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1

Characterization of Solidified Products Yielded by Plasma Melting Treatment of Simulated Non-Metallic Radioactive Wastes  

Microsoft Academic Search

As a part of an advanced volume reduction program for low level radioactive wastes in JAERI, melting tests of non-metallic solid wastes have been conducted with the aim of establishing the optimum melting condition for preparation of a stable solid that is suitable for disposal. Simulated non-metallic wastes containing Co, Cs and Eu tracers were melted with a plasma torch

Mikio NAKASHIMA; Toshiki FUKUI; Nobuyuki NAKASHIO; Motoyasu ISOBE; Atsushi OHTAKE; Takuji WAKUI; Takakuni HIRABAYASHI

2002-01-01

2

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

3

Development of melt refining decontamination technology for low level radioactive metal waste contaminated with uranium  

NASA Astrophysics Data System (ADS)

The feasibility study of Melt Refining Decontamination by Slagging (MRDS) havs been performed for the release and recycling of Low Level Radioactive Metal Waste (LLRMW) contaminated with uranium discharged from nuclear fuel cycle facilities. Experiments and their evaluation have been performed for the decontamination performance of the waste containing aluminum and have clarified the followings. Simulated waste was decontaminated to 0.01 Bq/g when the addition of aluminum is below 1.5 wt% in laboratory scale test equipment. This was demonstrated also in the engineering scale experiment for MRDS. These results demonstrate that the MRDS is an effective processing technology for low level radioactive metal waste with uranium.

Aoyama, M.; Miyamoto, Y.; Fukumoto, M.; Suto, O.

2005-02-01

4

Traitement par fusion des dechets metalliques contamines faible activite. (Fusion process for metallic wastes slightly contaminated by radioactive substances).  

National Technical Information Service (NTIS)

To ameliorate the management of metallic wastes lightly contaminated by radioactive substances and coming from nuclear installations dismantling, the Radiation Protection Service of Saclay has undertaken the study of fusion process for these wastes. After...

C. Doucet

1988-01-01

5

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.

Moore, Lang; Smith, David

2010-07-06

6

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

7

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. 3 figs.

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

1995-10-24

8

Viscoplasticity of simulated high-level radioactive waste glass containing platinum group metal particles  

NASA Astrophysics Data System (ADS)

The shear rate dependency of the viscosity of three simulated high-level radioactive waste glasses containing 0, 1.2 and 4.5 wt% platinum group metals (PGMs) was examined at a temperature range of 1173-1473 K by a rotating viscometer. Shear stress when the shear rate equals zero, i.e. yield stress, was also measured by capillary method. The viscosity of the glass containing no PGM was shear rate-independent Newtonian fluid. On the other hand, the apparent viscosity of the glasses containing PGMs increased with decreasing shear rate, and nonzero amount of yield stresses were detected from both glasses. The viscosity and yield stress of the glass containing 4.5 wt% PGMs was roughly one to two orders of magnitude greater than the glass containing 1.2 wt% PGMs. These viscoplastic properties were numerically expressed by Casson equation.

Uruga, Kazuyoshi; Usami, Tsuyoshi; Tsukada, Takeshi; Komamine, Satoshi; Ochi, Eiji

2014-09-01

9

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

10

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

11

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

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

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, D.K.; Van Cleve, J.E. Jr.

1980-04-23

14

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

15

Radioactive Waste: 1. Radioactive waste from your lab is  

E-print Network

Radioactive Waste: 1. Radioactive waste from your lab is collected by the RSO. 2. Dry radioactive waste must be segregated by isotope. 3. Liquid radioactive waste must be separated by isotope. 4. Liquid scintillation vials must be collected separately. 5. Any "mixed waste" must be cleared with the RSO and labeled

Jia, Songtao

16

ORNL radioactive waste operations  

SciTech Connect

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 in progress. The operating record of ORNL waste operation has been excellent over many years. Recent surveillance of radioactivity in the Oak Ridge environs indicates that atmospheric concentrations of radioactivity were not significantly different from other areas in East Tennesseee. Concentrations of radioactivity in the Clinch River and in fish collected from the river were less than 4% of the permissible concentration and intake guides for individuals in the offsite environment. While some radioactivity was released to the environment from plant operations, the concentrations in all of the media sampled were well below established standards.

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

1982-01-01

17

Engineering Deinococcus radiodurans for metal remediation in radioactive mixed waste environments.  

PubMed

We have developed a radiation resistant bacterium for the treatment of mixed radioactive wastes containing ionic mercury. The high cost of remediating radioactive waste sites from nuclear weapons production has stimulated the development of bioremediation strategies using Deinococcus radiodurans, the most radiation resistant organism known. As a frequent constituent of these sites is the highly toxic ionic mercury (Hg) (II), we have generated several D. radiodurans strains expressing the cloned Hg (II) resistance gene (merA) from Escherichia coli strain BL308. We designed four different expression vectors for this purpose, and compared the relative advantages of each. The strains were shown to grow in the presence of both radiation and ionic mercury at concentrations well above those found in radioactive waste sites, and to effectively reduce Hg (II) to the less toxic volatile elemental mercury. We also demonstrated that different gene clusters could be used to engineer D. radiodurans for treatment of mixed radioactive wastes by developing a strain to detoxify both mercury and toluene. These expression systems could provide models to guide future D. radiodurans engineering efforts aimed at integrating several remediation functions into a single host. PMID:10625398

Brim, H; McFarlan, S C; Fredrickson, J K; Minton, K W; Zhai, M; Wackett, L P; Daly, M J

2000-01-01

18

Radioactive waste storage issues  

SciTech Connect

In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

Kunz, D.E.

1994-08-15

19

Slag-based materials for toxic metal and radioactive waste stabilization  

SciTech Connect

The salt solution produced at the Defense Waste Processing Facility (DWPF) is a low-level hazardous waste and has both corrosive and metal toxicity characteristics. A wasteform was designed to stabilize this solution. The objectives were: to eliminate the hazardous characteristics of the waste; and to minimize the release of potential contaminants, such as NO{sub 3}{sup {minus}}, so that drinking water standards would be maintained for groundwater at the perimeter of the disposal site. The ability to produce the wasteform in high volumes and emplace it in an engineered landfill was also necessary for treating and disposing of the large amount of waste. EP toxicity and TCLP testing was conducted to determine whether various saltstone mixes qualified as nonhazardous according to EPA guidelines. Impact of the design landfill on the groundwater was modeled by numeric methods. Data from laboratory leaching studies, large-scale saltstone lysimeter experiments, and disposal site characterization studies were used in the performance assessment. 9 refs., 3 figs., 3 tabs.

Langton, C.A.

1989-01-01

20

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.

21

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

22

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

E-print Network

options for mixed waste and the University's storage capacity for this material is limited. CarefullyRSSC RADIOACTIVE WASTE DISPOSAL 08/2011 7-1 CHAPTER 7 RADIOACTIVE WASTE DISPOSAL PAGE I. Radioactive Waste Disposal

Slatton, Clint

23

Treatment of Radioactive Reactive Mixed Waste  

SciTech Connect

PacificEcoSolutions, Inc. (PEcoS) has installed a plasma gasification system that was recently modified and used to destroy a trimethyl-aluminum mixed waste stream from Los Alamos National Laboratory (LANL.) The unique challenge in handling reactive wastes like trimethyl-aluminum is their propensity to flame instantly on contact with air and to react violently with water. To safely address this issue, PacificEcoSolutions has developed a new feed system to ensure the safe containment of these radioactive reactive wastes during transfer to the gasification unit. The plasma gasification system safely processed the radioactively contaminated trimethyl-metal compounds into metal oxides. The waste stream came from LANL research operations, and had been in storage for seven years, pending treatment options. (authors)

Colby, S.; Turner, Z.; Utley, D. [Pacific EcoSolutions, Inc., 2025 Battelle Boulevard, Richland, Washington 99354 (United States); Duy, C. [Los Alamos National Laboratory - LA-UR-05-8410, Post Office Box 1663 MS J595, Los Alamos, New Mexico 97545 (United States)

2006-07-01

24

Treatment of heterogeneous mixed wastes: Enzyme degradation of cellulosic materials contaminated with hazardous organics and toxic and radioactive metals  

Microsoft Academic Search

The redirection and downsizing of the US Department of Energy`s nuclear weapons complex requires that many facilities be decontaminated and decommissioned (D and D). At Los Alamos National Laboratory, much of the low-level radioactive, mixed, and hazardous\\/chemical waste volume handled by waste management operations was produced by D and D and environmental restoration activities. A combination of technologies--air stripping and

Laura A. Vanderberg; Trudi M. Foreman; Moses Attrep; James R. Brainard; Nancy N. Sauer

1999-01-01

25

Optimization of radioactive waste storage.  

PubMed

In several countries, low-level radioactive wastes are treated and stored awaiting construction and operation of a final repository. In some cases, interim storage may be extended for decades requiring special attention regarding security issues. The International Atomic Energy Agency (IAEA) recommends segregation of wastes that may be exempted from interim storage or ultimate disposal. The paper presents a method to optimize the decision making process regarding exemption vs. interim storage or ultimate disposal of these wastes. PMID:17228185

Dellamano, José Claudio; Sordi, Gian-Maria A A

2007-02-01

26

Subseabed storage of radioactive waste  

NASA Astrophysics Data System (ADS)

The subject of the storage of nuclear wastes products incites emotional responses from the public, and thus the U.S. Subseabed Disposal Program will have to make a good case for waste storage beneath the ocean floor. The facts attendant, however, describe circumstances necessitating cool-headed analysis to achieve a solution to the growing nuclear waste problem. Emotion aside, a good case indeed is being made for safe disposal beneath the ocean floor.The problems of nuclear waste storage are acute. A year ago, U.S. military weapons production had accumulated over seventy-five million gallons of high-level radioactive liquid waste; solid wastes, such as spent nuclear fuel rods from reactors, amounted to more than 12,000 tons. These wastes are corrosive and will release heat for 1000 years or more. The wastes will remain dangerously radioactive for a period of 10,000 years. There are advantages in storing the wastes on land, in special underground repositories, or on the surface. These include the accessibility to monitor the waste and the possibility of taking action should a container rupture occur, and thus the major efforts to determine suitable disposal at this time are focused on land-based storage. New efforts, not to be confused with ocean dumping practices of the past, are demonstrating that waste containers isolated in the clays and sediments of the ocean floor may be superior (Environ. Sci. Tech., 16, 28A-37A 1982).

Bell, Peter M.

27

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

Federal Register 2010, 2011, 2012, 2013

...Request for a License To Import Radioactive Waste Pursuant to 10 CFR 110.70...Specialty Metals......... Radioactive Waste 186,000 kilograms Return of...export Utah for licenses XW003 management and and XW007....

2010-11-09

28

Radioactive liquid waste treatment facility  

Microsoft Academic Search

The Radioactive Liquid Waste Treatment Facility (RLWTF) at Argonne National Laboratory-West (ANL-W) in Idaho provides improved treatment for low-level aqueous waste compared to conventional systems. A unique, patented evaporated system is used in the RLWTF. SHADE (shielded hot air drum evaporator, US Patent No. 4,305,780) is a low-cost disposable unit constructed from standard components and is self-shielded. The results of

1984-01-01

29

Radioactive waste: Politics and technology  

SciTech Connect

This book presents an analysis of the divergent strategies used to forge radioactive waste policies in great Britain, Germany, and Sweden. Some basic knowledge of nuclear technology and its public policy development is needed. The book points out that developing institutional frameworks that permit agreement and consent is the principal challenge of radwaste management and places the problem of consent in an institutional framework.

Berkhout, F.

1995-08-01

30

Disposal of low-level radioactive wastes  

Microsoft Academic Search

The generation of low-level radioactive waste is a natural consequence of the societal uses of radioactive materials. These uses include the application of radioactive materials to the diagnosis and treatment of human disease and to research into the causes of human disease and their prevention. Currently, low level radioactive wastes are disposed of in one of three shallow land-burial disposal

W HENDEE

1986-01-01

31

Device for the pulverization of radioactive wastes  

Microsoft Academic Search

A device is claimed for pulverizing incombustible large solid radioactive wastes arising from atomic power plants or the like. The device comprises a furnace body provided with a vacant space for melting radioactive wastes, a gripper mounted on the furnace body to support the radioactive waste, plasma torches mounted on the furnace body to irradiate a plasma arc toward the

T. Adachi; S. Hiratake

1982-01-01

32

Public attitudes about radioactive waste  

SciTech Connect

Public attitudes about radioactive waste are changeable. That is my conclusion from eight years of social science research which I have directed on this topic. The fact that public attitudes about radioactive waste are changeable is well-known to the hands-on practitioners who have opportunities to talk with the public and respond to their concerns-practitioners like Ginger King, who is sharing the podium with me today. The public`s changeability and open-mindedness are frequently overlooked in studies that focus narrowly on fear and dread. Such studies give the impression that the outlook for waste disposal solutions is dismal. I believe that impression is misleading, and I`d like to share research findings with you today that give a broader perspective.

Bisconti, A.S. [Council for Energy Awareness, Washington, DC (United States)

1992-12-31

33

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

34

Radioactive waste treatment technologies and environment  

SciTech Connect

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 given to the Bohunice Radwaste Treatment and Conditioning Centre, Bituminization plant, Vitrification plant, and Near surface repository of radioactive waste in Mochovce and their operation. Conclusions to safe and effective management of radioactive waste in the Slovak Republic are presented. (authors)

HORVATH, Jan; KRASNY, Dusan [JAVYS, PLc. - Nuclear and Decommisioning Company, PLc. (Slovakia)

2007-07-01

35

Recovering metals from wastes  

Microsoft Academic Search

Metal recycling has come a long way from the scrap heap. Today, metals recovery is not simply a matter of collecting and remelting automobile and process scrap and beverage cans for profit, but of wringing out and reusing hazardous metals from plant wastes and soil, to comply with environmental laws. Processes developed to extract metal from ore are being redesigned

G. Parkinson; S. Moore; K. Fouhy

1994-01-01

36

Future radioactive liquid waste streams study  

Microsoft Academic Search

This study provides design planning information for the Radioactive Liquid Waste Treatment Facility (RLWTF). Predictions of estimated quantities of Radioactive Liquid Waste (RLW) and radioactivity levels of RLW to be generated are provided. This information will help assure that the new treatment facility is designed with the capacity to treat generated RLW during the years of operation. The proposed startup

Rey

1993-01-01

37

Dismantlement and Radioactive Waste Management of DPRK Nuclear Facilities  

SciTech Connect

One critical aspect of any denuclearization of the Democratic People’s 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

38

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

39

Solid radioactive waste subsystem design description  

SciTech Connect

The Solid Radioactive Waste Subsystem provides reliable processing of collected solid waste to meet the requirements of 10CFR20 and 10CFR61. The methods utilized are cement solidification for sludges, resins, liquids, and noncompactible waste, and compaction for dry compressible waste. The drums of processed waste will be stored until transported off-site for disposal at a licensed burial site.

NONE

1986-06-01

40

Radioactive waste disposal via electric propulsion  

NASA Technical Reports Server (NTRS)

It is shown that space transportation is a feasible method of removal of radioactive wastes from the biosphere. The high decay heat of the isotopes powers a thermionic generator which provides electrical power for ion thrust engines. The massive shields (used to protect ground and flight personnel) are removed in orbit for subsequent reuse; the metallic fuel provides a shield for the avionics that guides the orbital stage to solar system escape. Performance calculations indicate that 4000 kg. of actinides may be removed per Shuttle flight. Subsidiary problems - such as cooling during ascent - are discussed.

Burns, R. E.

1975-01-01

41

INEL metal recycle radioactive scrap metal survey report  

SciTech Connect

DOE requested that inventory and characterization of radioactive scrap metal (RSM) be conducted across the DOE complex. Past studies have estimated the metal available from unsubstantiated sources. In meetings held in FY-1993, with seven DOE sites represented and several DOE-HQ personnel present, INEL personnel discovered that these numbers were not reliable and that large stockpiles did not exist. INEL proposed doing in-field measurements to ascertain the amount of RSM actually available. This information was necessary to determine the economic viability of recycling and to identify feed stock that could be used to produce containers for radioactive waste. This inventory measured the amount of RSM available at the selected DOE sites. Information gathered included radionuclide content and chemical form, general radiation field, alloy type, and mass of metal.

Funk, D.M.

1994-09-01

42

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, Na 8(AlSiO 4) 6Cl 2, chlorapatite, Ca 5(PO 4) 3Cl, and spodiosite, Ca 2(PO 4)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

43

Radioactive liquid waste treatment facility  

SciTech Connect

The Radioactive Liquid Waste Treatment Facility (RLWTF) at Argonne National Laboratory-West (ANL-W) in Idaho provides improved treatment for low-level aqueous waste compared to conventional systems. A unique, patented evaporated system is used in the RLWTF. SHADE (shielded hot air drum evaporator, US Patent No. 4,305,780) is a low-cost disposable unit constructed from standard components and is self-shielded. The results of testing and recent operations indicate that evaporation rates of 2 to 6 gph (8 to 23 L/h) can be achieved with a single unit housed in a standard 30-gal (114-L) drum container. The operating experience has confirmed the design evaporation rate of 60,000 gal (227,000 L) per year, using six SHADE's. 2 references, 2 figures, 2 tables.

Black, R.L.

1984-07-01

44

Radioactive waste management and practice in Bangladesh  

SciTech Connect

A large amount of low- and medium-level radioactive wastes are being generated in different parts of Bangladesh. The solid wastes are being collected in steel containers and liquid wastes are collected in plastic carboys and drums. Gaseous Ar-41 is discharged into the atmosphere through the 25 m height stack under controlled conditions after proper monitoring. The solid radioactive wastes collected are approximately 5 m{sup 3} (1988--1992) with gross beta-gamma surface dose rates from 0.30 {micro}Sv/h to 250 {micro}Sv/h. The liquid radioactive wastes are approximately 200 liters (1988--1992) with gross-beta-gamma surface dose rates from 0.30 {micro}Sv/h to 1 mSv/h. The solid and liquid wastes presently being collected are mostly short lived and low level and safely stored according to international safety codes of practice. Radioactive waste packages collected during the 5-yrs study totaled 16, representing a collective volume of {approximately} 7.5 m{sup 3}. The problem of management of radioactive waste in Bangladesh is not so serious at present because the wastes arising are small now. A computerized data base has been developed to document inventory of all radioactive waste arising in the country. The current practices of collection, handling, safe storage and management of the radioactive wastes are reported in this paper.

Mollah, A.S.; Rahman, M.M. [Atomic Energy Research Establishment, Dhaka (Bangladesh). Inst. of Nuclear Science and Technology

1993-12-31

45

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

46

Waste characterization for radioactive liquid waste evaporators at Argonne National Laboratory - West.  

SciTech Connect

Several facilities at Argonne National Laboratory - West (ANL-W) generate many thousand gallons of radioactive liquid waste per year. These waste streams are sent to the AFL-W Radioactive Liquid Waste Treatment Facility (RLWTF) where they are processed through hot air evaporators. These evaporators remove the liquid portion of the waste and leave a relatively small volume of solids in a shielded container. The ANL-W sampling, characterization and tracking programs ensure that these solids ultimately meet the disposal requirements of a low-level radioactive waste landfill. One set of evaporators will process an average 25,000 gallons of radioactive liquid waste, provide shielding, and reduce it to a volume of six cubic meters (container volume) for disposal. Waste characterization of the shielded evaporators poses some challenges. The process of evaporating the liquid and reducing the volume of waste increases the concentrations of RCIU regulated metals and radionuclides in the final waste form. Also, once the liquid waste has been processed through the evaporators it is not possible to obtain sample material for characterization. The process for tracking and assessing the final radioactive waste concentrations is described in this paper, The structural components of the evaporator are an approved and integral part of the final waste stream and they are included in the final waste characterization.

Christensen, B. D.

1999-02-15

47

Radioactive-waste incineration at Purdue University  

SciTech Connect

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 was installed on a 12.7-cm-thick concrete floor in a metal quonset building. A standard EPA Method 5 sampling train was used to obtain stack samples. Also, stack gas velocity was measured with a type 5 pitot tube; stack temperature was measured with a thermocouple and pyrometer. The incinerator was tested for emissions from incineration of laboratory animal carcasses, liquid scintillation fluid, and trash. Emissions measured were particulates, SO/sub x/, NO/sub x/, Cl, CO, CO/sub 2/, H/sub 2/O, and unburned hydrocarbons in the particulate fraction. Three analyses were then averaged to arrive at the final determinations. Results of the study demonstrated the feasibility and cost-effectiveness of incinerating radioactive animal carcasses and liquid scintillation fluids, since emissions from those waste types were within EPA and State of Indiana limits. However, emissions from burning of trash exceeded State of Indiana limits. Therefore, incineration of trash alone, particularly if it contains glass or significant amounts of plastic, is not a recommended use of the tested equipment.

Not Available

1982-11-01

48

Technology applications for radioactive waste minimization  

SciTech Connect

The nuclear power industry has achieved one of the most successful examples of waste minimization. The annual volume of low-level radioactive waste shipped for disposal per reactor has decreased to approximately one-fifth the volume about a decade ago. In addition, the curie content of the total waste shipped for disposal has decreased. This paper will discuss the regulatory drivers and economic factors for waste minimization and describe the application of technologies for achieving waste minimization for low-level radioactive waste with examples from the nuclear power industry.

Devgun, J.S.

1994-07-01

49

Phosphate bonded solidification of radioactive incinerator wastes  

SciTech Connect

The incinerator at the Department of Energy Savannah River Site burns low level radioactive and hazardous waste. Ash and scrubber system waste streams are generated during the incineration process. Phosphate Ceramic technology is being tested to verify the ash and scrubber waste streams can be stabilized using this solidification method. Acceptance criteria for the solid waste forms include leachability, bleed water, compression testing, and permeability. Other testing on the waste forms include x-ray diffraction and scanning electron microscopy.

Walker, B. W.; Langton, C. A.; Singh, D.

1999-12-03

50

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 waste—reactor wastes and wastes arising from the use of radioisotopes in hospitals and in industry—and 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. PMID:13374534

Kenny, A. W.

1956-01-01

51

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

52

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

53

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

54

Scrap metal management issues associated with naturally occurring radioactive material  

SciTech Connect

Certain industrial processes sometimes generate waste by-products that contain naturally occurring radioactive material (NORM) at elevated concentrations. Some industries, including the water treatment, geothermal energy, and petroleum industries, generate scrap metal that may be contaminated with NORM wastes. Of these three industries, the petroleum industry probably generates the largest quantity of NORM-contaminated equipment, conservatively estimated at 170,000 tons per year. Equipment may become contaminated when NORM-containing scale or sludge accumulates inside water-handling equipment. The primary radionuclides of concern in these NORM wastes are radium-226 and radium-228. NORM-contaminated equipment generated by the petroleum industry currently is managed several ways. Some equipment is routinely decontaminated for reuse; other equipment becomes scrap metal and may be disposed of by burial at a licensed landfill, encapsulation inside the wellbore of an abandoned well, or shipment overseas for smelting. In view of the increased regulatory activities addressing NORM, the economic burden of managing NORM-contaminated wastes, including radioactive scrap metal, is likely to continue to grow. Efforts to develop a cost-effective strategy for managing radioactive scrap metal should focus on identifying the least expensive disposition options that provide adequate protection of human health and the environment. Specifically, efforts should focus on better characterizing the quantity of radioactive scrap available for recycle or reuse, the radioactivity concentration levels, and the potential risks associated with different disposal options.

