANCE REQUIREMENTS  

SciTech Connect

Currently no final repository for any type of radioactive waste is operated in Germany. Preliminary Final Storage Acceptance Requirements for radioactive waste packages were published in 1995. Up to now these are the basis for treatment of radioactive waste in Germany. After licensing of the final repository these preliminary waste acceptance requirements are completed with licensing conditions. Some of these conditions affect the preliminary waste acceptance requirements, e. g. behavior of chemo-toxic substances in case of accidents in the final repository or the allowed maximum concentration of fissile material. The presented examples of radioactive waste conditioning campaigns demonstrate that no difficulties are expected in management, characterization and quality assurance of radioactive wastes due to the licensing conditions.

Bandt, Gabriele; Posnatzki, Britta; Beckers, Klaus-Arno

2003-02-27

434

Summary of radioactive solid waste received in the 200 areas during calendar year 1996  

SciTech Connect

Rust Federal Services of Hanford Inc. manages and operates the Hanford Site 200 Area radioactive solid waste storage and disposal facilities for the US Department of Energy, Richland Operations Office under contract DE-AC06-87RL10930. These facilities include storage areas and disposal sites for radioactive solid waste. This document summarizes the amount of radioactive materials that have been buried and stored in the 200 Area radioactive solid waste storage and disposal facilities from startup in 1944 through calendar year 1996. This report does not include backlog waste, solid radioactive wastes in storage or disposed of in other areas, or facilities such as the underground tank farms. Unless packaged within the scope of WHC-EP-0063, Hanford Site Solid Waste Acceptance Criteria, liquid waste data are not included in this document.

Hladek, K.L.

1997-05-21

435

Handling and Treatment of Uranium Contaminated Combustible Radioactive Low Level Waste (LLW)  

SciTech Connect

Studsvik RadWaste in Sweden has many years of experience in handling of low-level radioactive waste, such as burnable waste for incineration and scrap metal for melting. In Erwin, TN, in the USA, Studsvik Inc also operates a THOR (pyrolysis) facility for treatment of various kinds of ion-exchange resins. The advantage of incineration of combustible waste as well as of ion-exchange resins by pyrolysis, is the vast volume reduction which minimizes the cost for final storage and results in an inert end-product which is feasible for safe final disposal. The amount of uranium in the incinerable waste has impact on the quality of the resulting ash. The quality improves with lower U-content. One way of reducing the Ucontent is leaching using a chemical process before and if necessary also after the incineration. Ranstad Mineral AB has been established in the 1960s to support the Swedish national program for uranium mining in southern Sweden. Ranstad Mineral works among others wit h chemical processes to reduce uranium content by leaching. During 1998-2000 about 150 tons/year have been processed. The goal was to reach uranium residues of less than 0.02% for disposal on the municipal waste disposal.

Lorenzen, J,; Lindberg, M.; Luvstrand, J.

2002-02-26

436

Engineering Deinococcus geothermailis for Bioremediation of High-Temperature Radioactive Waste Environments  

SciTech Connect

Deinococcus geothermalis is an extremely radiation-resistant thermophilic bacterium closely related to the mesophile Deinococcus radiodurans, which is being engineered for in situ bioremediation of radioactive wastes.

Brim, Hassan; Venkateswaran, Amudhan; Kostandarithes, Heather M.; Fredrickson, Jim K.; Daly, Michael J.

2003-08-01

437

Report to Congress: 1995 Annual report on low-level radioactive waste management progress  

SciTech Connect

This report is prepared in response to the Low-Level Radioactive Waste Policy Act, Public Law 96-573, 1980, as amended by the Low-Level Radioactive Waste Policy Amendments Act of 1985, Public Law 99-240. The report summarizes the progress of states and compact regions during calendar year 1995 in establishing new disposal facilities for commercially-generated low-level radioactive waste. The report emphasizes significant issues and events that have affected progress, and also includes an introduction that provides background information and perspective on United States policy for low-level radioactive waste disposal.

NONE

1996-06-01

438

1996 annual report on low-level radioactive waste management progress. Report to Congress  

SciTech Connect

This report is prepared in response to the Low-Level Radioactive Waste Policy Act (the Act), Public Law 96-573, 1980, as amended by the Low-Level Radioactive Waste Policy Amendments Act of 1985, Public Law 99-240. The report summarizes the activities during calendar year 1996 related to the establishment of new disposal facilities for commercially-generated low-level radioactive waste. The report emphasizes significant issues and events that have affected progress in developing new disposal facilities, and also includes an introduction that provides background information and perspective on US policy for low-level radioactive waste disposal.

NONE

1997-11-01

439

Vapor sampling of the headspace of radioactive waste storage tanks  

SciTech Connect

This paper recants the history of vapor sampling in the headspaces of radioactive waste storage tanks at Hanford. The first two tanks to receive extensive vapor pressure sampling were Tanks 241-SY-101 and 241-C-103. At various times, a gas chromatography, on-line mass spectrometer, solid state hydrogen monitor, FTIR, and radio acoustic ammonia monitor have been installed. The head space gas sampling activities will continue for the next few years. The current goal is to sample the headspace for all the tanks. Some tank headspaces will be sampled several times to see the data vary with time. Other tanks will have continuous monitors installed to provide additional data.

Reynolds, D.A., Westinghouse Hanford

1996-05-22

440

Nondestructive examination technologies for inspection of radioactive waste storage tanks  

SciTech Connect

The evaluation of underground radioactive waste storage tank structural integrity poses a unique set of challenges. Radiation fields, limited access, personnel safety and internal structures are just some of the problems faced. To examine the internal surfaces a sensor suite must be deployed as an end effector on a robotic arm. The purpose of this report is to examine the potential failure modes of the tanks, rank the viability of various NDE technologies for internal surface evaluation, select a technology for initial EE implementation, and project future needs for NDE EE sensor suites.

Anderson, M.T.; Kunerth, D.C.; Davidson, J.R.

1995-08-01

441

Highly refractory glass-ceramics suitable for incorporating radioactive wastes  

SciTech Connect

This invention is concerned with the production of glass ceramics especially suitable for incorporating radioactive wastes. The inventive glass-ceramics contain at least two crystal phases selected from the group of pollucite, mullite, monazite, and, optionally, tetragonal or cubic zirconia as the predominant crystal phases and consist essentially, expressed in weight percent on the oxide basis, of 5-40% cs2o, 15-50% al2o3, 0-30% la2o3+ceo2, 0-20% p2o5, 0-30% zro2, 12-65% la2o3+ceo2+p2o5, and 15-50% sio

Beall, G.H.; Rittler, H.L.

1982-02-09

442

Interactions of low-level, liquid radioactive wastes with soils. 1. Behavior of radionuclides in soil-waste systems  

Microsoft Academic Search

The characteristics of radioactive wastes and soils vary over a wide range. Liquid radioactive waste entering the environment will eventually contact the soil or geological matrix; interactions will be determined by the chemical and physical nature of the liquid, as well as the soil matrix. We report here the results from an investigation of certain of those characteristics as they

E. B. Fowler; E. H. Essington; W. L. Polzer

1981-01-01

443

Radioactive waste disposal implications of extending Part IIA of the Environmental Protection Act to cover radioactively contaminated land  

Microsoft Academic Search

A short study has been carried out of the potential radioactive waste disposal issues associated with the proposed extension of Part IIA of the Environmental Protection Act 1990 to include radioactively contaminated land, where there is no other suitable existing legislation. It was found that there is likely to be an availability problem with respect to disposal at landfills of

D. J. Nancarrow; M. M. White

2004-01-01

444

Radioactive Waste Management Complex low-level waste radiological performance assessment  

SciTech Connect

This report documents the projected radiological dose impacts associated with the disposal of radioactive low-level waste at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. This radiological performance assessment was conducted to evaluate compliance with applicable radiological criteria of the US Department of Energy and the US Environmental Protection Agency for protection of the public and the environment. The calculations involved modeling the transport of radionuclides from buried waste, to surface soil and subsurface media, and eventually to members of the public via air, groundwater, and food chain pathways. Projections of doses were made for both offsite receptors and individuals inadvertently intruding onto the site after closure. In addition, uncertainty and sensitivity analyses were performed. The results of the analyses indicate compliance with established radiological criteria and provide reasonable assurance that public health and safety will be protected.