Smith, K.P.; Blunt, D.L.

1995-08-01

55

Offgas treatment for radioactive waste incinerators  

SciTech Connect

Incineration of radioactive materials for resource recovery or waste volume reduction is recognized as an effective waste treatment method that will increase in usage and importance throughout the nuclear industry. The offgas cleanup subsystem of an incineration process is essential to ensure radionuclide containment and protection of the environment. Several incineration processes and associated offgas cleanup systems are discussed along with potential application of commercial pollution control components to radioactive service. Problems common to radioactive waste incinerator offgas service are identified and areas of needed research and development effort are noted.

Stretz, L.A.; Koenig, R.A.

1980-01-01

56

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

57

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  

Microsoft Academic Search

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

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

1994-01-01

58

Microwave remediation of hazardous and radioactive wastes  

SciTech Connect

A team from the Westinghouse Savannah River Technology Center (WSRC - a DOE Laboratory), and the University of Florida (UF - academia), has been active for about a decade in development of microwave technology for specialized waste management applications. This interaction has resulted in the development of unique equipment and uses of microwave energy for a variety of important applications for remediation of hazardous and radioactive wastes. Discussed are results of this unique technology for processing of electronic circuitry and components, medical wastes, discarded tires, and transuranic radioactive wastes.

Wicks, G.G.

2000-04-28

59

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

60

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

61

Radioactive Waste Management in A Hospital  

PubMed Central

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

62

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

63

ASSESSMENT OF RADIOACTIVE AND NON-RADIOACTIVE CONTAMINANTS FOUND IN LOW LEVEL RADIOACTIVE WASTE STREAMS  

SciTech Connect

This paper describes and presents the findings from two studies undertaken for the European Commission to assess the long-term impact upon the environment and human health of non-radioactive contaminants found in various low level radioactive waste streams. The initial study investigated the application of safety assessment approaches developed for radioactive contaminants to the assessment of nonradioactive contaminants in low level radioactive waste. It demonstrated how disposal limits could be derived for a range of non-radioactive contaminants and generic disposal facilities. The follow-up study used the same approach but undertook more detailed, disposal system specific calculations, assessing the impacts of both the non-radioactive and radioactive contaminants. The calculations undertaken indicated that it is prudent to consider non-radioactive, as well as radioactive contaminants, when assessing the impacts of low level radioactive waste disposal. For some waste streams with relatively low concentrations of radionuclides, the potential post-closure disposal impacts from non-radioactive contaminants can be comparable with the potential radiological impacts. For such waste streams there is therefore an added incentive to explore options for recycling the materials involved wherever possible.

R.H. Little, P.R. Maul, J.S.S. Penfoldag

2003-02-27

64

ASSESSMENT OF RADIOACTIVE AND NON-RADIOACTIVE CONTAMINANTS FOUND IN LOW LEVEL RADIOACTIVE WASTE STREAMS  

Microsoft Academic Search

This paper describes and presents the findings from two studies undertaken for the European Commission to assess the long-term impact upon the environment and human health of non-radioactive contaminants found in various low level radioactive waste streams. The initial study investigated the application of safety assessment approaches developed for radioactive contaminants to the assessment of nonradioactive contaminants in low level

R. H. Little; P. R. Maul; J. S. S. Penfoldag

2003-01-01

65

Mound Laboratory Cyclone Incinerator for radioactive waste  

Microsoft Academic Search

The Cyclone Incinerator at Mound Laboratory, funded by the Division of Waste Management, Production and Reprocessing of ERDA, is capable of handling various types of combustible radioactive wastes, either by batch or by continuous feed. In batch operation, the burn chamber is a 55-gallon drum which permits the in-situ burning of wastes directly in the storage drum. Off-the-shelf components have

S. S. Freeman; L. M. Klingler; D. F. Luthy; J. E. Todd

1977-01-01

66

40 CFR 227.30 - High-level radioactive waste.  

Code of Federal Regulations, 2011 CFR

...2011-07-01 2011-07-01 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...

2011-07-01

67

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

68

40 CFR 227.30 - High-level radioactive waste.  

...2014-07-01 2014-07-01 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...

2014-07-01

69

40 CFR 227.30 - High-level radioactive waste.  

Code of Federal Regulations, 2012 CFR

...2012-07-01 2011-07-01 true 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...

2012-07-01

70

Radioactive waste management in developing and newly industrialized countries  

Microsoft Academic Search

Radioactive wastes are mostly produced in countries with military nuclear programmes. However, non-nuclear weapon countries, with solely commercial nuclear industries, also produce radioactive wastes. Moreover, uranium and thorium mining and milling wastes, as well as other kinds of low-level radioactive wastes like those resulting from radiological accidents, can also be found in developing and newly industrialized countries. The paper discusses

A. S. Paschoa; A. Tranjan Filho

1995-01-01

71

Public involvement in radioactive waste management decisions  

SciTech Connect

Current repository siting efforts focus on Yucca Mountain, Nevada, where DOE`s Office of Civilian Radioactive Waste Management (OCRWM) is conducting exploratory studies to determine if the site is suitable. The state of Nevada has resisted these efforts: it has denied permits, brought suit against DOE, and publicly denounced the federal government`s decision to study Yucca Mountain. The state`s opposition reflects public opinion in Nevada, and has considerably slowed DOE`s progress in studying the site. The Yucca Mountain controversy demonstrates the importance of understanding public attitudes and their potential influence as DOE develops a program to manage radioactive waste. The strength and nature of Nevada`s opposition -- its ability to thwart if not outright derail DOE`s activities -- indicate a need to develop alternative methods for making decisions that affect the public. This report analyzes public participation as a key component of this openness, one that provides a means of garnering acceptance of, or reducing public opposition to, DOE`s radioactive waste management activities, including facility siting and transportation. The first section, Public Perceptions: Attitudes, Trust, and Theory, reviews the risk-perception literature to identify how the public perceives the risks associated with radioactivity. DOE and the Public discusses DOE`s low level of credibility among the general public as the product, in part, of the department`s past actions. This section looks at the three components of the radioactive waste management program -- disposal, storage, and transportation -- and the different ways DOE has approached the problem of public confidence in each case. Midwestern Radioactive Waste Management Histories focuses on selected Midwestern facility-siting and transportation activities involving radioactive materials.

NONE

1994-04-01

72

Characteristics of low-level radioactive waste: Decontamination waste  

Microsoft Academic Search

The objective of Project FIN A6359, Characteristics of Low-Level Radioactive Waste: Decontamination Waste Forms,'' funded by the US Nuclear Regulatory Commission, is to provide base-line data on the stability and leachability of solidified decontamination wastes that are generated at operating commercial nuclear power stations following the chemical decontamination of primary coolant systems. This work is being performed to assess the

C. V. McIsaac; D. W. Akers

1991-01-01

73

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

74

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. 6 figs.

Gotovchikov, V.T.; Ivanov, A.V.; Filippov, E.A.

1998-05-12

75

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

76

INEEL Radioactive Liquid Waste Reduction Program  

SciTech Connect

Reduction of radioactive liquid waste, much of which is Resource Conservation and Recovery Act (RCRA) listed, is a high priority at the Idaho National Technology and Engineering Center (INTEC). Major strides in the past five years have lead to significant decreases in generation and subsequent reduction in the overall cost of treatment of these wastes. In 1992, the INTEC, which is part of the Idaho National Environmental and Engineering Laboratory (INEEL), began a program to reduce the generation of radioactive liquid waste (both hazardous and non-hazardous). As part of this program, a Waste Minimization Plan was developed that detailed the various contributing waste streams, and identified methods to eliminate or reduce these waste streams. Reduction goals, which will reduce expected waste generation by 43%, were set for five years as part of this plan. The approval of the plan led to a Waste Minimization Incentive being put in place between the Department of Energy–Idaho Office (DOE-ID) and the INEEL operating contractor, Lockheed Martin Idaho Technologies Company (LMITCO). This incentive is worth $5 million dollars from FY-98 through FY-02 if the waste reduction goals are met. In addition, a second plan was prepared to show a path forward to either totally eliminate all radioactive liquid waste generation at INTEC by 2005 or find alternative waste treatment paths. Historically, this waste has been sent to an evaporator system with the bottoms sent to the INTEC Tank Farm. However, this Tank Farm is not RCRA permitted for mixed wastes and a Notice of Non-compliance Consent Order gives dates of 2003 and 2012 for removal of this waste from these tanks. Therefore, alternative treatments are needed for the waste streams. This plan investigated waste elimination opportunities as well as treatment alternatives. The alternatives, and the criteria for ranking these alternatives, were identified through Value Engineering meetings with all of the waste generators. The most promising alternatives were compared by applying weighting factors to each based on how well the alternative met the established criteria. From this information, an overall ranking of the various alternatives was obtained and a path forward recommended.

Tripp, Julia Lynn; Archibald, Kip Ernest; Argyle, Mark Don; Demmer, Ricky Lynn; Miller, Rose Anna; Lauerhass, Lance

1999-03-01

77

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

78

Radioactive waste disposal in thick unsaturated zones.  

PubMed

Portions of the Great Basin are undergoing crustal extension and have unsaturated zones as much as 600 meters thick. These areas contain multiple natural barriers capable of isolating solidified toxic wastes from the biosphere for tens of thousands to perhaps hundreds of thousands of years. An example of the potential utilization of such arid zone environments for toxic waste isolatic is the burial of transuranic radioactive wastes at relatively shallow depths (15 to 100 meters) in Sedan Crater, Yucca Flat, Nevada. The volume of this man-made crater is several times that of the projected volume of such wastes to the year 2000. Disposal in Sedan Crater could be accomplished at a savings on the order of $0.5 billion, in comparison with current schemes for burial of such wastes in mined repositories at depths of 600 to 900 meters, and with an apparently equal likelihood of waste isolation from the biosphere. PMID:17790523

Winogard, I J

1981-06-26

79

Radioactive Waste Disposal in Thick Unsaturated Zones  

NASA Astrophysics Data System (ADS)

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

Winograd, Isaac J.

1981-06-01

80

Process for the conditioning of solid radioactive waste with large dimensions  

SciTech Connect

A process is disclosed for the conditioning of solid radioactive waste with large dimensions, constituted by contaminated objects such as cartridge filters, metal chips, tools etc. Said waste is incorporated into an ambient temperature-thermosetting resin to which has previously been added at least one inert filler, and the said resin is then cross-linked. One application is the encasing of solid radioactive waste below water, particularly at the bottom of a pond.

Morin, B.; Thiery, D.

1982-02-16

81

40 CFR 147.3005 - Radioactive waste injection wells.  

Code of Federal Regulations, 2010 CFR

...2010-07-01 false Radioactive waste injection wells. 147.3005 Section 147...EPA-ADMINISTERED UNDERGROUND INJECTION CONTROL PROGRAMS Lands of...147.3005 Radioactive waste injection wells. Notwithstanding §§...

2010-07-01

82

Managing the disposition of potentially radioactive scrap metal.  

PubMed

In 2002, the National Council on Radiation Protection and Measurements (NCRP) issued Report No. 141, Managing Potentially Radioactive Scrap Metal. The report evaluates management policy and related issues regarding scrap metal generated in regulated facilities that have been under radiological control or have radiological concerns. It has been estimated that more than 9 million metric tons of scrap metal of all types that have been associated with the production or use of radioactive materials will be generated during the coming decades at various facilities across the United States. Currently, disposition of such metal has encountered particular obstacles, primarily because of the lack of a consistent disposition policy, systematic regulatory provisions, and, above all, public understanding. Without clarity in the regulatory passage, much of the scrap metal, including metal that has not been contaminated, could be mischaracterized as low-level radioactive waste, resulting in a costly disposition operation. NCRP Report No. 141 identifies this general category of metal as "potentially radioactive scrap metal" (PRSM) and discusses the viable disposition options for facilitating its management. Because much of the PRSM has been found to contain very low residual radioactivity or even none at all, one consideration is to release such metal outside of the radiological control framework. This would require the development and implementation of a set of strict release standards in the United States that would necessarily be risk-based and supported by a comprehensive management scheme. Developing a policy of this kind, however, would entail the resolution of many issues, not the least of which would be public acceptance, including that of the metal industry, of the possible recycling of PRSM in the general commerce. PMID:17033456

Chen, S Y

2006-11-01

83

High-level radioactive wastes. Supplement 1  

SciTech Connect

This bibliography contains information on high-level radioactive wastes included in the Department of Energy's Energy Data Base from August 1982 through December 1983. These citations are to research reports, journal articles, books, patents, theses, and conference papers from worldwide sources. Five indexes, each preceded by a brief description, are provided: Corporate Author, Personal Author, Subject, Contract Number, and Report Number. 1452 citations.

McLaren, L.H. (ed.)

1984-09-01

84

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

85

Annual radioactive waste tank inspection program - 1999  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1999 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.

Moore, C.J.

2000-04-14

86

Annual radioactive waste tank inspection program: 1995  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1995 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. Sr.

1996-04-01

87

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

88

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

89

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

90

Annual Radioactive Waste Tank Inspection Program 1994  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1994 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. Sr.

1995-04-01

91

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

92

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

93

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

94

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

SciTech Connect

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 by the treatment of the waste TBP/dodecane using steam reforming system. We constructed the demonstration scale steam reforming system which consists of a gasification chamber for vaporization of wastes, a metal mesh filter for removal of radioactive nuclides from gasified wastes, a combustion chamber, and scrubbers for removal of phosphorous oxides. We conducted process demonstration tests using waste TBP/dodecane with 0.07 g/L of uranium. We studied the temperature dependence of the gasification ratio of inorganic phosphorus compounds formed by pyrolysis of TBP in the gasification chamber and removal of uranium by the filter. As the results, more than 90% of phosphorus compounds were gasified from the gasification chamber at temperature of 600 deg. C or more, and the uranium concentration in the waste water generated from the off-gas treatment system is under the detection limits. The waste water containing the separated phosphorus compounds can be discharged into the river or the sea as the liquid wastes in which uranium concentration is under the regulatory level. These results show the steam reforming system is effective in the reduction of radioactive secondary waste in the treatment of TBP/dodecane. (authors)

Sone, Tomoyuki; Sasaki, Toshiki; Yamaguchi, Hiromi [Japan Atomic Energy Agency (Japan)

2007-07-01

95

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

Microsoft Academic Search

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

P. Tuite; K. Tuite; A. Levin

1991-01-01

96

Annual Radioactive Waste Tank Inspection Program - 2003  

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 2003 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 2003 inspection program revealed that the structural integrity and waste confinement capability of the Savannah River Site waste tanks remained unchanged from 2002. A total of 4249 photographs were made, 1178 visual and video inspections were performed, and 12 helium leak tests were conducted. Ultrasonic testing was performed on five High Level Waste Tanks in accordance with approved inspection plans that met the In-Service Inspection Program requirements.

WEST, WILLIAM

2004-06-03

97

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

98

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

99

Waste gas combustion in a Hanford radioactive waste tank  

SciTech Connect

It has been observed that a high-level radioactive waste tank generates quantities of hydrogen, ammonia, nitrous oxide, and nitrogen that are potentially well within flammability limits. These gases are produced from chemical and nuclear decay reactions in a slurry of radioactive waste materials. Significant amounts of combustible and reactant gases accumulate in the waste over a 110- to 120-d period. The slurry becomes Taylor unstable owing to the buoyancy of the gases trapped in a matrix of sodium nitrate and nitrite salts. As the contents of the tank roll over, the generated waste gases rupture through the waste material surface, allowing the gases to be transported and mixed with air in the cover-gas space in the dome of the tank. An ignition source is postulated in the dome space where the waste gases combust in the presence of air resulting in pressure and temperature loadings on the double-walled waste tank. This analysis is conducted with hydrogen mixing studies HMS, a three-dimensional, time-dependent fluid dynamics code coupled with finite-rate chemical kinetics. The waste tank has a ventilation system designed to maintain a slight negative gage pressure during normal operation. We modeled the ventilation system with the transient reactor analysis code (TRAC), and we coupled these two best-estimate accident analysis computer codes to model the ventilation system response to pressures and temperatures generated by the hydrogen and ammonia combustion.

Travis, J.R.; Fujita, R.K.; Spore, J.W.

1994-07-01

100

Data base for radioactive waste management: review of low-level radioactive waste disposal history  

Microsoft Academic Search

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 1 is a summary and analysis of the history of low level waste disposal at both commercial and government

J. J. Clancy; D. F. Gray; O. I. Oztunali

1981-01-01

101

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

102

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

103

Geological problems in radioactive waste isolation  

SciTech Connect

The problem of isolating radioactive wastes from the biosphere presents specialists in the fields of earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high level waste (HLW) which must be isolated in the underground and away from the biosphere for thousands of years. Essentially every country that is generating electricity in nuclear power plants is faced with the problem of isolating the radioactive wastes that are produced. The general consensus is that this can be accomplished by selecting an appropriate geologic setting and carefully designing the rock repository. Much new technology is being developed to solve the problems that have been raised and there is a continuing need to publish the results of new developments for the benefit of all concerned. The 28th International Geologic Congress that was held July 9--19, 1989 in Washington, DC provided an opportunity for earth scientists to gather for detailed discussions on these problems. Workshop W3B on the subject, Geological Problems in Radioactive Waste Isolation -- A World Wide Review'' was organized by Paul A Witherspoon and Ghislain de Marsily and convened July 15--16, 1989 Reports from 19 countries have been gathered for this publication. Individual papers have been cataloged separately.

Witherspoon, P.A. (ed.)

1991-01-01

104

Biodegradation testing of radioactive waste forms.  

PubMed

Biodegradation tests were conducted on solidified waste forms containing ion exchange resins contaminated with high levels of radioactive nuclides. These tests were part of a program to test waste forms in accordance with the U.S. NRC Branch Technical Position on Waste Forms. Small waste forms were manufactured using two different solidification agents, Portland Type I-II cement and vinyl ester-styrene (VES). Ion exchange material was taken from a filter system which had been used to remove radionuclides from highly contaminated water. As specified by NRC, the waste forms were evaluated for their resistance to biological degradation using the G21 and G22 procedures of the American Society for Testing Materials (ASTM). Results showed that microbial growth can be supported by the VES waste forms. The particular organisms used in the tests did not grow in the presence of the cement waste forms. It is also shown that the ASTM tests specified in the Technical Position are not suitable for the use intended. A different testing methodology is recommended which would provide direct verification of waste form integrity. PMID:24248802

Rogers, R D; McConnell, J W

1988-07-01

105

Commercial low-level radioactive waste transportation safety history  

Microsoft Academic Search

An excellent safety record has been established for the transport of commercial low-level radioactive waste. By using the Radioactive Material Incident Report data base to evaluate transportation accidents involving commercial low-level radioactive waste, it was found that there have been only four transportation accidents involving the release of commercial low-level radioactive waste in the last 20 years. The accidents were

1992-01-01

106

Characteristics of low-level radioactive waste: Decontamination waste  

SciTech Connect

The objective of Project FIN A6359, Characteristics of Low-Level Radioactive Waste: Decontamination Waste Forms,'' funded by the US Nuclear Regulatory Commission, is to provide base-line data on the stability and leachability of solidified decontamination wastes that are generated at operating commercial nuclear power stations following the chemical decontamination of primary coolant systems. This work is being performed to assess the adequacy of tests identified in Technical Position on Waste Forms,'' prepared by the NRC Low-Level Waste Management Branch, to meet the requirements of 10 CFR 61. As part of the project, samples of decontamination waste stream resins and cement waste forms were obtained from commercial nuclear power stations. During Fiscal Year 1990, samples from the FitzPatrick and Brunswick nuclear stations were examined. Samples were subjected to the leach tests described in Technical Position on Waste Forms'' to assess the effects of the decontamination wastes on the stability and leachability of the waste forms. Demineralized water and four different synthetic leachates with pH ranging from 4.2 to 10.4 were used for the tests. The results of these tests are tabulated and preliminary analyses are presented. In addition, samples from the Peach Bottom nuclear station were acquired for examination during Fiscal Year 1991. 1 ref., 21 tabs.

McIsaac, C.V.; Akers, D.W. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

1991-02-01

107

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

108

Transport of Carbon Dioxide and Radioactive Waste  

Microsoft Academic Search

\\u000a A comparative assessment of carbon dioxide (CO2) and radioactive waste transport systems associated with electricity generation was undertaken on the basis of 15 criteria\\u000a grouped under three areas, namely the transport chain, policy aspects and state of the technology. For CO2, we considered exclusively the transport that would take place under a future large-scale capture and storage infrastructure.\\u000a Our study

Darío R. Gómez; Michael Tyacke

109

CHAPTER 5-RADIOACTIVE WASTE MANAGEMENT  

SciTech Connect

The ore pitchblende was discovered in the 1750's near Joachimstal in what is now the Czech Republic. Used as a colorant in glazes, uranium was identified in 1789 as the active ingredient by chemist Martin Klaproth. In 1896, French physicist Henri Becquerel studied uranium minerals as part of his investigations into the phenomenon of fluorescence. He discovered a strange energy emanating from the material which he dubbed 'rayons uranique.' Unable to explain the origins of this energy, he set the problem aside. About two years later, a young Polish graduate student was looking for a project for her dissertation. Marie Sklodowska Curie, working with her husband Pierre, picked up on Becquerel's work and, in the course of seeking out more information on uranium, discovered two new elements (polonium and radium) which exhibited the same phenomenon, but were even more powerful. The Curies recognized the energy, which they now called 'radioactivity,' as something very new, requiring a new interpretation, new science. This discovery led to what some view as the 'golden age of nuclear science' (1895-1945) when countries throughout Europe devoted large resources to understand the properties and potential of this material. By World War II, the potential to harness this energy for a destructive device had been recognized and by 1939, Otto Hahn and Fritz Strassman showed that fission not only released a lot of energy but that it also released additional neutrons which could cause fission in other uranium nuclei leading to a self-sustaining chain reaction and an enormous release of energy. This suggestion was soon confirmed experimentally by other scientists and the race to develop an atomic bomb was on. The rest of the development history which lead to the bombing of Hiroshima and Nagasaki in 1945 is well chronicled. After World War II, development of more powerful weapons systems by the United States and the Soviet Union continued to advance nuclear science. It was this defense application that formed the basis for the commercial nuclear power industry.

Marra, J.

2010-05-05

110

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

Microsoft Academic Search

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

1988-01-01

111

Annual radioactive waste tank inspection program -- 1993  

SciTech Connect

Aqueous radioactive wastes from Savannah River Site (SRS) separations processes are contained in large underground carbon steel tanks. Inspections made during 1993 to evaluate these vessels, and evaluations based on data accrued by inspections made since the tanks were constructed, are the subject of this report. The 1993 inspection program revealed that the condition of the Savannah River Site waste tanks had not changed significantly from that reported in the previous annual report. No new leaksites were observed. No evidence of corrosion or materials degradation was observed in the waste tanks. However, degradation was observed on covers of the concrete encasements for the out-of-service transfer lines to Tanks 1 through 8.

McNatt, F.G. Sr.

1994-05-01

112

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

113

Institutional options for state management of low level radioactive waste  

Microsoft Academic Search

This paper concerns ''institutional'' (legal, organizational, and political) aspects of low-level radioactive waste management. Its point of departure is the Low-Level Radioactive Waste Policy Act of 1980. With federal law and political consensus now behind the policy of state responsibility for low level waste, the question becomes, how is this new policy to be implemented. The questions of policy implementation

1981-01-01

114

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.

115

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

116

MANAGEMENT OF SOLID RADIOACTIVE WASTE Revised August 2008  

E-print Network

are officially called very low level waste (VLLW) and low level waste (LLW). Their definitions will become is officially known as very low level waste (VLLW). Such waste can be disposed of as ordinary refuse but recordsk MANAGEMENT OF SOLID RADIOACTIVE WASTE Revised August 2008 Safety Services #12;MANAGEMENT OF SOLID

Davidson, Fordyce A.

117

Future radioactive liquid waste streams study  

SciTech Connect

This study provides design planning information for the Radioactive Liquid Waste Treatment Facility (RLWTF). Predictions of estimated quantities of Radioactive Liquid Waste (RLW) and radioactivity levels of RLW to be generated are provided. This information will help assure that the new treatment facility is designed with the capacity to treat generated RLW during the years of operation. The proposed startup date for the RLWTF is estimated to be between 2002 and 2005, and the life span of the facility is estimated to be 40 years. The policies and requirements driving the replacement of the current RLW treatment facility are reviewed. Historical and current status of RLW generation at Los Alamos National Laboratory are provided. Laboratory Managers were interviewed to obtain their insights into future RLW activities at Los Alamos that might affect the amount of RLW generated at the Lab. Interviews, trends, and investigation data are analyzed and used to create scenarios. These scenarios form the basis for the predictions of future RLW generation and the level of RLW treatment capacity which will be needed at LANL.

Rey, A.S.

1993-11-01

118

Low-level radioactive waste management. Volume IV. Radioactive waste solidification and handling practices  

Microsoft Academic Search

This study evaluates low-level waste management technology for light water reactors and identifies the problems that must be solved within the next few years to allow for the orderly development of large-scale management of low-level radioactive wastes generated at nuclear power facilities and by the nuclear power industry in California. This study provides an independent assessment of current and projected

Feizollahi

1979-01-01

119

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

120

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

121

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

122

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...

123

Issue briefs on low-level radioactive wastes  

SciTech Connect

This report contains 4 Issue Briefs on low-level radioactive wastes. They are entitled: Handling, Packaging, and Transportation, Economics of LLW Management, Public Participation and Siting, and Low Level Waste Management.

Not Available

1981-01-01

124

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

125

Improved separation techniques for the characterization of radioactive waste samples  

SciTech Connect

Analysts have routinely used organic solvent extractions and precipitation techniques to remove matrix constituents which interfere with the characterization of radioactive waste samples. Problems with these traditional techniques involve the production of organic waste and time consuming steps. Extraction chromatography using recently developed resins manufactured by Eichrom Industries provides accuracy comparable to traditional techniques while reducing waste and time. Three types of Eichrom resins were evaluated on samples from radioactive waste tanks at the Department of Energy`s (DOE) Oak Ridge National Laboratory (ORNL) for the analysis of the inorganic EPA target analyte elements, radioactive strontium, and radioactive technetium. Results show that extraction chromatography may be successfully applied to the characterization of DOE radioactive waste samples similar to those at ORNL, providing high efficiency, reduced waste production, and safety benefits.

Meeks, A.M.; Keller, J.M.; Giaquinto, J.M.; Ross, T.

1994-12-31

126

Area 5 Radioactive Waste Management Site Safety Assessment Document  

SciTech Connect

The Area 5 Radioactive Waste Management Safety Assessment Document evaluates site characteristics, facilities and operating practices which contribute to the safe handling and storage/disposal of radioactive wastes at the Nevada Test Site. Physical geography, cultural factors, climate and meteorology, geology, hydrology (with emphasis on radionuclide migration), ecology, natural phenomena, and natural resources are discussed and determined to be suitable for effective containment of radionuclides. Also considered, as a separate section, are facilities and operating practices such as monitoring; storage/disposal criteria; site maintenance, equipment, and support; transportation and waste handling; and others which are adequate for the safe handling and storage/disposal of radioactive wastes. In conclusion, the Area 5 Radioactive Waste Management Site is suitable for radioactive waste handling and storage/disposal for a maximum of twenty more years at the present rate of utilization.

Horton, K.K.; Kendall, E.W.; Brown, J.J.

1980-02-01

127

Waste characterization for radioactive liquid waste evaporators at Argonne National Laboratory - West  

Microsoft Academic Search

Several facilities at Argonne National Laboratory - West (ANL-W) generate many thousand gallons of radioactive liquid waste per year. These waste streams are sent to the AFL-W Radioactive Liquid Waste Treatment Facility (RLWTF) where they are processed through hot air evaporators. These evaporators remove the liquid portion of the waste and leave a relatively small volume of solids in a

1999-01-01

128

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

129

Apparatus for filling a container with radioactive solid wastes  

Microsoft Academic Search

In apparatus for filling a container suitable for storage with radioactive solid wastes arising from atomic power plants or the like, a plasma arc is irradiated toward a portion of the wastes to melt the portion of the wastes; portions of the wastes are successively moved so as to be subjected to irradiation of the plasma arc to continuously melt

T. Adachi; S. Hiratake

1984-01-01

130

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

131

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

132

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

133

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

Federal Register 2010, 2011, 2012, 2013

...Reduction and Low-Level Radioactive Waste Management AGENCY: Nuclear Regulatory...Reduction and Low-Level Radioactive Waste Management that updates the 1981...Reduction and Low-Level Radioactive Waste Management in response to a...

2011-09-21

134

77 FR 25760 - Low-Level Radioactive Waste Management and Volume Reduction  

Federal Register 2010, 2011, 2012, 2013

...NRC-2011-0183] Low-Level Radioactive Waste Management and Volume Reduction...Reduction and Low-Level Radioactive Waste Management,'' was published...Commission on Low- Level Radioactive Waste Management and Volume...

2012-05-01

135

76 FR 10810 - Public Workshop to Discuss Low-Level Radioactive Waste Management  

Federal Register 2010, 2011, 2012, 2013

...Workshop to Discuss Low-Level Radioactive Waste Management AGENCY: Nuclear Regulatory...regulatory framework for the management of commercial low-level radioactive waste...Part 61, ``Low-Level Radioactive Waste Management'' NRC staff is...

2011-02-28

136

Volume reduction of low-level radioactive wastes  

Microsoft Academic Search

A process is described for reducing the volume of a low-level radioactive liquid waste containing a compound of an element selected from the group consisting of I, Cs, Co and Mn. The process consists of: introducing the low-level radioactive liquid waste in the form of a finely atomized spray into a spray drying zone and contacting it with a hot

R. L. Gray; L. F. Grantham

1986-01-01

137

Low-level radioactive waste disposal facility closure  

Microsoft Academic Search

Part I of this report describes and evaluates potential impacts associated with changes in environmental conditions on a low-level radioactive waste disposal site over a long period of time. Ecological processes are discussed and baselines are established consistent with their potential for causing a significant impact to low-level radioactive waste facility. A variety of factors that might disrupt or act

G. J. White; T. W. Ferns; M. D. Otis; S. T. Marts; M. S. DeHaan; R. G. Schwaller

1990-01-01

138

Radioactive Waste Information for 1998 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 1998 at the Idaho National Engineering and Environmental Laboratory (INEEL). The data presented are from the INEEL Integrated Waste Information System.

D. L. French; R. E. Tallman; K. A. Taylor

1999-07-01

139

PRETREATMENT OF LIQUID RADIOACTIVE WASTES FOR UNDERGROUND DISPOSAL  

Microsoft Academic Search

The paper summarizes the experimental data on pretreatment of liquid radioactive wastes for underground disposal. The technologies of the pretreatment of low -, intermediate - and high- level radioactive wastes which is necessary to exclude the appearance of precipitates in geological formation are described in some detail. The pH values are controlled and addition of complexing agents (to form the

I. M. Kosareva; M. K. Savushkina; A. K. Pikaev

140

Radioactive Liquid Waste Treatment Facility: Environmental Information Document  

Microsoft Academic Search

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

H. T. Haagenstad; G. Gonzales; I. L. Suazo

1993-01-01

141

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

142

Radioactive Waste Management Procedures and Guidelines See Radiation Manual 1997 for further details  

E-print Network

1-24-03 Radioactive Waste Management Procedures and Guidelines See Radiation Manual 1997 PART I. Radioactive Waste A. Dry Waste 1. Labs must request a box from the Radioactive Waste program, and use only this box for accumulating their waste. 2. Place only radioactive material contaminated

143

Glassy slags as novel waste forms for remediating mixed wastes with high metal contents  

SciTech Connect

Argonne National Laboratory (ANL) is developing a glassy slag final waste form for the remediation of low-level radioactive and mixed wastes with high metal contents. This waste form is composed of various crystalline and metal oxide phases embedded in a silicate glass phase. This work indicates that glassy slag shows promise as final waste form because (1) it has similar or better chemical durability than high-level nuclear waste (HLW) glasses, (2) it can incorporate large amounts of metal wastes, (3) it can incorporate waste streams having low contents of flux components (boron and alkalis), (4) it has less stringent processing requirements (e.g., viscosity and electric conductivity) than glass waste forms, (5) its production can require little or no purchased additives, which can result in greater reduction in waste volume and overall treatment costs. By using glassy slag waste forms, minimum additive waste stabilization approach can be applied to a much wider range of waste streams than those amenable only to glass waste forms.

Feng, X.; Wronkiewicz, D.J.; Bates, J.K.; Brown, N.R.; Buck, E.C.; Gong, M.; Ebert, W.L.

1994-03-01

144

Geological problems in radioactive waste isolation - A world wide review  

SciTech Connect

The problem of isolating radioactive wastes from the biosphere presents specialists in the earth sciences with some of the most complicated problems they have ever encountered. This is especially true for high-level waste (HLW), which must be isolated in the underground and away from the biosphere for thousands of years. The most widely accepted method of doing this is to seal the radioactive materials in metal canisters that are enclosed by a protective sheath and placed underground in a repository that has been carefully constructed in an appropriate rock formation. Much new technology is being developed to solve the problems that have been raised, and there is a continuing need to publish the results of new developments for the benefit of all concerned. Table 1 presents a summary of the various formations under investigation according to the reports submitted for this world wide review. It can be seen that in those countries that are searching for repository sites, granitic and metamorphic rocks are the prevalent rock type under investigation. Six countries have developed underground research facilities that are currently in use. All of these investigations are in saturated systems below the water table, except the United States project, which is in the unsaturated zone of a fractured tuff.

Witherspoon, P.A. [Lawrence Berkeley Lab., CA (United States)

1991-06-01

145

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

146

Locating a Radioactive Waste Repository in the Ring of Fire  

Microsoft Academic Search

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

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

2004-01-01

147

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

148

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

149

DRINK: a biogeochemical source term model for low level radioactive waste disposal sites  

Microsoft Academic Search

Interactions between element chemistry and the ambient geochemistry play a significant role in the control of radionuclide migration in the geosphere. These same interactions influence radionuclide release from near surface, low level radioactive waste, disposal sites once physical containment has degraded. In situations where LLW contains significant amounts of metal and organic materials such as cellulose, microbial degradation in conjunction

Paul Humphreys; Ray McGarry; Alex Hoffmann; Peter Binks

1997-01-01

150

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

151

Defining a metal-based waste form for IFR pyroprocessing wastes  

Microsoft Academic Search

Pyrochemical electrorefining to recover actinides from metal nuclear fuel is a key element of the Integral Fast Reactor (IFR) fuel cycle. The process separates the radioactive fission products from the long-lived actinides in a molten LiCl-KCl salt, and it generates a lower waste volume with significantly less long-term toxicity as compared to spent nuclear fuel. The process waste forms include

S. M. McDeavitt; J. Y. Park; J. P. Ackerman

1994-01-01

152

Scrap metals industry perspective on radioactive materials.  

PubMed

With more than 80 reported/confirmed accidental melts worldwide since 1983 and still counting, potential contamination by radioactive materials remains as a major concern among recycled scrap and steel companies. Some of these events were catastrophic and have cost the industry millions of dollars in business and, at the same time, resulted in declining consumer confidence. It is also known that more events with confirmed radioactive contamination have occurred that involve mining of old steel slag and skull dumps. Consequently, the steel industry has since undergone massive changes that incurred unprecedented expenses through the installation of radiation monitoring systems in hopes of preventing another accidental melt. Despite such extraordinary efforts, accidental melts continue to occur and plague the industry. One recent reported/confirmed event occurred in the Republic of China in 2004, causing the usual lengthy shutdown for expensive decontamination efforts before the steel mill could resume operations. With this perspective in mind, the metal industry has a long-standing opposition to the release of radioactive materials of any kind to commerce for fear of contamination and the potential consequences. PMID:17033460

Turner, Ray

2006-11-01

153

Fusion reactor radioactive materials and national waste management regulations  

NASA Astrophysics Data System (ADS)

National regulations on waste management do not seem adequate to cope with the fusion case. The paper shows the relevance of this problem, showing some aspects of application of national radioactive waste management practices and regulations to fusion. In particular, the case of Italian waste management regulations is considered. The waste management strategy proposed in the SEAFP and PPCS studies, based upon recycling and clearance techniques, is compared to Italian national regulations. If those regulations were applied to fusion, a relevant part of the fusion radioactive materials should be classified in the Italian High Level Waste category. Also in the case of other national regulations, fusion waste would be rated mostly in the local `high-level' category. An evolution of those regulations in the future, in order to take into account the special characteristics of fusion radioactive materials, is recommended.

Zucchetti, Massimo; Ciampichetti, Andrea

2004-08-01

154

Assessment of recycling or disposal alternatives for radioactive scrap metal  

SciTech Connect

The US Department of Energy, Office of Environmental Restoration and Waste Management, Oak Ridge Programs Division, is participating with the Organization for Economic Cooperation and Development in providing analytical support for evaluation of management alternatives for radioactive scrap metals. For this purpose, Argonne National Laboratory is assessing environmental and societal implications of recycling and/or disposal process alternatives. This effort includes development of inventory estimates for contaminated metals; investigation of scrap metal market structure, processes, and trends; assessment of radiological and nonradiological effects of recycling; and investigation of social and political factors that are likely to either facilitate or constrain recycling opportunities. In addition, the option of scrap metal disposal is being assessed, especially with regard to the environmental and health impacts of replacing these metals if they are withdrawn from use. This paper focuses on the radiological risk assessment and dose estimate sensitivity analysis. A {open_quotes}tiered{close_quotes} 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 conservatism 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 [US Dept. of Energy, Oak Ridge, TN (United States); Nieves, L.A.; Chen, S.Y. [Argonne National Lab., IL (United States)

1993-11-01

155

Results of field testing of radioactive waste forms using lysimeters  

Microsoft Academic Search

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

McConnell J. W. Jr; R. D. Rogers; J. D. Jastrow; D. S. Wickliff

1992-01-01

156

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

157

Journey to the Nevada Test Site Radioactive Waste Management Complex  

ScienceCinema

Journey to the Nevada Test Site Radioactive Waste Management Complex begins with a global to regional perspective regarding the location of low-level and mixed low-level waste disposal at the Nevada Test Site. For decades, the Nevada National Security Site (NNSS) has served as a vital disposal resource in the nation-wide cleanup of former nuclear research and testing facilities. State-of-the-art waste management sites at the NNSS offer a safe, permanent disposal option for U.S. Department of Energy/U.S. Department of Defense facilities generating cleanup-related radioactive waste.

None

2014-10-28

158

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

Microsoft Academic Search

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

J. Freer; E. Freer; A. Bond

1996-01-01

159

Safe disposal of radionuclides in low-level radioactive-waste repository sites  

Microsoft Academic Search

This paper reports on the status of land disposal of low-level radioactive waste: experience and performance of existing low-level radioactive-waste sites, geohydrologic sitting guidelines and regulatory requirements, characterization of the geology and hydrology of low-level radioactive-waste repository sites, and geohydrologic modeling of performance of low-level radioactive-waste repository sites.

M. S. Bedinger; P. R. Stevens

1990-01-01

160

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

2007-01-01

161

Rev August 2006 Radiation Safety Manual Section 14 Radioactive Waste  

E-print Network

.............................................................................................14-13 UW Environmental Health and Safety #12;Rev August 2006 Section 14 ­ Radioactive Waste Radiation Safety Manual Page 14-2 11. Uranium and Thorium Compounds..............................................14

Wilcock, William

162

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

163

Melt processing of radioactive waste: A technical overview.  

National Technical Information Service (NTIS)

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 accumu...

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

1997-01-01

164

Solid low-level radioactive waste radiation stability studies  

E-print Network

ions that are strongly adsorbed (Eichholz 1976). High integrity containers (HIC) Nuclear power plants use organic ion-exchange materials for coolant chemistry control and removal of radioactive contamination from liquid wastes. These materials may... ions that are strongly adsorbed (Eichholz 1976). High integrity containers (HIC) Nuclear power plants use organic ion-exchange materials for coolant chemistry control and removal of radioactive contamination from liquid wastes. These materials may...

Williams, Arnold Andre?

2012-06-07

165

s.haszeldine@ed.ac.uk Radioactive waste Cumbria 6, 7 Sept 2012 1 Geological disposal of radioactive  

E-print Network

of sites · These are sites where water flow is favourable to disposal of radioactive waste. · Identified.haszeldine@ed.ac.uk Radioactive waste Cumbria 6, 7 Sept 2012 10 MRWS asked BGS to map the excluded zones in 2010 mineral or water into the sea and fresh water ....... discharge at or near the coast.s.haszeldine@ed.ac.uk Radioactive waste

166

Issues in radioactive waste management for fusion power  

Microsoft Academic Search

Analysis of recent conceptual designs reveals that commercial fusion power systems will raise issues of occupational and public health and safety. This paper focuses on radioactive wastes from fusion reactor materials activated by neutrons. The analysis shows that different selections of materials and neutronic designs can make differences in orders-of magnitude of the kinds and amounts of radioactivity to be

R. C. Maninger; D. W. Dorn

1983-01-01

167

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

168

In situ electrochemical characterization of grouted radioactive waste  

SciTech Connect

At the Hanford Site, twenty-eight double-shell tanks (DST) and one hundred and forty nine single-shell tanks (SST) are used for storage of radioactive liquid and sludge wastes and sat cake. A fundamental goal of the Westinghouse Hanford Company is to end the current storage practice for liquid wastes and to permanently dispose of the waste. The Hanford Defense Waste Environmental Impact Statement and subsequent record of decision has identified a cement-based waste form for disposal of DST low-level liquid waste. The low level radioactive fractions of these wastes will be immobilized in a cementitious grout at the Hanford Grout Processing Facility and disposed of in concrete vaults of the Grout Disposal Facility. Prior to closing each vault, postcuring verification will show that the final product meets the performance requirements. Any long term disposal system of radioactive waste will require monitoring to warn against structural deterioration and/or leach of the radioactive or hazardous components into the environment. We are investigating the possibility of monitoring the degree of immobilization of the waste by embedding a grid of long-lasting electrodes in grout. This work describes our ongoing attempts to understand the physics and chemistry of charge carriers in the grout under various load conditions.

Gu, Jingyan; Shen, Wu-Mian; Tomkiewicz, Micha [Brooklyn Coll., NY (United States). Dept. of Physics; Kruger, A.A. [Westinghouse Hanford Co., Richland, WA (United States)

1993-04-01

169

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

170

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

171

Concentration of radioactive components in liquid low-level radioactive waste by membrane distillation  

Microsoft Academic Search

The paper addresses some aspects of liquid low-level radioactive waste (LLLW) purification. Since the volume of liquid low-level wastes is usually large and the activity is rather low, the radioactive substances separated from the non-active portion have to be concentrated into the small volume for subsequent conditioning and disposal. The need for the improvement of decontamination and minimisation of the

G. Zakrzewska-Trznadel; M. Harasimowicz; A. G. Chmielewski

1999-01-01

172

Review and evaluation of metallic TRU nuclear waste consolidation methods  

SciTech Connect

The US Department of Energy established the Commercial Waste Treatment Program to develop, demonstrate, and deploy waste treatment technology. In this report, viable methods are identified that could consolidate the volume of metallic wastes generated in a fuel reprocessing facility. The purpose of this study is to identify, evaluate, and rate processes that have been or could be used to reduce the volume of contaminated/irradiated metallic waste streams and to produce an acceptable waste form in a safe and cost-effective process. A technical comparative evaluation of various consolidation processes was conducted, and these processes were rated as to the feasibility and cost of producing a viable product from a remotely operated radioactive process facility. Out of the wide variety of melting concepts and consolidation systems that might be applicable for consolidating metallic nuclear wastes, the following processes were selected for evaluation: inductoslay melting, rotating nonconsumable electrode melting, plasma arc melting, electroslag melting with two nonconsumable electrodes, vacuum coreless induction melting, and cold compaction. Each process was evaluated and rated on the criteria of complexity of process, state and type of development required, safety, process requirements, and facility requirements. It was concluded that the vacuum coreless induction melting process is the most viable process to consolidate nuclear metallic wastes. 11 references.

Montgomery, D.R.; Nesbitt, J.F.

1983-08-01

173

78 FR 26812 - Request To Amend a License To Export Radioactive Waste  

Federal Register 2010, 2011, 2012, 2013

...Amend a License To Export Radioactive Waste Pursuant to 10 CFR 110.70 (b...11005699. A radioactive total of 5,500 Energy of Canada waste). tons of low- Limited facilities as level waste). ``Ultimate Foreign...

2013-05-08

174

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

Code of Federal Regulations, 2011 CFR

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

2011-04-01

175

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

Code of Federal Regulations, 2012 CFR

...the transport of radioactive waste? 170.903 Section 170...DEPARTMENT OF THE INTERIOR LAND AND WATER INDIAN RESERVATION ROADS PROGRAM...Provisions Hazardous and Nuclear Waste Transportation § 170.903...the transport of radioactive waste? The Department of...