Maheras, S.J.; Rood, A.S.; Magnuson, S.O.; Sussman, M.E.; Bhatt, R.N.

1994-04-01

445

Evaluation of Incident Risks in a Repository for Radioactive Waste  

SciTech Connect

A probabilistic safety assessment of the operation phase of a repository for radioactive waste requires the knowledge of incident risks. These are evaluated from generic observations. The present method accounts for the uncertainty (1) of whether an incident occurs, (2) of the incident rate, (3) of the duration of generic observation, and (4) of the duration of operation phase of the repository. It yields a mean risk and its standard deviation from a minimum of generic data, comprising only the number of observed incidents and the duration of the observation, as more comprehensive generic data are seldom available. It was shown that incidents sharing a common generic observation must be either merged together to a total incident or the generic observation must be split up in sub-observations, one for each such incident. The method was tested on the example of the German Konrad repository for low-level waste in a deep geological formation. (authors)

Grundler, D.; Mariae, D.; Muller, W.; Boetsch, W. [Institut fur Sicherheitstechnologie (ISTec), Koln (Germany); Thiel, J. [Bundesamt fur Strahlenschutz (BfS), Salzgitter (Germany)

2008-07-01

446

Volume reduction techniques in low-level radioactive waste management  

SciTech Connect

The report presents a comprehensive compilation and data base of volume reduction techniques for low-level radioactive wastes generated in fuel cycle and non-fuel cycle facilities. Discussions of the volume reduction techniques are provided to include system descriptions, system performance data, volume reduction capabilities, process parameters, system limitations, and operating experience. An economic analysis is presented for shredding and compaction, incineration, calcination, evaporation/crystallization, and bituminization. PWR, BWR and non-fuel cycle scenarios are evaluated for volume reduction techniques used at a waste generator's facility and on a regional basis. The economic analyses estimate cost of capital equipment, construction, operation, processing, transportation, and disposal at the Barnwell, SC and the Hanford, WA disposal sites.

Trigilio, G.

1981-09-01

447

Management of radioactive waste from nuclear power plants  

SciTech Connect

Even thought risk assessment is an essential consideration in all projects involving radioactive or hazardous waste, its public role is often unclear, and it is not fully utilized in the decision-making process for public acceptance of such facilities. Risk assessment should be an integral part of such projects and should play an important role from beginning to end, i.e., from planning stages to the closing of a disposal facility. A conceptual model that incorporates all potential pathways of exposure and is based on site-specific conditions is key to a successful risk assessment. A baseline comparison with existing standards determines, along with other factors, whether the disposal site is safe. Risk assessment also plays a role in setting priorities between sites during cleanup actions and in setting cleanup standards for certain contaminants at a site. The applicable technologies and waste disposal designs can be screened through risk assessment.

Not Available

1993-09-01

448

Site characterization for LIL radioactive waste disposal in Romania  

SciTech Connect

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

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

2001-01-01

449

Accumulation of heavy metals by vegetables grown in mine wastes  

Microsoft Academic Search

Lead, cadmium, arsenic, and zinc were quantified in mine wastes and in soils mixed with mine wastes. Metal concentrations were found to be heterogeneous in the wastes. Iceberg lettuce, Cherry Belle radishes, Roma bush beans, and Better Boy tomatoes were cultivated in mine wastes and in waste-amended soils. Lettuce and radishes had 100% survival in the 100% mine waste treatments

G. P. Cobb; K. Sands; M. Waters; B. G. Wixson; E. Dorward-King

2000-01-01

450

25 CFR 170.903 - Who notifies tribes of the transport of radioactive waste?  

Code of Federal Regulations, 2011 CFR

...DEPARTMENT OF THE INTERIOR LAND AND WATER INDIAN RESERVATION ROADS PROGRAM Miscellaneous Provisions Hazardous and Nuclear Waste Transportation § 170.903 Who notifies tribes of the transport of radioactive waste? The Department of...