2012-04-01

176

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

Code of Federal Regulations, 2013 CFR

...the transport of radioactive waste? 170.903 Section 170...DEPARTMENT OF THE INTERIOR LAND AND WATER INDIAN RESERVATION ROADS PROGRAM...Provisions Hazardous and Nuclear Waste Transportation § 170.903...the transport of radioactive waste? The Department of...

2013-04-01

177

Final repository for Denmark's low- and intermediate level radioactive waste  

NASA Astrophysics Data System (ADS)

Bertel Nilsson*, Peter Gravesen, Stig A. Schack Petersen, Merete Binderup Geological Survey of Denmark and Greenland (GEUS), Řster Voldgade 10, 1350 Copenhagen, Denmark, * email address bn@geus.dk The Danish Parliament decided in 2003 that the temporal disposal of the low- and intermediate level radioactive waste at the nuclear facilities at Risř should find another location for a final repository. The Danish radioactive waste must be stored on Danish land territory (exclusive Greenland) and must hold the entire existing radioactive waste, consisting of the waste from the decommissioning of the nuclear facilities at Risř, and the radioactive waste produced in Denmark from hospitals, universities and industry. The radioactive waste is estimated to a total amount of up to 10,000 m3. The Geological Survey of Denmark and Greenland, GEUS, is responsible for the geological studies of suitable areas for the repository. The task has been to locate and recognize non-fractured Quaternary and Tertiary clays or Precambrian bedrocks with low permeability which can isolate the radioactive waste from the surroundings the coming more than 300 years. Twenty two potential areas have been located and sequential reduced to the most favorable two to three locations taking into consideration geology, hydrogeology, nature protection and climate change conditions. Further detailed environmental and geology investigations will be undertaken at the two to three potential localities in 2013 to 2015. This study together with a study of safe transport of the radioactive waste and an investigation of appropriate repository concepts in relation to geology and safety analyses will constitute the basis upon which the final decision by the Danish Parliament on repository concept and repository location. The final repository is planned to be established and in operation at the earliest 2020.

Nilsson, B.; Gravesen, P.; Petersen, S. S.; Binderup, M.

2012-12-01

178

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

Microsoft Academic Search

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

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

1980-01-01

179

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

180

Radioactive waste disposal fees-Methodology for calculation  

NASA Astrophysics Data System (ADS)

This paper summarizes the methodological approach used for calculation of fee for low- and intermediate-level radioactive waste disposal and for spent fuel disposal. The methodology itself is based on simulation of cash flows related to the operation of system for waste disposal. The paper includes demonstration of methodology application on the conditions of the Czech Republic.

Bemš, Július; Králík, Tomáš; Kuban?ák, Ján; Vaší?ek, Ji?í; Starý, Old?ich

2014-11-01

181

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...

182

ACTINIDE-ALUMINATE SPECIATION IN ALKALINE RADIOACTIVE WASTE  

Microsoft Academic Search

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 their solubility and sorption behavior in tanks, determining whether chemical separations are needed for waste treatment, and designing separations processes. Baseline

Clark-Deaborg

2001-01-01

183

Actinide-aluminate Speciation in Alkaline Radioactive Waste  

Microsoft Academic Search

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 their solubility and sorption behavior in tanks, determining whether chemical separations are needed for waste treatment, and designing separations processes. Baseline

David C. Clark; Nikolai N. Krot

2000-01-01

184

Research on uranium deposits as analogies of radioactive waste repositories  

Microsoft Academic Search

The disposal of highly radioactive waste deep underground in suitable geological formations is proposed by many countries to protect public health and safety. The study of natural analogies of nuclear waste repositories is one method of validating mathematical models and assuring that a proposed repository site and design will be safe. Since 1981, the AAEC has studied the major uranium

1988-01-01

185

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

2011-07-01

186

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.

Özdemir, Tonguç; Usanmaz, Ali

2009-09-01

187

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

188

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

189

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

190

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

191

RADIOACTIVE WASTE DISPOSAL AT KNOLLS ATOMIC POWER LABORATORY  

Microsoft Academic Search

One of Its Monograph Series The Industrial Atom.'' Disposal of ;\\u000a radioactive wastes from KAPL is considered with respect to the three physical ;\\u000a categories of waste--solid, liquid, and airborne---and the three environmental ;\\u000a recipients ---ground, surface water, and atmosphere. Solid waste-handling ;\\u000a includes monitoring radiation levels, segregation, collection, processing, ;\\u000a packaging, storing if necessary, and shipping to a remote

D. A. Manieri; W. H. Truran

1958-01-01

192

Argonne-West facility requirements for a radioactive waste treatment demonstration  

SciTech Connect

At Argonne National Laboratory-West (ANL-W), near Idaho Falls, Idaho, facilities that were originally constructed to support the development of liquid-metal reactor technology are being used and/or modified to meet the environmental and waste management research needs of DOE. One example is the use of an Argonne-West facility to conduct a radioactive waste treatment demonstration through a cooperative project with Science Applications International Corporation (SAIC) and Lockheed Idaho Technologies Company. The Plasma Hearth Process (PBP) project will utilize commercially-adapted plasma arc technology to demonstrate treatment of actual mixed waste. The demonstration on radioactive waste will be conducted at Argonne`s Transient Reactor Test Facility (TREAT). Utilization of an existing facility for a new and different application presents a unique set of issues in meeting applicable federal state, and local requirements as well as the additional constraints imposed by DOE Orders and ANL-W site requirements. This paper briefly describes the PHP radioactive demonstrations relevant to the interfaces with the TREAT facility. Safety, environmental design, and operational considerations pertinent to the PHP radioactive demonstration are specifically addressed herein. The personnel equipment, and facility interfaces associated with a radioactive waste treatment demonstration are an important aspect of the demonstration effort. Areas requiring significant effort in preparation for the PBP Project being conducted at the TREAT facility include confinement design, waste handling features, and sampling and analysis considerations. Information about the facility in which a radioactive demonstration will be conducted, specifically Argonne`s TREAT facility in the case of PHP, may be of interest to other organizations involved in developing and demonstrating technologies for mixed waste treatment.

Dwight, C.C.; Felicione, F.S.; Black, D.B.; Kelso, R.B.; McClellan, G.C.

1995-03-01

193

Department of Energy perspectives on residual radioactivity in waste  

SciTech Connect

The lack of generally-applicable standards for release of waste with minute amounts of radioactive material may have contributed to the use of inappropriate standards for making release decisions by DOE installations. The result was a large expenditure of resources to determine the amounts and types of waste involved and impacts of releasing these contaminated materials. Now DOE, in coordination with the Environmental Protection Agency, the Nuclear Regulatory Commission, the Department of Defense and the Office of Management and Budget, is working on generally-applicable standards for residual radioactivity at cleanup sites and in waste. DOE is funding standards development by EPA and is pursuing technical data for establishing allowable levels for radioactive materials in waste regulated under the Resource Conservation and Recovery Act. Until standards are developed and promulgated in regulations, DOE will evaluate, on a case-by-case basis, the release of slightly contaminated material as allowed for in currently existing Orders and regulations.

Stevens, L.E.; Owens, K.W.

1994-12-31

194

Measurement and calibration of metal and non-metal wastes produced from decommissioning.  

PubMed

This report described a radioactive waste reference drum which was established with large-area sources and metal slices. This reference drum could be applied in calibration or testing of drum counting systems having 4? counting geometry and being made with plastic scintillators. This metal reference drum has the advantages of easy operation, low natural background and it also has agreeable measurement efficiency calibration curves for the drum counting system as the non-metal reference drum studied previously. On the other hand, this study explored the counting efficiency variations of the drum counting system by simulations of the metal reference drum being filled with wastes up to different heights within the drum. With the exploration, it is feasible to correct the measurement errors caused by different quantities of waste filling. PMID:24342558

Yeh, Chin-Hsien; Yuan, Ming-Chen

2014-05-01

195

Encapsulation of mixed radioactive and hazardous waste contaminated incinerator ash in modified sulfur cement  

SciTech Connect

Some of the process waste streams incinerated at various Department of Energy (DOE) facilities contain traces of both low-level radioactive (LLW) and hazardous constituents, thus yielding ash residues that are classified as mixed waste. Work is currently being performed at Brookhaven National Laboratory (BNL) to develop new and innovative materials for encapsulation of DOE mixed wastes including incinerator ash. One such material under investigation is modified sulfur cement, a thermoplastic developed by the US Bureau of Mines. Monolithic waste forms containing as much as 55 wt % incinerator fly ash from Idaho national Engineering Laboratory (INEL) have been formulated with modified sulfur cement, whereas maximum waste loading for this waste in hydraulic cement is 16 wt %. Compressive strength of these waste forms exceeded 27.6 MPa. Wet chemical and solid phase waste characterization analyses performed on this fly ash revealed high concentrations of soluble metal salts including Pb and Cd, identified by the Environmental Protection Agency (EPA) as toxic metals. Leach testing of the ash according to the EPA Toxicity Characteristic Leaching Procedure (TCLP) resulted in concentrations of Pb and Cd above allowable limits. Encapsulation of INEL fly ash in modified sulfur cement with a small quantity of sodium sulfide added to enhance retention of soluble metal salts reduced TCLP leachate concentrations of Pb and Cd well below EPA concentration criteria for delisting as a toxic hazardous waste. 12 refs., 4 figs., 2 tabs.

Kalb, P.D.; Heiser, J.H. III; Colombo, P.

1990-01-01

196

Annual Radioactive Waste Tank Inspection Program 2001  

SciTech Connect

The waste tank in-service inspection program is an ongoing program. This report gives results of the 2001 inspections and summarizes significant findings of previous in-service inspections for each waste tank.

Waltz, R.S.

2002-06-25

197

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

198

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

199

Method for aqueous radioactive waste treatment  

DOEpatents

Plutonium, strontium, and cesium found in aqueous waste solutions resulting from nuclear fuel processing are removed by contacting the waste solutions with synthetic zeolite incorporating up to about 5 wt % titanium as sodium titanate in an ion exchange system. More than 99.9% of the plutonium, strontium, and cesium are removed from the waste solutions.

Bray, Lane A. (Richland, WA); Burger, Leland L. (Richland, WA)

1994-01-01

200

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

201

METAL BEHAVIOR DURING MEDICAL WASTE INCINERATION  

EPA Science Inventory

Medical waste contains toxic metals such as lead, cadmium, and mercury. onsequently, the incineration of medical waste may result in the emissions of trace metals into the environment, if incinerators are not properly designed and operated. PA's Risk Reduction Engineering Laborat...

202

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

203

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

204

Biogeochemical changes at early stage after the closure of radioactive waste geological repository in South Korea  

E-print Network

Organic waste a b s t r a c t Permanent disposal of low- and intermediate-level radioactive wastesBiogeochemical changes at early stage after the closure of radioactive waste geological repository e Korea Radioactive Waste Agency (KORAD), 111, Daedeok-daero 989 beon-gil, Yuseong-gu, Daejeon 305

Ohta, Shigemi

205

ANALYSES AND PRELIMINARY RESULTS OF AN UPDATED ITER RADIOACTIVE WASTE ASSESSMENT  

E-print Network

ANALYSES AND PRELIMINARY RESULTS OF AN UPDATED ITER RADIOACTIVE WASTE ASSESSMENT S. ZHENG,a * R aimed at updating the ITER radioactive inventory assessment and assisting the waste manage- ment operations, and waste management processes and services. KEYWORDS: ITER, radioactive waste management

206

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

207

Radioactive waste minimization at a large academic medical facility.  

PubMed

The University of Texas Medical Branch (UTMB) at Galveston is a large academic medical center with about 12,700 employees, 350 radioisotope research labs and 200 permitted radioactive materials users. Consequently, UTMB generates a fairly large amount of radioactive waste. The majority of this waste contains short-lived radionuclides, such as 32P, 33P, and 35S, which are held for decay and then disposed at a sanitary landfill. However, some waste, including long-lived waste and stock vials, is compacted into drums and stored in a warehouse facility, on-site, until disposal at a low-level radioactive waste (LLRW) facility. Space in the warehouse is limited but disposal is currently cost prohibitive. A reevaluation of our program was conducted to see if volumes of LLRW requiring disposal at a commercial LLRW facility could be reduced. A reevaluation of the waste streams resulted in the shifting of most of the material that was being drummed for shipment to a LLRW facility to disposal by landfill or incineration. Materials that were previously assumed to be radioactive are now being evaluated prior to disposal to determine if they may be disposed of as non-radioactive waste. Following the initial evaluation, the amount of compacted dry solids assumed to contain long-lived radionuclides was reduced. The space that was saved due to the decrease in drumming for disposal is now used to hold the increased volume of decay-in-storage material. The monetary savings will amount to about $45,000 per year. This program is currently being expanded to reduce other waste streams at the university. PMID:12003027

Krieger, Kenneth; Van Baalen, Mary; Walters, Christopher

2002-05-01

208

California's low-level radioactive waste crisis  

Microsoft Academic Search

California is quickly approaching the January 1, 1993, deadline for providing disposal capacity for low-level waste generated within the state, a deadline set by federal law more than a decade ago. What alternatives are available to California's 500 waste producers, who routinely ship this waste to out-to-state sites Frankly, not many. The immediate response for many will be to store

2009-01-01

209

Radioactive materials in recycled metals--an update.  

PubMed

In April 1995, Health Physics published a review paper titled "Radioactive Materials in Recycled Metals." At that time, 35 accidental meltings of radioactive sources in metal mills were reported, including 22 in the U.S., along with 293 other events in the U.S. where radioactive material was found in metals for recycling. Since that date, there have been additional accidental meltings of radioactive sources in metal mills both in the U.S. and elsewhere. There also was an incident in Texas that involved stolen radioactive devices, which resulted in exposures of members of the general public. Also, the U.S. Nuclear Regulatory Commission took steps to address the underlying problem of inadequate control and accountability of radioactive materials licensed by the Nuclear Regulatory Commission. The Steel Manufacturers Association made available data collected by its members beginning in 1994 that expanded the database for radioactive materials found by the metal recycling industry in recycled metal scrap to over 2,300 reports as of 30 June 1997. PMID:9482594

Lubenau, J O; Yusko, J G

1998-03-01

210

Radioactive Liquid Waste Treatment FacilityDischarges in 2011  

Microsoft Academic Search

This report documents radioactive discharges from the TA50 Radioactive Liquid Waste Treatment Facilities (RLWTF) during calendar 2011. During 2011, three pathways were available for the discharge of treated water to the environment: discharge as water through NPDES Outfall 051 into Mortandad Canyon, evaporation via the TA50 cooling towers, and evaporation using the newly-installed natural-gas effluent evaporator at TA50. Only one

Del Signore; John C

2012-01-01

211

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

212

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

213

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 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. 6 figs.

Gotovchikov, V.T.; Ivanov, A.V.; Filippov, E.A.

1999-03-16

214

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...

215

What a public-relations-model regarding radioactive waste implicates  

SciTech Connect

The behavior of public attitude to radioactive waste with time was investigated by using a mathematical model which was developed for estimating the extent of attitude change, being based on the assumption that the change of public attitude to a certain subject is caused by the information environment mainly formed by the newsmedia. Investigations were also made on the extent the public relations activity can contribute to the change of public opinion for the radioactive waste, and on the method of assortment and execution of various types of activity which brings the maximum change of attitude under a given condition of budget.

Ohnishi, Teruaki [CRC Research Institute, Inc., Tokyo (Japan); [Energy Research Center Wakasa Bay, Fukui (Japan)

1996-12-31

216

Geohydrologic aspects for siting and design of low-level radioactive-waste disposal  

Microsoft Academic Search

The objective for siting and design of low-level radioactive-waste repository sites is to isolate the waste from the biosphere until the waste no longer poses an unacceptable hazard. Low-level radioactive waste commonly is isolated at shallow depths with various engineered features to stabilize the waste and to reduce its dissolution and transport by groundwater. Low-level radioactive waste may need to

Bedinger

1991-01-01

217

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

218

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

219

Theoretical modeling of crevice and pitting corrosion processes in relation to corrosion of radioactive waste containers  

SciTech Connect

A mathematical and numerical model for evaluation of crevice and pitting corrosion in radioactive waste containers is presented. The model considers mass transport, mass transfer at the metal/solution interface, and chemical speciation in the corrosion cavity. The model is compared against experimental data obtained in artificial crevices. Excellent agreement is found between modeled and experimental values. The importance of full consideration of complex ion formation in the aqueous solution is emphasized and illustrated. 10 refs., 5 figs.

Walton, J.C. (Idaho National Engineering Lab., Idaho Falls, ID (USA))

1989-09-09

220

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

221

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

222

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

223

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

224

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

225

Automated NDT techniques in radioactive waste management  

SciTech Connect

The prime NDT method selected for characterization of the waste is real-time x-radiography (RTR). An RTR system specifically designed for the TRU waste inspection is currently being used to develop the best techniques for waste certification. It is based on a standard 420 kV constant potential x-ray machine with a rare-earth fluorescing screen (gadolinium oxysulfide) functioning as an image converter. The low-light-level image produced on the screen is picked up by a CCTV camera with an image intensifier coupled to a plumbicon imaging tube. The system was designed for automated waste container handling and translation. Image analysis is not currently automated, although the CCTV image is digitized to allow signal averaging and edge enhancement through digital filtering. The digitized image is available through an IEEE 488 I/O port for more sophisticated computerized analysis.

Barna, B.A.; Brown, B.W.; Anderson, B.C.

1983-01-01

226

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

227

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

SciTech Connect

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

228

High level radioactive waste glass production and product description  

SciTech Connect

This report examines borosilicate glass as a means of immobilizing high-level radioactive wastes. Borosilicate glass will encapsulate most of the defense and some of the commercial HLW in the US. The resulting waste forms must meet the requirements of the WA-SRD and the WAPS, which include a short term PCT durability test. The waste form producer must report the composition(s) of the borosilicate waste glass(es) produced but can choose the composition(s) to meet site-specific requirements. Although the waste form composition is the primary determinant of durability, the redox state of the glass; the existence, content, and composition of crystals; and the presence of glass-in-glass phase separation can affect durability. The waste glass should be formulated to avoid phase separation regions. The ultimate result of this effort will be a waste form which is much more stable and potentially less mobile than the liquid high level radioactive waste is currently.

Sproull, J.F.; Marra, S.L.; Jantzen, C.M.

1993-12-01

229

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

230

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

Code of Federal Regulations, 2010 CFR

...false Waste specific prohibitions-toxicity characteristic metal wastes. 268...34 Waste specific prohibitions—toxicity characteristic metal wastes...secondary lead smelting which exhibits the Toxicity Characteristic due to the presence...

2010-07-01

231

Beneficial role of conflict in radioactive waste management programs  

SciTech Connect

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 in the value orientation of certain groups and in differing perceptions of risk. Research on similar controversial issues reveals that conflict may be beneficial in the long run by contributing to the public's participation level and understanding of the issues, and to the decision-makers' appreciation of the lay perspective. The paper is in three parts. First, we review the sources of conflict over radioactive waste management issues. The negative attitudes and fears of the public toward different types of projects involving radioactivity, value conflicts, and differential perceptions of risk are cited as sources. Next we discuss the consequences of conflict in terms of sociological theory. Finally, we discuss how conflict can be directed and managed to produce an informed decision-making process. When the public is sensitized to an issue, when prevailing attitudes on the issue are negative, and when perceived risks are high - all of which are characteristic of waste management issues - specific steps should be taken to establish a legitimate process of communication and interaction between the public and the sponsor agency. When conflict is recognized as inevitable, the goal of a communications program is no longer to avoid it. It is to use the increased awareness to increase knowledge about waste management issues and public participation in decisions so that the final solution is acceptable at some level to all parties.

Payne, B.A.; Williams, R.G.

1985-01-01

232

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

Federal Register 2010, 2011, 2012, 2013

...License To Import Radioactive Waste Pursuant to 10 CFR 110.70...EnergySolutions, August 27, Radioactive waste 1,000 tons Incineration for Germany. 2010, November...materials for EnergySolutions incineration. in Oak Ridge, TN. The...

2010-11-30

233

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

234

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

235

Introduction to Nuclear Waste Management Nuclear Waste is a type of radioactive waste that is usually the by-product of  

E-print Network

Introduction to Nuclear Waste Management Nuclear Waste is a type of radioactive waste Meltdowns Bad? - Nuclear Fallout -Water Pollution - Human Health Nuclear Waste Management Elizabeth McKibben, Kedar Mahagaokar, Dimitri Livitz, Marco Eres University of Massachusetts, Amherst

Auerbach, Scott M.

236

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

237

Immobilization of hazardous and radioactive wastes into glass structures  

SciTech Connect

As a result of more than three decades of international research, glass has emerged as the material of choice for immobilization of a wide range of potentially hazardous radioactive and non-radioactive materials. The ability of glass structures to incorporate and then immobilize many different elements into durable, high integrity, waste glass products is a direct function of the unique random network structure of the glassy state. Every major country involved with long-term management of high-level radioactive waste (HLW) has either selected or is considering glass as the matrix of choice for immobilizing and ultimately, disposing of the potentially hazardous, high-level radioactive material. There are many reasons why glass is preferred. Among the most important considerations are the ability of glass structures to accommodate and immobilize the many different types of radionuclides present in HLW, and to produce a product that not only has excellent technical properties, but also possesses good processing features. Good processability allows the glass to be fabricated with relative ease even under difficult remote-handling conditions necessary for vitrification of highly radioactive material. The single most important property of the waste glass produced is its ability to retain hazardous species within the glass structure and this is reflected by its excellent chemical durability and corrosion resistance to a wide range of environmental conditions.

Wicks, G.G.

1997-10-01

238

Commercial low-level radioactive waste transportation liability and radiological risk  

SciTech Connect

This report was prepared for States, compact regions, and other interested parties to address two subjects related to transporting low-level radioactive waste to disposal facilities. One is the potential liabilities associated with low-level radioactive waste transportation from the perspective of States as hosts to low-level radioactive waste disposal facilities. The other is the radiological risks of low-level radioactive waste transportation for drivers, the public, and disposal facility workers.

Quinn, G.J.; Brown, O.F. II; Garcia, R.S.

1992-08-01

239

Commercial low-level radioactive waste transportation liability and radiological risk  

Microsoft Academic Search

This report was prepared for States, compact regions, and other interested parties to address two subjects related to transporting low-level radioactive waste to disposal facilities. One is the potential liabilities associated with low-level radioactive waste transportation from the perspective of States as hosts to low-level radioactive waste disposal facilities. The other is the radiological risks of low-level radioactive waste transportation

G. J. Quinn; O. F. II Brown; R. S. Garcia

1992-01-01

240

Analysis of local acceptance of a radioactive waste disposal facility.  