2011-04-01

451

Processing of Radioactive Waste Solutions in a Vacuum Evaporator-Crystallizer.  

National Technical Information Service (NTIS)

Results of the first 18 months' operation of Hanford's vacuum evaporator-crystallizer are reported. This process reduces the volume of radioactive waste solutions and simultaneously converts the waste to a less mobile salt cake. The evaporator-crystallize...

J. C. Petrie R. I. Donovan R. E. Van der Cook W. R. Christensen

1975-01-01

452

PC-based discrete event simulation model of the Civilian Radioactive Waste Management System.  

National Technical Information Service (NTIS)

A System Simulation Model has been developed for the Department of Energy to simulate the movement of individual waste packages (spent fuel assemblies and fuel containers) through the Civilian Radioactive Waste Management System (CRWMS). A discrete event ...

G. L. Airth D. S. Joy J. W. Nehls

1991-01-01

453

Superconducting Open-Gradient Magnetic Separation for the Pretreatment of Radioactive or Mixed Waste Vitrification Feeds.  

National Technical Information Service (NTIS)

An open-gradient magnetic separation (OGMS) process is being considered to separate deleterious elements from radioactive and mixed waste streams prior to vitrification or stabilization. By physically segregating solid wastes and slurries based on the mag...

L. Nunez M. D. Kaminsky R. D. Doctor C. Crawfor J. A. Ritter

1999-01-01

454

Kostnader foer kaernkraftens radioaktiva restprodukter. (Cost for the radioactive wastes from nuclear power).  

National Technical Information Service (NTIS)

The costs for handling and storing radioactive waste and spent fuels from the Swedish nuclear reactors are calculated. The estimates also include costs for research and development for waste handling and disposal and for reactor decommissioning. Up to 199...

1990-01-01

455

Radioactive Waste Management in Hungary at the Turn of the Millennium I.  

National Technical Information Service (NTIS)

The paper deals with the Hungarian radioactive waste management practice from the beginning up to now. It gives a historical overview which is extended with the detailed description of activity of the present temporary waste disposal facility in Puespoeks...

S. Pellet A. Temesi A. Fritz

2003-01-01

456

Sulfur polymer cement, a solidification and stabilization agent for hazardous and radioactive wastes.  

National Technical Information Service (NTIS)

Hydraulic cements have been the primary radioactive waste stabilization agents in the United States for 50 years. Twelve years ago, Brookhaven National Laboratory was funded by the Department of Energy's Defense Low-Level Waste Management Program to test ...

G. R. Darnell

1992-01-01

457

Sulfur polymer cement, a new stabilization agent for mixed and low- level radioactive waste.  

National Technical Information Service (NTIS)

Solidification and stabilization agents for radioactive, hazardous, and mixed wastes are failing to pass governmental tests at alarming rates. The Department of Energy's National Low-Level Waste Management Program funded testing of Sulfur Polymer Cement (...

G. R. Darnell

1991-01-01

458

Impact of High-Level-Radioactive Wastes thermal output on repository design.  

National Technical Information Service (NTIS)

France is now investigating a number of deep geological formations (clay, granite, salt and schist) for disposal of long half-life radioactive waste, notably vitrified high-level waste (HLW) packages which would be stacked in vertical boreholes extending ...

J. L. Girotto L. Chaudon J. M. Hoorelbeke

1992-01-01

459

Final response to BDAT related comments document. Mixed radioactive hazardous wastes, polynuclear aromatic u wastes, halogenated aliphatic U wastes, non-halogenated aromatic U wastes, F002-f006, F019. Volume 1-J  

SciTech Connect

The contents of this article include the following: mixed radioactive hazardous wastes (radioactive lead wastes, radioactive mercury wastes, radioactive zirconium fines, and other radioactive wastes); polynuclear aromatic u wastes (treatment standards and recycling.reuse); halogenated aliphatic u wastes (treatment standards and bdat); non-halogenated aromatic u wastes (treatment standards and recycling/reuse); solvents (methods of detection, biological treatment, treatment standards, 2-nitropropane standard, and definition of wastewater and solvent mixtures); electroplating wastewater treatment sludges (wastewater definition, treatment standards, f006 subcategory, and analytical methods); and aluminum conversion coating treatment sludges (analytical methodology, bdat, and treatment standards).