PubMed

Like many other countries in the world, Korea has struggled to site a facility for radioactive waste for almost 30 years because of the strong opposition from local residents. Finally, in 2005, Gyeongju was established as the first Korean site for a radioactive waste facility. The objectives of this research are to verify Gyeongju citizens' average level of risk perception of a radioactive waste disposal facility as compared to other risks, and to explore the best model for predicting respondents' acceptance level using variables related to cost-benefit, risk perception, and political process. For this purpose, a survey is conducted among Gyeongju residents, the results of which are as follows. First, the local residents' risk perception of an accident in a radioactive waste disposal facility is ranked seventh among a total of 13 risks, which implies that nuclear-related risk is not perceived very highly by Gyeongju residents; however, its characteristics are still somewhat negative. Second, the comparative regression analyses show that the cost-benefit and political process models are more suitable for explaining the respondents' level of acceptance than the risk perception model. This may be the result of the current economic depression in Gyeongju, residents' familiarity with the nuclear industry, or cultural characteristics of risk tolerance. PMID:18627537

Chung, Ji Bum; Kim, Hong-Kew; Rho, Sam Kew

2008-08-01

241

Future costs of low-level radioactive waste disposal  

Microsoft Academic Search

US Ecology is in the forefront of the development of future low-level radioactive waste (LLRW) disposal facilities with its current projects in California and Nebraska. As the site characterization work proceeds and engineering efforts become refined, new cost estimates are made that can be used to predict a major component of future disposal costs. The unknown portion of disposal costs

Scoville

1989-01-01

242

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

243

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

244

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

245

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...

246

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

247

High?level radioactive waste management in the USA  

Microsoft Academic Search

High?level radioactive waste (HLW) disposal policy in the USA since 1987 has focused on a site in volcanic tuffs 305 meters beneath Yucca Mountain, Nevada, with current plans calling for the repository to be opened in 2017 subject to approval by the Obama Administration. Yet the offsite radiation release standards of the US Environmental Protection Agency are still being finalized,

Barry D. Solomon

2009-01-01

248

Biological Information Document, Radioactive Liquid Waste Treatment Facility  

Microsoft Academic Search

This document is intended to act as a baseline source material for risk assessments which can be used in Environmental Assessments and Environmental Impact Statements. The current Radioactive Liquid Waste Treatment Facility (RLWTF) does not meet current General Design Criteria for Non-reactor Nuclear Facilities and could be shut down affecting several DOE programs. This Biological Information Document summarizes various biological

Biggs

1995-01-01

249

Driving Forces and Priorities in the Hungarian Radioactive Waste Management  

SciTech Connect

Hungary, being a candidate state to the European Union, pays particular attention to the measures that are typically considered as good practice within the EU when developing and implementing its national program for the safe management of spent fuel and radioactive waste. The Public Agency for Radioactive Waste Management (PURAM) has been designated to carry out the multilevel tasks in the field of radioactive waste management. In accordance with changes in infrastructure, Hungary is about to make significant strategic and technical decisions. There are several technical priorities for the coming years, such as improving the existing L/ILW repository, construction of a new repository for L/ILW, extension of the interim storage facility for spent fuel and setting up a revised back-end policy. Preparations for decommissioning of the nuclear facilities have to be developed as well. The paper outlines the main problem areas as well as the approach to managing radioactive wastes. It will be concluded that priorities can be set, but key dates and deadlines will always contain an element of uncertainty due to public and political acceptance problems.

Takats, F.; Ormai, P.

2002-02-26

250

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

251

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

252

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

253

Integrated approach to hazardous and radioactive waste remediation  

SciTech Connect

The US Department of Energy Office of Technology Development is supporting the demonstration, and evaluation of a suite of waste retrieval technologies. An integration of leading-edge technologies with commercially available baseline technologies will form a comprehensive system for effective and efficient remediation of buried waste throughout the complex of DOE nuclear facilities. This paper discusses the complexity of systems integration, addressing organizational and engineering aspects of integration as well as the impact of human operators, and the importance of using integrated systems in remediating buried hazardous and radioactive waste.

Hyde, R.A.; Reece, W.J.

1994-11-01

254

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

...Class C waste, and other radioactive waste storage and handling. 72.128 Section 72...LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL...C waste, and other radioactive waste storage and handling. (a) Spent fuel,...

2010-01-01

255

Management of ocean disposal of radioactive wastes: a basis for the control of other pollutants  

SciTech Connect

To manage, on a scientific basis, the quantities of all kinds of waste disposal to coastal waters and open oceans it is necessary to assess the environmental or assimilative capacity for these materials which will not result in an unacceptable biological impact upon the components of the ecosystem nor on man who uses its resources. One approach available is that which has been demonstrated for the management of the disposal of radioactive wastes to the oceans. Methodologies have been developed, both generic and site-specific, which allow the relationship between discharge or release rate and the radiation dose to be established. Guidelines and recommendations which govern acceptable radiation exposed to man have been developed by the International Commission on Radiological Protection (ICRP). These methodologies developed for the control of radioactive wastes can be applied directly for public health protection for non-radioactive wastes such as metals and organochlorine pesticides. ICRP recommendations on justification and optimization can be integrated into an overall management philosophy in order to quantify alternative waste disposal options.

Templeton, W.L.

1981-09-01

256

[Radioactive waste due to electric power and mineral fertiliser production].  

PubMed

Radiation Protection Unit of the Institute for Medical Research and Occupational Health in Zagreb has been conducting systematic investigations of radioactive contamination of the Croatian environment by anthropogenic fission products as well as by naturally occurring radioactive material (NORM) since 1963. Several critical sites in Croatia were identified for NORM, that is, for slag and ash repositories from coal-fired power plants and phosphogypsum repository from a mineral fertilizer production plant. As the coals and phosphate ores contain naturally occurring radionuclides, especially the members of the uranium and thorium radioactive chains, utilising these materials in various industries only enhances their natural radioactivity in residual waste. Consequently, the resulting activity concentrations of natural radionuclides in waste material could be several times higher than in the adjacent soil. These deposited materials pose permanent risk of radiation exposure due to the long physical half-life of natural radionuclides (e.g., T 1/2 = 1600 years for 226Ra). Results of scientific investigations related to natural radioactivity are used in the recovery of slag and ash repositories and landfills, as well as in establishing regulatory criteria targeting import of coal and phosphate ores. In consequence, recently measured activity concentrations of natural radioactivity in imported materials used nowadays in coal-fired power plants are significantly lower than in previously used raw materials. Therefore, slag and ash can be used as additive materials in cement production. PMID:17121006

Marovi?, Gordana; Sencar, Jasminka; Bronzovi?, Maja; Frani?, Zdenko; Kovac, Jadranka

2006-09-01

257

Low-level radioactive waste management: federal-state cooperation or confusion  

Microsoft Academic Search

This paper describes and analyzes the legislative history of the Low-Level Radioactive Waste Policy Act of 1980 and discusses major issues and problems resulting from the implementation of the Act. Five specific issues addressed in this paper are: what radioactive waste constitutes ''low-level radioactive waste'' within the meaning of the Act; what responsibilities, if any, do the states have to

2009-01-01

258

MONTE CARLO SIMULATION OF RADIONUCLIDE MIGRATION IN FRACTURED ROCK FOR THE PERFORMANCE ASSESSMENT OF RADIOACTIVE WASTE  

E-print Network

for chemical or low-level radioactive wastes, or the Performance Assessment (PA) of geological repositories OF RADIOACTIVE WASTE REPOSITORIES F. Cadini1 , J. De Sanctis1 , I. Bertoli1 , E. Zio1,2 1 Dipartimento di Energia is a fundamental task in any performance assessment aimed at verifying the protection offered by radioactive waste

Paris-Sud XI, Université de

259

78 FR 7818 - 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...Eastern Technologies, Inc.; Class A radioactive The total Amend to: 1) Remove Mexico...from the (ETI) facility, the Class A radioactive secondary waste will waste...

2013-02-04

260

Radioactive waste management treatments: A selection for the Italian scenario  

SciTech Connect

The increased attention for radioactive waste management is one of the most peculiar aspects of the nuclear sector considering both reactors and not power sources. The aim of this paper is to present the state-of-art of treatments for radioactive waste management all over the world in order to derive guidelines for the radioactive waste management in the Italian scenario. Starting with an overview on the international situation, it analyses the different sources, amounts, treatments, social and economic impacts looking at countries with different industrial backgrounds, energetic policies, geography and population. It lists all these treatments and selects the most reasonable according to technical, economic and social criteria. In particular, a double scenario is discussed (to be considered in case of few quantities of nuclear waste): the use of regional, centralized, off site processing facilities, which accept waste from many nuclear plants, and the use of mobile systems, which can be transported among multiple nuclear sites for processing campaigns. At the end the treatments suitable for the Italian scenario are presented providing simplified work-flows and guidelines. (authors)

Locatelli, G. [Univ. of Lincoln, Lincoln School of Engineering, Brayford Pool - Lincoln LN6 7TS (United Kingdom); Mancini, M. [Politecnico di Milano, Dept. of Management, Economics and Industrial Engineering, Via Lambruschini 4/B, Milano (Italy); Sardini, M. [Politecnico di Milano, Dept. of Energy, Via Lambruschini 4, Milano (Italy)

2012-07-01

261

Low-level radioactive waste source terms for the 1992 integrated data base  

SciTech Connect

This technical manual presents updated generic source terms (i.e., unitized amounts and radionuclide compositions) which have been developed for use in the Integrated Data Base (IDB) Program of the U.S. Department of Energy (DOE). These source terms were used in the IDB annual report, Integrated Data Base for 1992: Spent Fuel and Radioactive Waste Inventories, Projections, and Characteristics, DOE/RW-0006, Rev. 8, October 1992. They are useful as a basis for projecting future amounts (volume and radioactivity) of low-level radioactive waste (LLW) shipped for disposal at commercial burial grounds or sent for storage at DOE solid-waste sites. Commercial fuel cycle LLW categories include boiling-water reactor, pressurized-water reactor, fuel fabrication, and uranium hexafluoride (UF{sub 6}) conversion. Commercial nonfuel cycle LLW includes institutional/industrial (I/I) waste. The LLW from DOE operations is category as uranium/thorium fission product, induced activity, tritium, alpha, and {open_quotes}other{close_quotes}. Fuel cycle commercial LLW source terms are normalized on the basis of net electrical output [MW(e)-year], except for UF{sub 6} conversion, which is normalized on the basis of heavy metal requirement [metric tons of initial heavy metal ]. The nonfuel cycle commercial LLW source term is normalized on the basis of volume (cubic meters) and radioactivity (curies) for each subclass within the I/I category. The DOE LLW is normalized in a manner similar to that for commercial I/I waste. The revised source terms are based on the best available historical data through 1992.

Loghry, S L; Kibbey, A H; Godbee, H W; Icenhour, A S; DePaoli, S M

1995-01-01

262

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

263

Training requirements and responsibilities for the Buried Waste Integrated Demonstration at the Radioactive Waste Management Complex  

Microsoft Academic Search

The Buried Waste Integrated Demonstration (BWID) is scheduled to conduct intrusive (hydropunch screening tests, bore hole installation, soil sampling, etc.) and nonintrusive (geophysical surveys) studies at the Radioactive Waste Management Complex (RWMC). These studies and activities will be limited to specific locations at the RWMC. The duration of these activities will vary, but most tasks are not expected to exceed

H. G. Vega; S. B. French; D. L. Rick

1992-01-01

264

Incineration of Low Level Radioactive Vegetation for Waste Volume Reduction  

SciTech Connect

The DOE changing mission at Savannah River Site (SRS) are to increase activities for Waste Management and Environmental Restoration. There are a number of Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) locations that are contaminated with radioactivity and support dense vegetation, and are targeted for remediation. Two such locations have been studied for non-time critical removal actions under the National Contingency Plan (NCP). Both of these sites support about 23 plant species. Surveys of the vegetation show that radiation emanates mainly from vines, shrubs, and trees and range from 20,000 to 200,000 d/m beta gamma. Planning for removal and disposal of low-level radioactive vegetation was done with two principal goals: to process contaminated vegetation for optimum volume reduction and waste minimization, and for the protection of human health and environment. Four alternatives were identified as candidates for vegetation removal and disposal: chipping the vegetation and packing in carbon steel boxes (lined with synthetic commercial liners) and disposal at the Solid Waste Disposal Facility at SRS; composting the vegetation; burning the vegetation in the field; and incinerating the vegetation. One alternative `incineration` was considered viable choice for waste minimization, safe handling, and the protection of the environment and human health. Advantages and disadvantages of all four alternatives considered have been evaluated. For waste minimization and ultimate disposal of radioactive vegetation incineration is the preferred option. Advantages of incineration are that volume reduction is achieved and low-level radioactive waste are stabilized. For incineration and final disposal vegetation will be chipped and packed in card board boxes and discharged to the rotary kiln of the incinerator. The slow rotation and longer resident time in the kiln will ensure complete combustion of the vegetative material.

Malik, N.P.S.; Rucker, G.G.; Looper, M.G.

1995-03-01

265

Review process for low-level radioactive waste disposal license application under Low-Level Radioactive Waste Policy Amendments Act  

Microsoft Academic Search

This document estimates the level of effort and expertise that is needed to review a license application within the required time. It is intended to be used by the NRC staff as well as States and interested parties to provide a better understanding of what the NRC envisions will be involved in licensing a low-level radioactive waste disposal facility. 5

Pittiglio; C. L. Jr

1987-01-01

266

Behavior of radioactive iodine and technetium in the spray calcination of high-level waste  

SciTech Connect

The Remote Laboratory-Scale Waste Treatment Facility (RLSWTF) was designed and built as a part of the High-Level Waste Immobilization Program (now the High-Level Waste Process Development Program) at the Pacific Northwest Laboratory. In this facility, which is installed in a radiochemical cell, small volumes of radioactive liquid wastes can be solidified, the process off gas can be analyzed, and the methods for decontaminating this off gas can be tested. Initial operations were completed with nonradioactive, simulated waste solutions (Knox, Siemens and Berger 1981). The first radioactive operations in this facility were performed with a simulated, commercial waste composition containing tracer levels of /sup 99/Tc and /sup 131/I. This report describes the facility and test operations and presents the results of the behavior of /sup 131/I and /sup 99/Tc during solidification of radioactive liquid wastes. During the spray calcination of commercial high-level liquid waste spiked with /sup 99/Tc and /sup 131/I, there was a 0.3 wt% loss of particulates, a 0.15 wt% loss of /sup 99/Tc and a 31 wt% loss of /sup 131/I past the sintered-metal filters. These filters and a venturi scrubber were very efficient in removing particulates and /sup 99/Tc from the off-gas stream. Liquid scrubbers were not efficient in removing /sup 131/I, as 25% of the total lost went to the building off-gas system. Therefore, solid adsorbents will be needed to remove iodine. For all future RLSWTF operations where iodine is present, a silver zeolite adsorber will be used.

Knox, C.A.; Farnsworth, R.K.

1981-08-01

267

Separation of critical radioactive and non-radioactive species from aqueous waste streams.  

PubMed

The separation of radioactive and non-radioactive species from the simulated DOE neutralized current acid waste (NCAW) stream was studied. Cation and anion species were referred to their possible basic compounds, and divided into seven groups (nitrate, phosphate, sulfate, fluoride, nitrite, carbonate, and hydroxide). The nitrate group (the major anion in the DOE waste streams) contains several cations species, while the rest of the groups are only in the form of sodium. The precipitation measurements were conducted in three experimental stages. In the first stage, the precipitation of sodium sulfate, sodium phosphate, sodium-sulfate-phosphate, and aluminum nitrate systems were studied using isopropylamine (IPA) as a precipitation solvent. The objectives of this stage were to evaluate the precipitation ability of IPA in precipitating these compounds individually, and to validate the consistency of the analytical instruments and the employed experimental procedure. Tests performed on the acquired data indicated a high level of experimental consistency. The removal of phosphate, sulfate and aluminum were very high. In the second stage, the precipitation studies were conducted on the: (1) nitrate group alone; (2) binary groups containing the groups of nitrate-phosphate, nitrate-sulfate, nitrate-fluoride, nitrate-nitrite, and nitrate-carbonate; (3) combined nitrate, phosphate, sulfate, and fluoride groups and (4) combined nitrate, phosphate, sulfate, fluoride, nitrite, and carbonate groups. IPA was used as a precipitation solvent. The objectives of this stage were to evaluate the interactions of these groups in the absence of the hydroxide group (e.g. DOE acid-dissolved sludge and acidified supernate streams), and the influence of such interactions on the individual removal of the targeted species. The removal of the aluminum, phosphate, fluoride, and alkaline cations were significantly high (reached 99.9%). The removal of sulfate were moderately high (reached 87%), and the removal of nitrate and alkali cations including cesium were to some extent low (reached about 50%). In the third stage, the precipitation of inorganic species from the simulated NCAW stream was studied using IPA and ethylamine (EA). The precipitation process is very feasible for reducing the radioactivity contents of alkaline cations. However, the process is less effective in separating alkali cations including cesium. The removal of polyvalent transition metals such as aluminum ion is negatively influenced by the significant presence of hydroxide. While the process is effectively capable of separating phosphate, fluoride, and sulfate, it is significantly less effective in separating nitrate and nitrite. A previously derived thermodynamics framework was used to model the precipitation measurements. The framework provided two predictive equations (the 2-Suffix and 3-Suffix equations). Both equations were reasonably adequate for predicting the solubility phase behavior of tested inorganic species in a mixed-solvents mixture as well as for estimating optimum interaction parameters. However, the 3-Suffix equation was better than the 2-Suffix equation. The parameters were useful for estimating the: (1) precipitation fractions (%P) of the studied species, for instance, at different concentration levels of similar targeted species, or in different waste streams with similar or approximate abundance of species, or at different solvents volume ratio (V(r)) where no experimental data are available. PMID:11230913

Bader, M S

2001-03-30

268

Guidelines for generators of hazardous chemical waste at LBL and guidelines for generators of radioactive and mixed waste at LBL  

SciTech Connect

In part one of this document the Governing Documents and Definitions sections provide general guidelines and regulations applying to the handling of hazardous chemical wastes. The remaining sections provide details on how you can prepare your waste properly for transport and disposal. They are correlated with the steps you must take to properly prepare your waste for pickup. The purpose of the second part of this document is to provide the acceptance criteria for the transfer of radioactive and mixed waste to LBL's Hazardous Waste Handling Facility (HWHF). These guidelines describe how you, as a generator of radioactive or mixed waste, can meet LBL's acceptance criteria for radioactive and mixed waste.

Not Available

1991-09-01

269

LEACHING OF METALS FROM MINERAL PROCESSING WASTE  

EPA Science Inventory

The purpose of this project is to test the leaching of Mineral Processing Waste (MPW) contaminated with heavy metals using scientifically defendable leaching tests other than TCLP. Past experience and literature have shown that TCLP underestimates the levels of metals such as oxo...

270

LEACHING OF METALS FROM MINERAL PROCESSING WASTE  

EPA Science Inventory

The purpose of this project is to test the leaching of Mineral processing Waste (MPW) contaminated with heavy metals using scientifically defendable leaching tests other than TCLP. Past experience and literature have shown that TCLP underestiates the levels of metals such as oxoa...

271

Vapor sampling of the headspaces of radioactive waste storage tanks  

SciTech Connect

At the Hanford Site in southeast Washington State, 177 underground storage tanks have been built since 1943 to store radioactive waste. During the period of 1944 to 1989, wastes were generated from the reprocessing of nuclear fuel and the recovery of radioisotopes. The acidic liquid wastes were neutralized with sodium hydroxide for storage in mild steel, underground storage tanks. The radioactive waste in the tanks at the Hanford Site is composed mostly of water, sodium nitrate, sodium nitrite, sodium aluminate, and sodium hydroxide, with many other compounds in lesser amounts. The waste also contains organic molecules resulting from chelating agents used to recover fission products or solvents that became entrained in the waste through liquid-liquid extraction processes. These organic compounds appear to play a large role in the tanks headspace compositions. Two major classes of waste tanks exist at the Hanford Site: double-shell and single-shell tanks. The 28 double-shell tanks have positive ventilation. Although a few of the 149 inactive single-shell tanks have positive ventilation, most are passively ventilated. It has always been expected that the waste in the tanks will produce hydrogen gas from the radiolysis of water. It should be pointed out that nitrate ion, which is plentiful in the waste, provides some protection to the water from the radiolysis. The result is that all tanks are assumed to generate hydrogen at some low rate. Evaluations and measurements have been performed to determine if radiolytically-produced hydrogen can accumulate in the tank headspaces. As expected, the measurements show values of hydrogen well below the lower flammability limit.

Reynolds, D.A.; Kirch, N.W. [Westinghouse Hanford Company, Richland, WA (United States); Huckaby, J.L. [Pacific Northwest National Lab., Richland, WA (United States)

1996-12-31

272

Managing commercial low-level radioactive waste beyond 1992: Issues and potential problems of temporary storage  

Microsoft Academic Search

In accordance with the Low-Level Radioactive Waste Policy Amendments Act of 1985, States will become responsible for managing low-level radioactive waste, including mixed waste, generated within their borders as of January 1, 1993. In response to this mandate, many States and compact regions have made substantial progress toward establishing new disposal capacity for these wastes. While this progress is noteworthy,

Kerr

1991-01-01

273

Functional design criteria radioactive liquid waste line replacement, Project W-087. Revision 3  

SciTech Connect

This document provides the functional design criteria for the 222-S Laboratory radioactive waste drain piping and transfer pipeline replacement. The project will replace the radioactive waste drain piping from the hot cells in 222-S to the 219-S Waste Handling Facility and provide a new waste transfer route from 219-S to the 244-S Catch Station in Tank Farms.

McVey, C.B.

1994-10-13

274

Functional design criteria radioactive liquid waste line replacement, Project W-087. Revision 3  

Microsoft Academic Search

This document provides the functional design criteria for the 222-S Laboratory radioactive waste drain piping and transfer pipeline replacement. The project will replace the radioactive waste drain piping from the hot cells in 222-S to the 219-S Waste Handling Facility and provide a new waste transfer route from 219-S to the 244-S Catch Station in Tank Farms.

McVey

1994-01-01

275

Geological problems in radioactive waste isolation - second worldwide review  

SciTech Connect

The first world wide review of the geological problems in radioactive waste isolation was published by Lawrence Berkeley National Laboratory in 1991. This review was a compilation of reports that had been submitted to a workshop held in conjunction with the 28th International Geological Congress that took place July 9-19, 1989 in Washington, D.C. Reports from 15 countries were presented at the workshop and four countries provided reports after the workshop, so that material from 19 different countries was included in the first review. It was apparent from the widespread interest in this first review that the problem of providing a permanent and reliable method of isolating radioactive waste from the biosphere is a topic of great concern among the more advanced, as well as the developing, nations of the world. This is especially the case in connection with high-level waste (HLW) after its removal from nuclear power plants. The general concensus is that an adequate isolation can be accomplished by selecting an appropriate geologic setting and carefully designing the underground system with its engineered barriers. This document contains the Second Worldwide Review of Geological Problems in Radioactive Waste Isolation, dated September 1996.

Witherspoon, P.A. [ed.