Rosengrant, L.; Craig, R.

1990-05-01

460

Acoustic emission monitoring of cement-based structures immobilising radioactive waste  

SciTech Connect

The long term performance of cementitious structures immobilising radioactive waste can be affected by physical and chemical processes within the encapsulating materials such as formation of new phases (e.g., vaterite, brucite), degradation of cement phases (e.g., CSH gel, portlandite), degradation of some waste components (e.g., organics), corrosion of metallic constituents (aluminium, magnesium), gas emission, further hydration etc. The corrosion of metals in the high pH cementitious environment is of especial concern as it can potentially cause wasteform cracking. One of the perspective non-destructive methods used to monitor and assess the mechanical properties of materials and structures is based on an acoustic emission (AE) technique. In this study an AE non-destructive technique was used to evaluate the mechanical performance of cementitious structures with encapsulated metallic waste such as aluminium. AE signals generated as a result of aluminium corrosion in a small-size blast furnace slag (BFS)/ordinary Portland cement (OPC) sample were detected, recorded and analysed. A procedure for AE data analysis including conventional parameter-based AE approach and signal-based analysis was applied and demonstrated to provide information on the aluminium corrosion process and its impact on the mechanical performance of the encapsulating cement matrix. (authors)

Spasova, L.M.; Ojovan, M.I. [University of Sheffield (United Kingdom); Hayes, M.; Godfrey, H. [Nexia Solutions, Sellafield, Seascale, Cumbria, CA20 1PG (United Kingdom)

2007-07-01

461

Office of Civilian Radioactive Waste Management annual report to Congress  

SciTech Connect

This is the fifth Annual Report to Congress by the Office of Civilian Radioactive Waste Management (OCRWM). The report covers the activities and expenditures of OCRWM during fiscal year 1987, which ended on September 30, 1987. The activities and accomplishments of OCRWM during fiscal year 1987 are discussed in chapters 1 through 9 of this report. The audited financial statements of the Nuclear Waste Fund are provided in chapter 10. Since the close of the fiscal year, a number of significant events have occurred. Foremost among them was the passage of the Nuclear Waste Policy Amendments Act of 1987 (Amendments Act) on December 21, 1987, nearly 3 months after the end of the fiscal year covered by this report. As a result, some of the plans and activities discussed in chapters 1 through 9 are currently undergoing significant change or are being discontinued. Most prominent among the provisions of the Amendments Act is the designation of Yucca Mountain, Nevada, as the only candidate first repository site to be characterized. Therefore, the site characterization plans for Deaf Smith, Texas, and Hanford, Washington, discussed in chapter 3, will not be issued. The refocusing of the waste management program under the Amendments Act is highlighted in the epilogue, chapter 11. 68 refs., 7 figs., 7 tabs.

NONE

1988-08-01

462

Management of low-level radioactive wastes around the world  

SciTech Connect

This paper reviews the status of various practices used throughout the world for managing low-level radioactive wastes. Most of the information in this review was obtained through the DOE-sponsored International Program Support Office (IPSO) activities at Pacific Northwest Laboratory (PNL) at Richland, Washington. The objective of IPSO is to collect, evaluate, and disseminate information on international waste management and nuclear fuel cycle activities. The center's sources of information vary widely and include the proceedings of international symposia, papers presented at technical society meetings, published topical reports, foreign trip reports, and the news media. Periodically, the information is published in topical reports. Much of the information contained in this report was presented at the Fifth Annual Participants' Information Meeting sponsored by DOE's Low-Level Waste Management Program Office at Denver, Colorado, in September of 1983. Subsequent to that presentation, the information has been updated, particularly with information provided by Dr. P. Colombo of Brookhaven National Laboratory who corresponded with low-level waste management specialists in many countries. The practices reviewed in this paper generally represent actual operations. However, major R and D activities, along with future plans, are also discussed. 98 refs., 6 tabls.

Lakey, L.T.; Harmon, K.M.; Colombo, P.

1985-04-01

463