1996-09-01

276

Determination of Iodine-129 in Low Level Radioactive Wastes - 13334  

SciTech Connect

For the radioactivity determination of {sup 129}I in the radioactive wastes, alkali fusion and anion-exchange resin separation methods, which are sample pretreatment methods, have been investigated in this study. To separate and quantify the {sup 129}I radionuclide in an evaporator bottom and spent resin, the radionuclide was chemically leached from the wastes and adsorbed on an anion exchange resin at pH 4, 7, 9. In the case of dry active waste and another solid type, the alkali fusion method was applied. KNO{sub 3} was added as a KOH and oxidizer to the wastes. It was then fused at 450 deg. C for 1 hour. The radioactivity of the separated iodine was measured with a low energy gamma spectrometer after the sample pretreatment. Finally, it was confirmed that the recovery rate of the iodine for the alkali fusion method was 83.6±3.8%, and 86.4±1.6% for the anionic exchange separation method. (authors)

Choi, K.C.; Ahn, J.H.; Park, Y.J.; Song, K.S. [Nuclear Chemistry Research Division, Korea Atomic Energy Research Institute, Daejeon, 305-600 (Korea, Republic of)] [Nuclear Chemistry Research Division, Korea Atomic Energy Research Institute, Daejeon, 305-600 (Korea, Republic of)

2013-07-01

277

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

278

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

279

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

280

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

281

Low-level radioactive waste form qualification testing  

SciTech Connect

This report summarizes activities that have already been completed as well as yet to be performed by the Idaho National Engineering and Environmental Laboratory (INEEL) to develop a plan to quantify the behavior of radioactive low-level waste forms. It briefly describes the status of various tasks, including DOE approval of the proposed work, several regulatory and environmental related documents, tests to qualify the waste form, preliminary schedule, and approximate cost. It is anticipated that INEEL and Brookhaven National Laboratory will perform the majority of the tests. For some tests, services of other testing organizations may be used. It should take approximately nine months to provide the final report on the results of tests on a waste form prepared for qualification. It is anticipated that the overall cost of the waste quantifying service is approximately $150,000. The following tests are planned: compression, thermal cycling, irradiation, biodegradation, leaching, immersion, free-standing liquid tests, and full-scale testing.

Sohal, M.S.; Akers, D.W.

1998-06-01

282

RADIOACTIVE LAUNDRY WASTE TREATMENT SYSTEM WITHOUT SECONDARY WASTE GENERATION  

Microsoft Academic Search

A new treatment system for the laundry liquid radwaste generated from nuclear power plant has been developed. The system is composed of a RO membrane module and a UV photo-oxidation reactor. It is designed with the flow rate, 1 ton\\/hr, and the volume reduction fatcor, more than 100. The DF(Decontamination Factor) over 100 is expected for the radioactive cobalt and

Jong-Kil Park; Se-Moon Park; Jong-Bin Kim; Myung-Chan Lee; Myung-Jae Song

2000-01-01

283

Actinide-aluminate Speciation in Alkaline Radioactive Waste  

SciTech Connect

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 their solubility and sorption behavior in tanks, determining whether chemical separations are needed for waste treatment, and designing separations processes. Baseline washing of tank sludges with NaOH solutions is being proposed to reduce the volume of HLW. Alkaline pretreatment of HLW will be needed to remove aluminum [as NaAl(OH)4] because it significantly reduces the HLW volume; however, the aluminate ion [Al(OH)4 -] enhances actinide solubility via an unknown mechanism. Thus, alkaline wash residues may require an additional treatment to remove actinides. The results of this research will determine the nature TRU (U, Np, Pu, Am) speciation with aluminate anions under alkaline, oxidizing tank-like conditions. Specific issues to be addressed include solubility of these actinides, speciation in aluminate-containing alkaline supernatants, the role of actinide redox states on solubility, and partitioning between supernatant and solid phases, including colloids. Studies will include thermodynamics, kinetics, spectroscopy, electrochemistry, and surface science. We have already determined, for example, that certain high valent forms of Np and Pu are very soluble under alkaline conditions due to the formation of anionic hydroxo complexes, AnO2(OH)4 2- and AnO2(OH)5 3-. The presence of aluminate ions causes the actinide solubilities to increase, although the exact species are not known. We are currently characterizing the high valent TRU elements bound to oxo, water, OH-, and Al(OH)4 -, ligands under waste-like conditions. These waste-like conditions are in the range of 1-3 M excess hydroxide, {approx}0.2 M carbonate, {approx}0.5 M aluminate, for a total sodium of 2-4 M. Molecular structure-specific probes include Raman, multinuclear nuclear magnetic resonance (NMR), extended X-ray absorption fine structure (EXAFS), luminescence, optical absorption (UV-Vis-conventional and photoacoustic) spectroscopies. We anticipate that such new knowledge will impact on clean-up approaches to significantly reduce costs, schedules, and risks. Research Progress and Implications: In the first one and one half years of the project we have determined the true role of aluminate [Al(OH)4 -] anions in enhancing solubility of actinide ions. Last year we reported preliminary spectroscopic observations of a new actinide chemical species in the presence of aluminate anions under alkaline, waste tank-like conditions. We postulated that the aluminate anion acted as a ligand to uranium, and that the new compound was an actinide-aluminate coordination complex of high negative charge. More detailed studies aimed at identification of this new species revealed that it is actually a new dimeric uranyl species, and that there is no aluminate anion in the metal coordination sphere. Rather, the data indicate that the aluminate acts as an electrolyte, and increases the hydroxide ion activity and hence the overall solubility via formation of UO2(OH)5 3-. In general, highly charged species are stabilized by high ionic strength. This will have a direct impact on sludge washing using NaOH to remove aluminate ions from the system. Changes in the aluminate concentration effect the position of the equilibrium outlined below. Furthermore, we also find changes in aluminum chemistry based on the presence of uranium, including aluminate precipitation reactions under conditions where the aluminate anions should be solubilized.

Clark, David C.; Krot, Nikolai N.

2000-06-01

284

Radioactive Waste Management information for 1994 and record-to-date  

SciTech Connect

This document, Radioactive Waste Management Information for 1994 and Record-To-Date, contains computerized radioactive waste data records from the Idaho National Engineering Laboratory (INEL). Data are compiled from information supplied by the US Department of Energy (DOE) contractors. Data listed are on airborne and liquid radioactive effluents and solid radioactive waste that is stored, disposed, and sent to the INEL for reduction. Data are summarized for the years 1952 through 1993. Data are detailed for the calendar year 1994.

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

1995-07-01

285

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

286

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

287

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 the Southern States Energy Board (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

1990-11-01

288

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 the Southern States Energy Board (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 sew be supplied to all parties in receipt of this publication provided they remain on the SSEB mailing list.

Not Available

1989-11-01

289

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

290

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

291

High level radioactive waste management facility design criteria  

SciTech Connect

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 the high level waste into a more stable, manageable substance. This paper discuss the structural design requirements for this unique one of a kind facility. A special emphasis will be concentrated on the design criteria pertaining to earthquake, wind and tornado, and flooding.

Sheikh, N.A.; Salaymeh, S.R.

1993-10-01

292

Radioactive waste disposal for fission and fusion reactors  

SciTech Connect

The calculated radioactive waste inventories of the Turkey Point pressurized water fission reactor (PWR) and the Starfire conceptual fusion tokamak are compared as a function of time from initial start-up to 10,000 years after decommissioning. Only material out of reactor at least one year is considered. The total activity in Ci/W(th) of the Starfire tokamak is slightly greater than that of the PWR during the active lifetimes of the two reactors and beyond 1000 years. However, using reduced activation materials in Starfire can result in about 1/2000 as much long-lived radioactivity as in the fission reactor. It is stressed that comparison of wastes on this basis is not straightforward, since the radioisotopes and methods required for their disposal are different for fusion and fission reactors. 2 refs., 1 fig., 2 tabs.

Heinisch, H.L.; Doran, D.G.

1989-01-01

293

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

294

Low level radioactive waste disposal siting: a social and technical plan for Pennsylvania. Volume 3. Technical analyses  

Microsoft Academic Search

Volume III comprises 9 chapters: Definition of Low Level Radioactive Waste; A Perspective on the Relative Toxicity of Low Level Radioactive Waste; A Generic Low Level Radioactive Waste Disposal Facility Description; An Economic Analysis of a Generic Low Level Radioactive Waste Disposal Facility; Site Selection; Geology-Pennsylvania Specific; Technical Considerations; Disposal Cell Stability; and Site Monitoring Considerations.

G. Aron; R. J. Bord; F. A. Clemente; W. P. Dornsife; A. R. Jarrett; W. A. Jester; R. F. Schmalz; W. F. Witzig

1984-01-01

295

[Board on Radioactive Waste Managements action on progress toward objectives  

SciTech Connect

This report is a progress report to the US DOE from the Board on Radioactive Waste Management (BRWM), which summarizes the activities of the board during the period December 1, 1993 to May 2, 1994. The report summarizes the meetings of the board as a whole, of various of its subcommittees, and of activities it has undertaken to further its original mission. This board is associated with the National Research Council to give advice to US DOE.

Not Available

1994-11-28

296

Russian Containers for Transportation of Solid Radioactive Waste  

Microsoft Academic Search

The Russian Shipyard ''Zvyozdochka'' has designed a new container for transportation and storage of solid radioactive wastes. The PST1A-6 container is cylindrical shaped and it can hold seven standard 200-liter (55-gallon) drums. The steel wall thickness is 6 mm, which is much greater than standard U.S. containers. These containers are fully certified to the Russian GOST requirements, which are basically

Vladimir G. Petrushenko; Edward P. Baal; Dmitry Yu. Tsvetkov; V. R. Korb; Vladimir S. Nikitin; A. A. Mikheev; Andrew Griffith; Patrick Schwab; Ashot Nazarian

2002-01-01

297

Condition assessment of the Los Alamos National Laboratory radioactive liquid waste collection system  

Microsoft Academic Search

The radioactive liquid waste collection system (RLWCS) at Los Alamos National Laboratory (LANE) is a site-wide double-encased piping system installed in 1982 that allows radioactive liquid waste (RLW) producing facilities to gravity drain their waste to the radioactive liquid waste treatment facility (RLWTF) through a system of underground high-density polyethylene (HDPE) pipes and vaults. The RLWCS stretches approximately four miles

G. L. Edgemon; W. D. Moss; V. P. Worland

2004-01-01

298

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.

Steinhäusler, Friedrich

2010-10-01

299

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

300

Savannah River Site chemical, metal, and pesticide (CMP) waste vitrification treatability studies  

SciTech Connect

Numerous Department of Energy (DOE) facilities, as well as Department of Defense (DOD) and commercial facilities, have used earthen pits for disposal of chemicals, organic contaminants, and other waste materials. Although this was an acceptable means of disposal in the past, direct disposal into earthen pits without liners or barriers is no longer a standard practice. At the Savannah River Site (SRS), approximately three million pounds of such material was removed from seven chemical, metal, and pesticide disposal pits. This material is known as the Chemical, Metal, and Pesticide (CMP) Pit waste and carries several different listed waste codes depending on the contaminants in the respective storage container. The waste is not classified as a mixed waste because it is believed to be non-radioactive; however, in order to treat the material in a non-radioactive facility, the waste would first have to be screened for radioactivity. The Defense Waste Processing Technology (DWPT) Section of the Savannah River Technology Center (SRTC) was requested by the DOE-Savannah River (SR) office to determine the viability of vitrification of the CMP Pit wastes. Radioactive vitrification facilities exist which would be able to process this waste, so the material would not have to be analyzed for radioactive content. Bench-scale treatability studies were performed by the DWPT to determine whether a homogeneous and durable glass could be produced from the CMP Pit wastes. Homogeneous and durable glasses were produced from the six pits sampled. The optimum composition was determined to be 68.5 wt% CMP waste, 7.2 wt% Na{sub 2}O, 9 wt% CaO, 7.2 wt% Li{sub 2}O and 8.1 wt% Fe{sub 2}O{sub 3}. This glass melted at 1,150 C and represented a two fold volume reduction.

Cicero, C.A.

1997-01-13

301

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

302

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

Code of Federal Regulations, 2011 CFR

...reactor-related greater than Class C waste, and other radioactive waste storage and handling...Section 72.128 Energy NUCLEAR REGULATORY COMMISSION...INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND...

2011-01-01

303

Radioactive Liquid Waste Treatment Facility Discharges in 2011  

SciTech Connect

This report documents radioactive discharges from the TA50 Radioactive Liquid Waste Treatment Facilities (RLWTF) during calendar 2011. During 2011, three pathways were available for the discharge of treated water to the environment: discharge as water through NPDES Outfall 051 into Mortandad Canyon, evaporation via the TA50 cooling towers, and evaporation using the newly-installed natural-gas effluent evaporator at TA50. Only one of these pathways was used; all treated water (3,352,890 liters) was fed to the effluent evaporator. The quality of treated water was established by collecting a weekly grab sample of water being fed to the effluent evaporator. Forty weekly samples were collected; each was analyzed for gross alpha, gross beta, and tritium. Weekly samples were also composited at the end of each month. These flow-weighted composite samples were then analyzed for 37 radioisotopes: nine alpha-emitting isotopes, 27 beta emitters, and tritium. These monthly analyses were used to estimate the radioactive content of treated water fed to the effluent evaporator. Table 1 summarizes this information. The concentrations and quantities of radioactivity in Table 1 are for treated water fed to the evaporator. Amounts of radioactivity discharged to the environment through the evaporator stack were likely smaller since only entrained materials would exit via the evaporator stack.

Del Signore, John C. [Los Alamos National Laboratory

2012-05-16

304

Teaching Radioactive Waste Management in an Undergraduate Engineering Program - 13269  

SciTech Connect

The University of Ontario Institute of Technology is Ontario's newest university and the only one in Canada that offers an accredited Bachelor of Nuclear Engineering (Honours) degree. The nuclear engineering program consists of 48 full-semester courses, including one on radioactive waste management. This is a design course that challenges young engineers to develop a fundamental understanding of how to manage the storage and disposal of various types and forms of radioactive waste, and to recognize the social consequences of their practices and decisions. Students are tasked with developing a major project based on an environmental assessment of a simple conceptual design for a waste disposal facility. They use collaborative learning and self-directed exploration to gain the requisite knowledge of the waste management system. The project constitutes 70% of their mark, but is broken down into several small components that include, an environmental assessment comprehensive study report, a technical review, a facility design, and a public defense of their proposal. Many aspects of the project mirror industry team project situations, including the various levels of participation. The success of the students is correlated with their engagement in the project, the highest final examination scores achieved by students with the strongest effort in the project. (authors)

Ikeda, Brian M. [Faculty of Energy Systems and Nuclear Science, University of Ontario Institute of Technology, 2000 Simcoe Street North, Oshawa, Ontario L1H 7K4 (Canada)] [Faculty of Energy Systems and Nuclear Science, University of Ontario Institute of Technology, 2000 Simcoe Street North, Oshawa, Ontario L1H 7K4 (Canada)

2013-07-01

305

Directions in low-level radioactive waste management. Low-level radioactive waste disposal: commercial facilities no longer operating  

Microsoft Academic Search

This publication discusses three commercial facilities-no longer operating-that have received and now contain low-level radioactive waste. The facilities are located at West Valley, New York; Maxey Flats, Kentucky; and Sheffield, Illinois. All three of the facilities were selected and developed in the 1960s. The onset of water management problems caused the closure of the sites at West Valley and Maxey

R. E. Berlin; P. T. Tuite

1982-01-01

306

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

307

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

308

Gamma monitor for assay of radioactive solid-waste shipments  

SciTech Connect

A gamma waste monitor has been developed and evaluated at the Savannah River Plant (SRP). The purpose of the monitor is to improve estimates of the radionuclides in solid wastes arriving at the plant's burial ground. This monitor, a computer-based spectrometer, quantitatively measures many radionuclides in SRP waste, including waste in heavily shielded shipping casks. Radionuclides emitting gamma rays of sufficient energy to penetrate the shipping container walls can be measured directly. Other radionuclides that are beta emitters or which emit gamma photons too weak to penetrate the walls of the waste containers can often be estimated by their association with measurable gamma photons. Development of the monitor was initiated to find a more accurate method of estimating the quantities of radioactive materials accumulated in the burial ground and to ensure compliance with burial limits imposed by SRP technical standards. Another benefit from the monitor is that it provides specific radionuclide data which are essential to environmental impact evaluations and decommissioning planning. The gamma waste monitor is described. (WHK)

Crawford, J H

1982-06-01

309

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

310

Developments in the control of low-level radioactive waste production  

Microsoft Academic Search

Ontario Hydro owns and operates 16 Canada deuterium uranium (CANDU)-type reactors in 3 multiunit stations. These stations collectively produce approx. 6000 mÂł\\/yr of low-level radioactive solid wastes. All radioactive solid wastes are sent unprocessed to an Ontario-Hydro-owned waste processing and storage site. This site charges approximately $750\\/mÂł of low-level waste (LLW) received. The volume of waste is reduced by incineration

Spooner

1987-01-01

311

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

312

Air pollution control concepts for a low-level radioactive waste incinerator  

Microsoft Academic Search

The Low-Level Radioactive Waste Policy Act Amendments of 1985 placed a due imperative on the development of additional options for disposal of low-level radioactive waste (LLRW). These amendments allowed surcharges on land disposal of LLRW and provided a time table for individual regions to site, develop and implement regional waste disposal practices. Surcharges, beginning at $10 per cubic foot, placed

1987-01-01

313

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

Microsoft Academic Search

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

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

2003-01-01

314

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

315

Potential for radioactive patient excreta in hospital trash and medical waste  

Microsoft Academic Search

Radioactive excreta from nuclear medicine patients can enter solid waste as common trash and medical biohazardous waste. Many landfills and transfer stations now survey these waste streams with scintillation detectors which may result in rejection of a hospital`s waste. Our survey indicated that on the average either or both of Boston University Medical Center Hospital`s waste streams can contain detectable

Victor Evdokimoff; Charles Cash; Kevin Buckley; Ariosto Cardenas

1994-01-01

316

Potential for radioactive patient excreta in hospital trash and medical waste  

SciTech Connect

Radioactive excreta from nuclear medicine patients can enter solid waste as common trash and medical biohazardous waste. Many landfills and transfer stations now survey these waste streams with scintillation detectors which may result in rejection of a hospital`s waste. Our survey indicated that on the average either or both of Boston University Medical Center Hospital`s waste streams can contain detectable radioactive excreta on a weekly basis. To avoid potential problems, radiation detectors were installed in areas where housekeepers carting trash and medical waste must pass through to ensure no radioactivity leaves the institution. 3 refs.

Evdokimoff, V.; Cash, C.; Buckley, K. [Boston Univ. Medical Center, MA (United States)] [and others

1994-02-01

317

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

Federal Register 2010, 2011, 2012, 2013

...GE Hitachi Nuclear Energy, LLC. Radioactive waste Up to 210 Cobalt- Recycling, China August 1, 2011, August 5, consisting of 60 sealed forensic testing 2011, IW030. used Cobalt-60 sources. or storage and radioactive Combined total...

2011-08-30

318

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

319

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

320

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

2011-03-01

321

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

322

Heavy metal distribution in household waste  

Microsoft Academic Search

The present study was undertaken at the request of the French Ministry of Environment with the help of the national agency for waste recovery and disposal (ANRED) and the company Valorga. The aim of this paper is to report the original methods of assessment and relevant results in visual form. Knowledge of the distribution of each heavy metal (mercury, cadmium,

P. Rosseaux; A. Navarro; P. Vermande

1989-01-01

323

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

324

DOE site performance assessment activities. Radioactive Waste Technical Support Program  

SciTech Connect

Information on performance assessment capabilities and activities was collected from eight DOE sites. All eight sites either currently dispose of low-level radioactive waste (LLW) or plan to dispose of LLW in the near future. A survey questionnaire was developed and sent to key individuals involved in DOE Order 5820.2A performance assessment activities at each site. The sites surveyed included: Hanford Site (Hanford), Idaho National Engineering Laboratory (INEL), Los Alamos National Laboratory (LANL), Nevada Test Site (NTS), Oak Ridge National Laboratory (ORNL), Paducah Gaseous Diffusion Plant (Paducah), Portsmouth Gaseous Diffusion Plant (Portsmouth), and Savannah River Site (SRS). The questionnaire addressed all aspects of the performance assessment process; from waste source term to dose conversion factors. This report presents the information developed from the site questionnaire and provides a comparison of site-specific performance assessment approaches, data needs, and ongoing and planned activities. All sites are engaged in completing the radioactive waste disposal facility performance assessment required by DOE Order 5820.2A. Each site has achieved various degrees of progress and have identified a set of critical needs. Within several areas, however, the sites identified common needs and questions.

Not Available

1990-07-01

325

Characteristics of solidified products containing radioactive molten salt waste.  

PubMed

The molten salt waste from a pyroprocess to recover uranium and transuranic elements is one of the problematic radioactive wastes to be solidified into a durable wasteform for its final disposal. By using a novel method, named as the GRSS (gel-route stabilization/solidification) method, a molten salt waste was treated to produce a unique wasteform. A borosilicate glass as a chemical binder dissolves the silicate compounds in the gel products to produce one amorphous phase while most of the phosphates are encapsulated by the vitrified phase. Also, Cs in the gel product is preferentially situated in the silicate phase, and it is vitrified into a glassy phase after a heat treatment. The Sr-containing phase is mainly phosphate compounds and encapsulated by the glassy phase. These phenomena could be identified by the static and dynamic leaching test that revealed a high leach resistance of radionuclides. The leach rates were about 10(-3) - 10(-2) g/m2 x day for Cs and 10(-4) - 10(-3) g/m2 x day for Sr, and the leached fractions of them were predicted to be 0.89% and 0.39% at 900 days, respectively. This paper describes the characteristics of a unique wasteform containing a molten salt waste and provides important information on a newly developed immobilization technology for salt wastes, the GRSS method. PMID:18044538

Park, Hwan-Seo; Kim, In-Tae; Cho, Yong-Zun; Eun, Hee-Chul; Kim, Joon-Hyung

2007-11-01

326

Evaluating detonation possibilities in a Hanford radioactive waste tank  

SciTech Connect

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 101-SY, has been periodically releasing high concentrations of a hydrogen/nitrous oxide/nitrogen/ ammonia gas mixture into the tank dome vapor space. There are concerns that under certain conditions a detonation of the flammable gas mixture may occur. There are two ways that a detonation can occur during a release of waste gases into the dome vapor splice: (1) direct initiation of detonation by a powerful ignition source, and (2) deflagration to detonation transition (DDT). The first case involves a strong ignition source of high energy, high power, or of large size (roughly 1 g of high explosive (4.6 kj) for a stoichiometric hydrogen-air mixture{sup 1}) to directly initiate a detonation by ``shock`` initiation. This strong ignition is thought to be incredible for in-tank ignition sources. The second process involves igniting the released waste gases, which results in a subsonic flame (deflagration) propagating into the unburned combustible gas. The flame accelerates to velocities that cause compression waves to form in front of the deflagration combustion wave. Shock waves may form, and the combustion process may transition to a detonation wave.

Travis, J.R.; Fujita, R.K.; Ross, M.C.; Edwards, J.N. [Los Alamos National Lab., NM (United States); Shepherd, J.E. [California Inst. of Tech., Pasadena, CA (United States)

1994-07-01

327

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. 4 refs., 3 figs.

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

1996-12-31

328

Indiana State Briefing Book for low-level radioactive-waste management  

Microsoft Academic Search

The Indiana State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Indiana. The profile is the result of a survey of

E. L. Mitter; R. D. Hume; H. R. Briggs; E. D. Feigenbaum

1981-01-01

329

THE CURRENT STATUS OF THE ASSURED ISOLATION CONCEPT FOR LOW-LEVEL RADIOACTIVE WASTES  

Microsoft Academic Search

No new full-range low-level radioactive waste disposal facility has been established in the United States since the early seventies. It is also obvious that no additional sites will be established in the near future by any of the low-level radioactive waste state or compact authorities. The near surface and deep geological disposal of low-level radioactive waste seems to be an

David V. LeMone

2000-01-01

330

Development of low-level radioactive waste disposal capacity in the United States - progress or stalemate?  

Microsoft Academic Search

It has been fifteen years since responsibility for the disposal of commercially generated low-level radioactive waste (LLW) was shifted to the states by the United States Congress through the Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA). In December 1985, Congress revisited the issue and enacted the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA). No new disposal sites

J. S. Devgun; G. S. Larson

1995-01-01

331

RSP WASTE UNIVERSITY OF HAWAII RADIOACTIVE WASTE PICKUP REQUEST FORM Revision 06/07 (WASTE WHICH CONTAINS RADIOISOTOPES BUT NO HAZARDOUS CHEMICALS)  

E-print Network

RSP WASTE UNIVERSITY OF HAWAII RADIOACTIVE WASTE PICKUP REQUEST FORM Revision 06/07 (WASTE WHICH CONTAINS RADIOISOTOPES BUT NO HAZARDOUS CHEMICALS) INSTRUCTIONS : 1. *NO ISOTOPES MAY BE MIXED IN THE WASTE BOX! One type of isotope per waste box - Except C-14 AND H-3 WHICH MAY BE DISPOSED OF TOGETHER. 2

Browder, Tom

332

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

333

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

334

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

335

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

336

Geoenvironmental evaluation of geological formations of Lithuania for radioactive waste disposal  

SciTech Connect

The Ignalina Nuclear Power Plant, operating at present in Lithuania, every year produces approximately 1,5 ths.t. of radioactive wastes. They are being stored in temporary areas. The possibilities of underground disposal of radioactive wastes were evaluated. There are three geological formations in Lithuania, which are potentially suitable media for radioactive wastes disposal: Lower proterozoic rocks of crystalline basement, Upper Permian anhydrite layer, and Upper Permian salt domes. They are being proposed in the radioactive wastes management program as candidates for more detail investigations.

Kadunas, V.; Valiunas, J. [Institute of Geology, Vilnius (Lithuania)

1996-12-01

337

Design and testing of wood containers for radioactive waste  

SciTech Connect

A wood container for shipping and storing radioactive waste was designed to eliminate the problems caused by the weight, cost, and shape of the steel containers previously used. Tests specified by federal regulations (compression, free-drop, penetration, and vibration) were conducted on two of the containers, one loaded to 2500 lb and one loaded to 5000 lb. The 5000-lb container failed the free-drop test, but the 2500-lb container easily passed the tests and therefore qualifies as a Type A container. Its simplicity of design, low weight, and ease in handling have proved to be time-saving and cost-effective.

Roberts, R.S.; Barry, P.E.

1981-03-25

338

Naturally occurring crystalline phases: analogues for radioactive waste forms  

SciTech Connect

Naturally occurring mineral analogues to crystalline phases that are constituents of crystalline radioactive waste forms provide a basis for comparison by which the long-term stability of these phases may be estimated. The crystal structures and the crystal chemistry of the following natural analogues are presented: baddeleyite, hematite, nepheline; pollucite, scheelite;sodalite, spinel, apatite, monazite, uraninite, hollandite-priderite, perovskite, and zirconolite. For each phase in geochemistry, occurrence, alteration and radiation effects are described. A selected bibliography for each phase is included.

Haaker, R.F.; Ewing, R.C.

1981-01-01

339

Disposal of liquid radioactive wastes through wells or shafts  

SciTech Connect

This report describes disposal of liquids and, in some cases, suitable solids and/or entrapped gases, through: (1) well injection into deep permeable strata, bounded by impermeable layers; (2) grout injection into an impermeable host rock, forming fractures in which the waste solidifies; and (3) slurrying into excavated subsurface cavities. Radioactive materials are presently being disposed of worldwide using all three techniques. However, it would appear that if the techniques were verified as posing minimum hazards to the environment and suitable site-specific host rock were identified, these disposal techniques could be more widely used.

Perkins, B.L.

1982-01-01

340

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

341

The Black Sea: A Georeactor to Immobilize Metal Wastes  

Microsoft Academic Search

\\u000a Industries in many countries produce a range of metal wastes (metal sludges, residues from etching baths or galvanization\\u000a processes, metal-rich fly ashes, tailings from ore dressing operations, metallurgical slags etc.). If the metals cannot be\\u000a recycled, these wastes are disposed in specially adapted isolated landfills, often after conversion into (hydro-)oxide sludges.\\u000a Such metal-rich waste deposits will require “eternal” monitoring, and

R. D. Schuiling

342

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

343

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

344

Radioactive waste disposal characteristics of candidate tokamak demonstration reactors  

SciTech Connect

Results from the current physics, materials and blanket R and D programs are combined with physics and engineering design constraints to characterize candidate tokamak demonstration plant (DEMO) designs. Blanket designs based on the principal structural materials, breeding materials and coolants being developed for the DEMO were adapted from the literature. Neutron flux and activation calculations were performed, and several radioactive waste disposal indices were evaluated, for each design. Of the primary low-activation structural materials under development in the US, it appears that vanadium and ferritic steel alloys, and possibly silicon carbide, could lead to DEMO designs which could satisfy realistic low-level waste (LLW) criteria, provided that impurities can be controlled within plausible limits. Allowable LLW concentrations are established for the limiting alloying and impurity elements. All breeding materials and neutron multipliers considered meet the LLW criterion.

Hoffman, E.A.; Stacey, W.M.; Hertel, N.E.

1998-08-01

345

Risk methodology for geologic disposal of radioactive waste  

SciTech Connect

This report contains the description of a procedure for selecting scenarios that are potentially important to the isolation of high- level radioactive wastes in deep geologic formations. In this report, the term scenario is used to represent a set of naturally occurring and/or human-induced conditions that represent realistic future states of the repository, geologic systems, and ground-water flow systems that might affect the release and transport of radionuclides from the repository to humans. The scenario selection procedure discussed in this report is demonstrated by applying it to the analysis of a hypothetical waste disposal site containing a bedded-salt formation as the host medium for the repository. A final set of 12 scenarios is selected for this site. 52 refs., 48 figs., 5 tabs.

Cranwell, R.M.; Campbell, J.E.; Ortiz, N.R. (Sandia National Labs., Albuquerque, NM (USA)); Guzowski, R.V. (Science Applications International Corp., Albuquerque, NM (USA))

1990-04-01

346

Management of Radioactive Waste Arising from the Medical, Industrial, and Research Use of Radionuclides.  

National Technical Information Service (NTIS)

The management of radioactive wastes in Australia is reviewed. Technical criteria for regulated user-disposal, shallow ground disposal and long-term storage are examined. Options for ensuring adequate regional and national access to waste repositories are...

1985-01-01

347

Management of Wastes Containing Radioactivity from Mining and Milling of Uranium Ores in Northern Australia.  

National Technical Information Service (NTIS)

The procedures and controls to achieve safe management of wastes containing radioactivity during the mining and processing of uranium ores are mainly site specific depending on the nature, location and distribution of the ore and gangue material. Waste ro...

J. M. Costello

1977-01-01

348

Gamma-ray spectrometry method used for radioactive waste drums characterization for final disposal at National Repository for Low and Intermediate Radioactive Waste--Baita, Romania.  

PubMed

The Radioactive Waste Management Department from IFIN-HH, Bucharest, performs the conditioning of the institutional radioactive waste in concrete matrix, in 200 l drums with concrete shield, for final disposal at DNDR - Baita, Bihor county, in an old exhausted uranium mine. This paper presents a gamma-ray spectrometry method for the characterization of the radioactive waste drums' radionuclides content, for final disposal. In order to study the accuracy of the method, a similar concrete matrix with Portland cement in a 200 l drum was used. PMID:24331854

Done, L; Tugulan, L C; Dragolici, F; Alexandru, C

2014-05-01

349

FCF metallic waste data uncertainty analysis.  

SciTech Connect

Metallic waste is a residual of the electrometallurgical treatment of the Experimental Breeder Reactor II (EBR-II) spent fuel. The treatment is based on electrorefining the fuel in molten salt, and currently it remains in the demonstration phase at the Fuel Conditioning Facility (FCF) at Argonne National Laboratory-West (ANL-W). A reference metallic waste form is produced by mixing 15% zirconium with the stainless steel cladding hulls, which remain in the fuel dissolution baskets (FDB's) after electrorefining, to form a metal alloy. Estimates of uranium in this waste form are of importance to both operations and sensitive materials control and accountability (MC and A). Accurate estimates of the uranium in this product provide important information regarding the dissolution of uranium and the efficiency of the electrorefining process. Under certain operating conditions, non-negligible amounts of uranium were found in this stream, which made it an area of interest for MC and A. The estimates of uranium in this waste stream are currently provided through analysis of cladding hulls samples. The collected cladding hulls data and the errors associated with the data are discussed here, in addition to the effects of these errors on the overall facility ID variance.

Yacout, A. M.

1998-02-02

350

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

351

On problem of burial of solid tritium-containing high radioactive wastes  

SciTech Connect

Within the range of realization of national programs of treatment with radioactive wastes the problems of localization and burial of solid tritium-containing wastes is of great importance. This problem is characterized by a number of peculiarities connected with the localization of tritium-containing wastes on one side and on the other hand, it requires the specific approach connected with the diversity of ways of tritium migration into the environment with its genetic significant, and as a rule, with extremely high waste activity. As a metal-sorbent in given products, titanium is used in a form of thin films sprayed on various metal backings. Mainly, the corrosion-resistant materials are chosen for backing materials such as, molybdenum, copper or stainless steel, made in a form of discs or rectangle plates with thickness from 0.1 to 2 mm and area of 20 cm{sup 2}. The activity of one article may be attained to 100 Ci. Tritium is well sorbed by titanium at the temperature approximately 400 C (its solubility reaches 467 cm per 1 g of titanium) and is relatively well kept by it up to this temperature.

Voitenko, V.A.; Kolomiets, N.F.

1993-12-31

352

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

353

Gas Generation in Radioactive Wastes - MAGGAS Predictive Life Cycle Model  

SciTech Connect

Gases may form from radioactive waste in quantities posing different potential hazards throughout the waste package life cycle. The latter includes surface storage, transport, placing in an operating repository, storage in the repository prior to backfill, closure and the post-closure stage. Potentially hazardous situations involving gas include fire, flood, dropped packages, blocked package vents and disruption to a sealed repository. The MAGGAS (Magnox Gas generation) model was developed to assess gas formation for safety assessments during all stages of the waste package life cycle. This is a requirement of the U.K. regulatory authorities and Nirex and progress in this context is discussed. The processes represented in the model include: Corrosion, microbial degradation, radiolysis, solid-state diffusion, chemico-physical degradation and pressurisation. The calculation was split into three time periods. First the 'aerobic phase' is used to model the periods of surface storage, transport and repository operations including storage in the repository prior to backfill. The second and third periods were designated 'anaerobic phase 1' and 'anaerobic phase 2' and used to model the waste packages in the post-closure phase of the repository. The various significant gas production processes are modeled in each phase. MAGGAS (currently Version 8) is mounted on an Excel spreadsheet for ease of use and speed, has 22 worksheets and is operated routinely for assessing waste packages (e.g. for ventilation of stores and pressurisation of containers). Ten operational and decommissioning generic nuclear power station waste streams were defined as initial inputs, which included ion exchange materials, sludges and concentrates, fuel element debris, graphite debris, activated components, contaminated items, desiccants and catalysts. (authors)

Streatfield, R.E.; Hebditch, D.J. [British Nuclear Group, Berkeley Centre C11, Berkeley, Gloucestershire, GL 13 9PB (United Kingdom); Swift, B.T.; Hoch, A.R. [Serco Assurance, Harwell Business Centre, Didcot, Oxfordshire, OX 11 ORA (United Kingdom); Constable, M. [AEA Technology Plc., B44 Winfrith, Dorchester, Dorset, DT2 8WQ (United Kingdom)

2006-07-01

354

Design and operational considerations of United States commercial near-surface low-level radioactive waste disposal facilities  

Microsoft Academic Search

In accordance with the Low-Level Radioactive Waste Policy Amendments Act of 1985, states are responsible for providing for disposal of commercially generated low-level radioactive waste (LLW) within their borders. LLW in the US is defined as all radioactive waste that is not classified as spent nuclear fuel, high-level radioactive waste, transuranic waste, or by-product material resulting from the extraction of

Birk

1997-01-01

355

Description of Site Operations at the Low-Level Radioactive Waste Disposal Site  

Microsoft Academic Search

The purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than

Y. T. Mohamed; M. A. Hasan; Y. F. Lasheen

2007-01-01

356

Metal Poisons in Waste Tanks (U)  

SciTech Connect

Many of the storage tanks with waste from processing fissile materials contain, along with the fissile material, metals which may serve as nuclear criticality poisons. It would be advantageous to the criticality evaluation of these wastes if it can be demonstrated that the poisons remain with the fissile materials and if an always safe poison-to-fissile ratio can be established. The first task, demonstrating that the materials stay together, is the job of the chemist, the second, demonstrating an always safe ratio, is the job of the physicist. The latter task is the object of this paper

Williamson, T.G. [Westinghouse Savannah River Company, AIKEN, SC (United States)

1996-10-14

357

Metals recovery from wastes. (Latest citations from Metadex). Published Search  

SciTech Connect

The bibliography contains citations concerning the recovery and recycling or reuse of ferrous and nonferrous metals from various industrial wastes. Types of waste considered include waste water, sludge, scrap, battery waste, and waste liquors.(Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

NONE

1996-02-01

358

Metals recovery from wastes. (Latest citations from Metadex). Published Search  

SciTech Connect

The bibliography contains citations concerning the recovery and recycling or reuse of ferrous and nonferrous metals from various industrial wastes. Types of waste considered include waste water, sludge, scrap, battery waste, and waste liquors. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)

NONE

1997-01-01

359

Environmental assessment, finding of no significant impact, and response to comments. Radioactive waste storage  

SciTech Connect

The Department of Energy`s (DOE) Rocky Flats Environmental Technology Site (the Site), formerly known as the Rocky Flats Plant, has generated radioactive, hazardous, and mixed waste (waste with both radioactive and hazardous constituents) since it began operations in 1952. Such wastes were the byproducts of the Site`s original mission to produce nuclear weapons components. Since 1989, when weapons component production ceased, waste has been generated as a result of the Site`s new mission of environmental restoration and deactivation, decontamination and decommissioning (D&D) of buildings. It is anticipated that the existing onsite waste storage capacity, which meets the criteria for low-level waste (LL), low-level mixed waste (LLM), transuranic (TRU) waste, and TRU mixed waste (TRUM) would be completely filled in early 1997. At that time, either waste generating activities must cease, waste must be shipped offsite, or new waste storage capacity must be developed.

NONE

1996-04-01

360

Understanding the toxicity of buried radioactive waste and its impacts.  

PubMed

The oral ingestion toxicities of buried high level radioactive waste from nuclear power plants and of the natural radioactivity in the ground are calculated and expressed as cancer doses, the number of fatal cancers predicted by the linear no-threshold theory if all of the material were fed to people. Unless the size of the U.S. nuclear power industry is greatly expanded, there will probably never be more than 2 trillion cancer doses (CD) in U.S. repositories, as compared with 31 trillion CD in the ground above them. Measurements of the uranium, thorium, and radium in human bodies indicate that the latter cause 500 deaths per year in U.S. The great majority of this material is derived from the top few meters of soil that are penetrated by plant roots. It is concluded that the annual number of U.S. deaths from buried nuclear wastes will be about 1.0 (or less), orders of magnitude less than the number from coal burning electricity generation, the principal competitor of nuclear power. PMID:16155457

Cohen, Bernard L

2005-10-01

361

Three multimedia models used at hazardous and radioactive waste sites  

SciTech Connect

Multimedia models are used commonly in the initial phases of the remediation process where technical interest is focused on determining the relative importance of various exposure pathways. This report provides an approach for evaluating and critically reviewing the capabilities of multimedia models. This study focused on three specific models MEPAS Version 3.0, MMSOILS Version 2.2, and PRESTO-EPA-CPG Version 2.0. These models evaluate the transport and fate of contaminants from source to receptor through more than a single pathway. The presence of radioactive and mixed wastes at a site poses special problems. Hence, in this report, restrictions associated with the selection and application of multimedia models for sites contaminated with radioactive and mixed wastes are highlighted. This report begins with a brief introduction to the concept of multimedia modeling, followed by an overview of the three models. The remaining chapters present more technical discussions of the issues associated with each compartment and their direct application to the specific models. In these analyses, the following components are discussed: source term; air transport; ground water transport; overland flow, runoff, and surface water transport; food chain modeling; exposure assessment; dosimetry/risk assessment; uncertainty; default parameters. The report concludes with a description of evolving updates to the model; these descriptions were provided by the model developers.

Moskowitz, P.D.; Pardi, R.; Fthenakis, V.M.; Holtzman, S.; Sun, L.C. [Brookhaven National Lab., Upton, NY (United States); Rambaugh, J.O.; Potter, S. [Geraghty and Miller, Inc., Plainview, NY (United States)

1996-02-01

362

The 1987 state-by-state assessment of low-level radioactive wastes received at commercial disposal sites: National Low-Level Radioactive Waste Management Program  

Microsoft Academic Search

The Low-Level Waste Management Program has published nine annual State-by-State Assessment Reports since 1979. These reports provide both national and state-specific disposal data on low-level radioactive wastes. Data in this report are divided into generator categories, waste classes, volumes, and activities. Included in this report are tables showing a distribution of wastes by state for 1987 and a comparison of

A. K. Tyron-Hopko; C. B. Ozaki

1988-01-01

363

Greater-than-Class C low-level radioactive waste characterization. Appendix H: Packaging factors for greater-than-Class C low-level radioactive waste  

Microsoft Academic Search

This report develops and presents estimates for a set of three values that represent a reasonable range for the packaging factors for several waste streams that are potential greater-than-Class C low-level radioactive waste. The packaging factor is defined as the volume of a greater-than-Class C low-level waste disposal container divided by the original, as-generated or ``unpackaged,`` volume of the wastes

G. Quinn; P. Grant

1991-01-01

364

The Hybrid Treatment Process for treatment of mixed radioactive and hazardous wastes  

SciTech Connect

This paper describes a new process for treating mixed hazardous and radioactive waste, commonly called mixed waste. The process is called the Hybrid Treatment Process (HTP), so named because it is built on the 20 years of experience with vitrification of wastes in melters, and the 12 years of experience with treatment of wastes by the in situ vitrification (ISV) process.

Ross, W.A.; Kindle, C.H.

1992-04-01

365

Geological challenges in radioactive waste isolation: Third worldwide review  

SciTech Connect

The broad range of activities on radioactive waste isolation that are summarized in Table 1.1 provides a comprehensive picture of the operations that must be carried out in working with this problem. A comparison of these activities with those published in the two previous reviews shows the important progress that is being made in developing and applying the various technologies that have evolved over the past 20 years. There are two basic challenges in perfecting a system of radioactive waste isolation: choosing an appropriate geologic barrier and designing an effective engineered barrier. One of the most important developments that is evident in a large number of the reports in this review is the recognition that a URL provides an excellent facility for investigating and characterizing a rock mass. Moreover, a URL, once developed, provides a convenient facility for two or more countries to conduct joint investigations. This review describes a number of cooperative projects that have been organized in Europe to take advantage of this kind of a facility in conducting research underground. Another critical development is the design of the waste canister (and its accessory equipment) for the engineered barrier. This design problem has been given considerable attention in a number of countries for several years, and some impressive results are described and illustrated in this review. The role of the public as a stakeholder in radioactive waste isolation has not always been fully appreciated. Solutions to the technical problems in characterizing a specific site have generally been obtained without difficulty, but procedures in the past in some countries did not always keep the public and local officials informed of the results. It will be noted in the following chapters that this procedure has caused some problems, especially when approval for a major component in a project was needed. It has been learned that a better way to handle this problem is to keep all stakeholders fully informed of project plans and hold periodic meetings to brief the public, especially in the vicinity of the selected site. This procedure has now been widely adopted and represents one of the most important developments in the Third Worldwide Review.

Witherspoon Editor, P.A.; Bodvarsson Editor, G.S.

2001-12-01

366

Behavior of radioactive iodine and technetium in the spray calcination of high-level waste  

NASA Astrophysics Data System (ADS)

The Remote Laboratory-Scale Waste Treatment Facility (RLSWTF) was designed and built as a part of the High-Level Waste Immobilization Program (now the High-Level Waste Process Development Program) at the Pacific Northwest Laboratory. In facility, installed in a radiochemical cell, is described in which installed in a radiochemical cell is described in which small volumes of radioactive liquid wastes can be solidified, the process off gas can be analyzed, and the methods for decontaminating this off gas can be tested. During the spray calcination of commercial high-level liquid waste spiked with Tc-99 and I-131 and 31 wt% loss of I-131 past the sintered-metal filters. These filters and venturi scrubber were very efficient in removing particulates and Tc-99 from the the off-gas stream. Liquid scrubbers were not efficient in removing I-131 as 25% of the total lost went to the building off-gas system. Therefore, solid adsorbents are needed to remove iodine. For all future operations where iodine is present, a silver zeolite adsorber is to be used.

Knox, C. A.; Farnsworth, R. K.

1981-08-01

367

Heavy metal distribution in household waste  

SciTech Connect

The present study was undertaken at the request of the French Ministry of Environment with the help of the national agency for waste recovery and disposal (ANRED) and the company Valorga. The aim of this paper is to report the original methods of assessment and relevant results in visual form. Knowledge of the distribution of each heavy metal (mercury, cadmium, lead, nickel, chromium, zinc and copper) in the different parts or components of household refuse will allow the development of both statutory safeguards on the disposal of products such as batteries, a source of heavy metals, and of effective technological treatment of the granulometric fractions which are richest in toxic elements.

Rosseaux, P.; Navarro, A.; Vermande, P. (Institut National des Sciences Appliques, Villeurbanne (France))

1989-09-01

368

Alternative methods for disposal of low-level radioactive wastes. Volume 2. Task 2a. Technical requirements for belowground vault disposal of low-level radioactive waste  

Microsoft Academic Search

The study reported herein contains the results of Task 2a (Technical Requirements for Belowground Vault Disposal of Low-Level Radioactive Waste) of a four-task study entitled ''Criteria for Evaluating Engineered Facilities.'' The overall objective of this study is to ensure that the criteria needed to evaluate five alternative low-level radioactive waste (LLW) disposal methods are available potential license applicants. The belowground

J. B. Warriner; R. D. Bennett

1985-01-01

369

Alternative methods for disposal of low-level radioactive wastes. Task 2e: technical requirements for shaft disposal of low-level radioactive waste. Volume 5  

Microsoft Academic Search

The study reported herein contains the results of Task 2e (Technical Requirements for Shaft Disposal of Low-Level Radioactive Waste) of a four-task study entitled ''Criteria for Evaluating Engineered Facilities''. The overall objective of this study is to ensure that the criteria needed to evaluate five alternative low-level radioactive waste (LLW) disposal methods are available to potential license applicants. The shaft

1985-01-01

370

Alternative methods for disposal of low-level radioactive wastes. Volume 3. Task 2b: technical requirements for aboveground vault disposal of low-level radioactive waste  

Microsoft Academic Search

The study reported herein contains the results of Task 2b (Technical Requirements for Aboveground Vault Disposal of Low-Level Radioactive Waste) of a four-task study entitled ''Criteria for Evaluating Engineered Facilities.'' The overall objective of this study is to ensure that the criteria needed to evaluate five alternative low-level radioactive waste (LLW) disposal methods are available potential license applicants. The above-ground

R. D. Bennett; J. B. Warriner

1985-01-01

371

Economics and Environmental Compatibility of Fusion Reactors —Its Analysis and Coming Issues— 3. Expected Effect of Fusion Reactor on Global Environment 3.1 Research Aimed at Reducing Radioactive Waste  

NASA Astrophysics Data System (ADS)

Waste management at fusion power plants is reviewed. Recent study indicates that most of the waste from a fusion reactor can be cleared from regulatory control over a 50-year cooling after decommissioning. In addition, the remaining metal radioactive waste is anticipated to be recyclable within 100-year cooling. These results indicate the prospect of a low emission system of fusion energy materials.

Tobita, Kenji; Hiwatari, Ryouji

372

The application of metal cutting technologies in tasks performed in radioactive environments  

SciTech Connect

The design and use of equipment to perform work in radioactive environments is uniquely challenging. Some tasks require that the equipment be operated by a person wearing a plastic suit or full face respirator and donning several pairs of rubber gloves. Other applications may require that the equipment be remotely controlled. Other important, design considerations include material compatibility, mixed waste issues, tolerance to ionizing radiation, size constraints and weight capacities. As always, there is the ``We need it ASAP`` design criteria. This paper describes four applications where different types of metal cutting technologies were used to successfully perform tasks in radioactive environments. The technologies include a plasma cutting torch, a grinder with an abrasive disk, a hydraulic shear, and a high pressure abrasive water jet cutter.

Fogle, R.F.; Younkins, R.M.

1997-05-01

373

EVALUATION OF ULTIMATE DISPOSAL METHODS FOR LIQUID AND SOLID RADIOACTIVE WASTES. PART III. INTERIM STORAGE OF SOLIDIFIED WASTES  

Microsoft Academic Search

The costs of interim storage of solidified Purex and Thorex wastes in ; water-filled canals were estimated as the third part of a study to evaluate, from ; the standpoint of econoNonemics and hazards, the various steps leading to and ; including the permanent disposal of highly radioactive liquid and solid wastes. ; The wastes were assumed to have been

J. O. Blomeke; J. J. Perona; H. O. Weeren; T. L. Bradshaw

1963-01-01

374

Evaluation of ultimate disposal methods for liquid and solid radioactive wastes. Part III. Interim storage of soldified wastes  

Microsoft Academic Search

The costs of interim storage of solidified Purex and Thorex wastes in water-filled canals were estimated as the third part of a study to evaluate, from the standpoint of economics and hazards, the various steps leading to and including the permanent disposal of highly radioactive liquid and solid wastes. The wastes were assumed to have been solidified following their production

J. O. Blomeke; J. J. Perona; H. O. Weeren; R. L. Bradshaw

1963-01-01

375

75 FR 74104 - 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 110.70 (b...EnergySolutions, August 27, Radioactive waste Not to exceed Return to two Germany...facilities for resulting from appropriate the incineration disposition. of contaminated...

2010-11-30

376

18th U.S. Department of Energy Low-Level Radioactive Waste Management Conference. Program  

SciTech Connect

This conference explored the latest developments in low-level radioactive waste management through presentations from professionals in both the public and the private sectors and special guests. The conference included two continuing education seminars, a workshop, exhibits, and a tour of Envirocare of Utah, Inc., one of America's three commercial low-level radioactive waste depositories.

None

1997-05-20

377

Low Level Radioactive Wastes Conditioning during Decommissioning of Salaspils Research Reactor  

Microsoft Academic Search

The decommissioning of Salaspils research reactor is connected with the treatment of 2200 tons different materials. The largest part of all materials (60 % of all dismantled materials) is connected with low level radioactive wastes conditioning activities. Dismantled radioactive materials were cemented in concrete containers using water-cement mortar. According to elaborated technology, the tritiated water (150 tons of liquid wastes

G. Abramenkova; M. Klavins; A. Abramenkovs

2008-01-01

378

New York's development of low-level radioactive waste disposal capability  

Microsoft Academic Search

The authors report how New York has undertaken a program to meet its responsibilities under the Federal Low-Level Radioactive Waste Policy Act (LLRWPA) as amended in 1985. In 1986, it enacted the New York State Low-Level Radioactive Waste Management Act (state LLRWMA) which provides for the state to meet all the milestones established by the 1985 amendments to the federal

A. F. Orazio; J. D. Dunkleberger

1988-01-01

379

Development and implementation of the Low-Level Radioactive Waste Policy Act  

Microsoft Academic Search

The Low-Level Radioactive Waste Policy Act, passed in December 1980, was a major step in initiating the establishment of a national system for the management of commercially generated low-level radioactive waste. States have made considerable progress in developing the institutional structures needed as a framework for developing regional disposal sites. Nearly 40 states have enacted legislation in response to the

K. F. Downs; J. A. Coleman

1984-01-01

380

2005 Data Report: Groundwater Monitoring Program Area 5 Radioactive Waste Management Site  

SciTech Connect

This report is a compilation of the calendar year 2005 groundwater sampling results from the Area 5 Radioactive Waste Management Site. In additon to providing groundwater monitoring results, this report also includes information regarding site hydrogeology, well construction, sample collection, and meteorological data measured at the Area 5 Radioactive Waste Management Site at the Nevada Test Site, Ny County, Nevada.

Bechtel Nevada

2006-02-01

381

77 FR 73054 - Application for a License To Export Radioactive Waste  

Federal Register 2010, 2011, 2012, 2013

...REGULATORY COMMISSION Application for a License To Export Radioactive Waste Pursuant to 10 CFR 110.70(b) ``Public Notice...Approximately Storage or Canada. 2012, October 25, 2012, XW020, radioactive 1178 pounds disposal by the 11006061. waste in the...

2012-12-07

382

78 FR 26813 - 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...maximum the licensee name 2013, IW022/03, 11005700. A radioactive total of 5,500 from ``Perma-Fix waste). tons of...

2013-05-08

383

78 FR 45578 - Application For a License to Export Radioactive Waste  

Federal Register 2010, 2011, 2012, 2013

...REGULATORY COMMISSION Application For a License to Export Radioactive Waste Pursuant to 10 CFR 110.70 (b) ``Public Notice...quantity Storage or Canada. June 4, 2013, June 5, 2013, radioactive waste authorized for disposal by the XW021, 11006101....

2013-07-29

384

Environmental factors needed to establish the geotechnical feasibility of storing radioactive waste in Columbia River basalt  

Microsoft Academic Search

The geotechnical program required to fully establish the feasibility of storing commercial radioactive waste in Columbia River Basalt is a complex interdisciplinary effort. This report details the program required to establish the feasibility of storing radioactive waste in this basalt. The program includes: (1) achieving an understanding of the geologic setting; (2) appropriately defining the extent of hydrologic isolation of

R. A. Deju; P. A. Eddy; M. W. Grutzeck; C. W. Myers

1977-01-01

385

On-site transfer system for remote handling of low-level radioactive waste  

Microsoft Academic Search

Increased uncertainties regarding the future availability of low-level radioactive waste (LLW) disposal sites have caused many commercial nuclear power utilities to investigate and implement alternatives to radwaste storage and disposal. Nuclear Packaging, Inc., under contract to Southern California Edison has developed an on-site radioactive waste transfer system (OTS), which allows shielded handling of LLW at the San Onofre Nuclear Generating

Schmoker; Duane S

1985-01-01

386

Elimination of liquid discharge to the environment from the TA50 Radioactive Liquid Waste Treatment Facility  

Microsoft Academic Search

Alternatives were evaluated for management of treated radioactive liquid waste from the radioactive liquid waste treatment facility (RLWTF) at Los Alamos National Laboratory. The alternatives included continued discharge into Mortandad Canyon, diversion to the sanitary wastewater treatment facility and discharge of its effluent to Sandia Canyon or Canada del Buey, and zero liquid discharge. Implementation of a zero liquid discharge

D. Moss; N. Williams; D. Hall; K. Hargis; M. Saladen; M. Sanders; S. Voit; P. Worland; S. Yarbro

1998-01-01

387

The plasma torch for the vitrification of low-level radioactive waste  

Microsoft Academic Search

Summary form only given. A problem arousing international concern is the long-term storage and disposal of radioactive wastes. Solving this problem is particularly important because of the dangers of improper storage, both for the present and the future. It is essential that radioactive waste be stored in a compact and stable form. Plasma torch technology provides a possible solution for

A. L. Peratt

1995-01-01

388

Incineration of radioactive organic liquid wastes by underwater thermal plasma  

NASA Astrophysics Data System (ADS)

This work deals with incineration of radioactive organic liquid wastes using an oxygen thermal plasma jet, submerged under water. The results presented here are focused on incineration of three different wastes: a mixture of tributylphosphate (TBP) and dodecane, a perfluoropolyether oil (PFPE) and trichloroethylene (TCE). To evaluate the plutonium behavior in used TBP/dodecane incineration, zirconium is used as a surrogate of plutonium; the method to enrich TBP/dodecane mixture in zirconium is detailed. Experimental set-up is described. During a trial run, CO2 and CO contents in the exhaust gas are continuously measured; samples, periodically taken from the solution, are analyzed by appropriate chemical methods: contents in total organic carbon (COT), phosphorus, fluoride and nitrates are measured. Condensed residues are characterized by RX diffraction and SEM with EDS. Process efficiency, during tests with a few L/h of separated or mixed wastes, is given by mineralization rate which is better than 99.9 % for feed rate up to 4 L/h. Trapping rate is also better than 99 % for phosphorous as for fluorine and chlorine. Those trials, with long duration, have shown that there is no corrosion problems, also the hydrogen chloride and fluoride have been neutralized by an aqueous solution of potassium carbonate.

Mabrouk, M.; Lemont, F.; Baronnet, J. M.

2012-12-01

389

Phosphate glasses for radioactive, hazardous and mixed waste immobilization  

DOEpatents

Lead-free phosphate glass compositions are provided which can be used to immobilize low level and/or high level radioactive wastes in monolithic waste forms. The glass composition may also be used without waste contained therein. Lead-free phosphate glass compositions prepared at about 900 C include mixtures from about 1--6 mole % iron (III) oxide, from about 1--6 mole % aluminum oxide, from about 15--20 mole % sodium oxide or potassium oxide, and from about 30--60 mole % phosphate. The invention also provides phosphate, lead-free glass ceramic glass compositions which are prepared from about 400 C to about 450 C and which includes from about 3--6 mole % sodium oxide, from about 20--50 mole % tin oxide, from about 30--70 mole % phosphate, from about 3--6 mole % aluminum oxide, from about 3--8 mole % silicon oxide, from about 0.5--2 mole % iron (III) oxide and from about 3--6 mole % potassium oxide. Method of making lead-free phosphate glasses are also provided. 8 figs.

Cao, H.; Adams, J.W.; Kalb, P.D.

1998-11-24

390

Phosphate glasses for radioactive, hazardous and mixed waste immobilization  

DOEpatents

Lead-free phosphate glass compositions are provided which can be used to immobilize low level and/or high level radioactive wastes in monolithic waste forms. The glass composition may also be used without waste contained therein. Lead-free phosphate glass compositions prepared at about 900 C include mixtures from about 1 mole % to about 6 mole % iron (III) oxide, from about 1 mole % to about 6 mole % aluminum oxide, from about 15 mole % to about 20 mole % sodium oxide or potassium oxide, and from about 30 mole % to about 60 mole % phosphate. The invention also provides phosphate, lead-free glass ceramic glass compositions which are prepared from about 400 C to about 450 C and which includes from about 3 mole % to about 6 mole % sodium oxide, from about 20 mole % to about 50 mole % tin oxide, from about 30 mole % to about 70 mole % phosphate, from about 3 mole % to about 6 mole % aluminum oxide, from about 3 mole % to about 8 mole % silicon oxide, from about 0.5 mole % to about 2 mole % iron (III) oxide and from about 3 mole % to about 6 mole % potassium oxide. Method of making lead-free phosphate glasses are also provided. 8 figs.

Cao, H.; Adams, J.W.; Kalb, P.D.

1999-03-09

391

Phosphate glasses for radioactive, hazardous and mixed waste immobilization  

DOEpatents

Lead-free phosphate glass compositions are provided which can be used to immobilize low level and/or high level radioactive wastes in monolithic waste forms. The glass composition may also be used without waste contained therein. Lead-free phosphate glass compositions prepared at about 900.degree. C. include mixtures from about 1 mole % to about 6 mole %.iron (III) oxide, from about 1 mole % to about 6 mole % aluminum oxide, from about 15 mole % to about 20 mole % sodium oxide or potassium oxide, and from about 30 mole % to about 60 mole % phosphate. The invention also provides phosphate, lead-free glass ceramic glass compositions which are prepared from about 400.degree. C. to about 450.degree. C. and which includes from about 3 mole % to about 6 mole % sodium oxide, from about 20 mole % to about 50 mole % tin oxide, from about 30 mole % to about 70 mole % phosphate, from about 3 mole % to about 6 mole % aluminum oxide, from about 3 mole % to about 8 mole % silicon oxide, from about 0.5 mole % to about 2 mole % iron (III) oxide and from about 3 mole % to about 6 mole % potassium oxide. Method of making lead-free phosphate glasses are also provided.

Cao, Hui (Middle Island, NY); Adams, Jay W. (Stony Brook, NY); Kalb, Paul D. (Wading River, NY)

1999-03-09

392

Phosphate glasses for radioactive, hazardous and mixed waste immobilization  

DOEpatents

Lead-free phosphate glass compositions are provided which can be used to immobilize low level and/or high level radioactive wastes in monolithic waste forms. The glass composition may also be used without waste contained therein. Lead-free phosphate glass compositions prepared at about 900.degree. C. include mixtures from about 1 mole % to about 6 mole % iron (III) oxide, from about 1 mole % to about 6 mole % aluminum oxide, from about 15 mole % to about 20 mole % sodium oxide or potassium oxide, and from about 30 mole % to about 60 mole % phosphate. The invention also provides phosphate, lead-free glass ceramic glass compositions which are prepared from about 400.degree. C. to about 450.degree. C. and which includes from about 3 mole % to about 6 mole % sodium oxide, from about 20 mole % to about 50 mole % tin oxide, from about 30 mole % to about 70 mole % phosphate, from about 3 mole % to about 6 mole % aluminum oxide, from about 3 mole % to about 8 mole % silicon oxide, from about 0.5 mole % to about 2 mole % iron (III) oxide and from about 3 mole % to about 6 mole % potassium oxide. Method of making lead-free phosphate glasses are also provided.

Cao, Hui (Middle Island, NY); Adams, Jay W. (Stony Brook, NY); Kalb, Paul D. (Wading River, NY)

1998-11-24

393

Material Not Categorized As Waste (MNCAW) data report. Radioactive Waste Technical Support Program  

SciTech Connect

The Department of Energy (DOE), Headquarters, requested all DOE sites storing valuable materials to complete a questionnaire about each material that, if discarded, could be liable to regulation. The Radioactive Waste Technical Support Program entered completed questionnaires into a database and analyzed them for quantities and type of materials stored. This report discusses the data that TSP gathered. The report also discusses problems revealed by the questionnaires and future uses of the data. Appendices contain selected data about material reported.

Casey, C.; Heath, B.A.

1992-11-01

394

Rhode Island State Briefing Book on low-level radioactive-waste management  

SciTech Connect

The Rhode Island State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Rhode Island. The profile is the result of a survey of radioactive material licensees in Rhode Island. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may affect waste management practices in Rhode Island.

Not Available

1981-07-01

395

[Current status on storage, processing and risk communication of medical radioactive waste in Japan].  

PubMed

Decay-in-storage for radioactive waste including that of nuclear medicine has not been implemented in Japan. Therefore, all medical radioactive waste is collected and stored at the Japan Radioisotope Association Takizawa laboratory, even if the radioactivity has already decayed out. To clarify the current situation between Takizawa village and Takizawa laboratory, we investigated the radiation management status and risk communication activities at the laboratory via a questionnaire and site visiting survey in June 2010. Takizawa laboratory continues to maintain an interactive relationship with local residents. As a result, Takizawa village permitted the acceptance of new medical radioactive waste containing Sr-89 and Y-90. However, the village did not accept any non-medical radioactive waste such as waste from research laboratories. To implement decay-in-storage in Japan, it is important to obtain agreement with all stakeholders. We must continue to exert sincere efforts to acquire the trust of all stakeholders. PMID:23514856

Watanabe, Hiroshi; Yamaguchi, Ichiro; Kida, Tetsuo; Hiraki, Hitoshi; Fujibuchi, Toshioh; Maehara, Yoshiaki; Tsukamoto, Atsuko; Koizumi, Mitsue; Kimura, Yumi; Horitsugi, Genki

2013-03-01

396

Iron Phosphate Glass as Potential Waste Matrix for High-Level Radioactive Waste  

SciTech Connect

Recently, Iron Phosphate Glass (IPG) is investigated as the alternative final waste form for High-Level Radioactive Waste (HLW) in U.S. This study is aimed to investigate feasibility of IPG to HLW arising from commercial reprocessing in Japan. In order to evaluate favorable preparation conditions, maximum waste loading and property of IPG, the melting tests were carried. From the results of melting tests, the favorable preparation conditions was with matrix of Fe/P 0.43 (mole ratio in products) and melting at 1200{sup o} for 4h. The products of 10-20mass% waste loading of simulated HLW were glassy and had no crystal peaks, however the product of 30mass% waste loading showed some crystal peaks by XRD analysis. IPG and Borosilicate glass (BG) had about the same thermal properties. As a result, IPG had enough potential for high waste loading and the extremely good chemical durability for consideration as a waste form for Japanese HLW.

Fukui, T.; Ishinomori, T.; Endo, Y.; Sazarashi, M.; Ono, S.; Suzuki, K.

2003-02-25

397

Fall-Out: New York v. United States and the Low-Level Radioactive Waste Problem  

Microsoft Academic Search

For over thirty years, \\u0009\\u0009\\u0009the United States has failed to solve its low-level radioactive waste \\u0009\\u0009\\u0009problem. Working independently, state \\u0009\\u0009\\u0009governments have not developed a single new disposal site for low-level \\u0009\\u0009\\u0009radioactive waste. Congress' best \\u0009\\u0009\\u0009efforts to address the growing quantities of waste included passing a law that, \\u0009\\u0009\\u0009in part, required states to accept responsibility for all low-level radioactive \\u0009\\u0009\\u0009waste. Unsurprisingly,

Samantha Dreilinger

2010-01-01

398

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

SciTech Connect

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

Romano, Stephen; Welling, Steven; Bell, Simon

2003-02-27

399

Monte Carlo simulations of radioactive waste embedded into EPDM and effect of lead filler  

NASA Astrophysics Data System (ADS)

Radioactive waste is generated from the nuclear industry and should be processed and disposed of according to the regulations set by the appropriate regulatory authority. Ethylene propylene diene monomer (EPDM) is a widely used polymer and might be considered as a potential candidate radioactive waste encapsulation material. In this study, the dose rate distribution in the radioactive waste drum (containing radioactive waste and the polymer matrix) was determined using Monte Carlo simulations. The change in the dose rate within the waste drum with different amounts of lead filler was also simulated. It was seen that lead filler would decrease the dose delivered to the polymer by means of energy dissipation. Moreover, the change of mechanical properties of EPDM was estimated and their variation within the waste drum was determined for the duration of 15, 30 and 300 years after embedding.

Özdemir, Tonguç

2014-05-01

400

Structure and Vibrational Spectra of Slags Produced from Radioactive Waste  

NASA Astrophysics Data System (ADS)

The structure of the anionic motif of aluminosilicate and aluminoborosilicate glasses containing simulated slags from a solid radioactive waste incinerator was studied by IR and Raman spectroscopy. Spectra of melted slag were consistent with Si-O tetrahedra with various numbers of bridging O ions and Al-O tetrahedra embedded in the Si-O network in the slag vitreous and crystalline phases (nepheline, nagelschmidtite). Vibrations of doubly and triply bound Si-O tetrahedra and Al-O tetrahedra embedded between them were mainly responsible for the spectra as the content of sodium disilicate fl ux and the glass fraction in the materials increased. Addition of sodium tetraborate fl ux caused the appearance of B-O vibrations of predominantly three-coordinate B and a tendency toward chemical differentiation preceding phase separation.

Malinina, G. A.; Stefanovsky, S. V.

2014-05-01

401

Russian Containers for Transportation of Solid Radioactive Waste  

SciTech Connect

The Russian Shipyard ''Zvyozdochka'' has designed a new container for transportation and storage of solid radioactive wastes. The PST1A-6 container is cylindrical shaped and it can hold seven standard 200-liter (55-gallon) drums. The steel wall thickness is 6 mm, which is much greater than standard U.S. containers. These containers are fully certified to the Russian GOST requirements, which are basically identical to U.S. and IAEA standards for Type A containers. They can be transported by truck, rail, barge, ship, or aircraft and they can be stacked in 6 layers in storage facilities. The first user of the PST1A-6 containers is the Northern Fleet of the Russian Navy, under a program sponsored jointly by the U.S. DoD and DOE. This paper will describe the container design and show how the first 400 containers were fabricated and certified.

Petrushenko, V. G.; Baal, E. P.; Tsvetkov, D. Y.; Korb, V. R.; Nikitin, V. S.; Mikheev, A. A.; Griffith, A.; Schwab, P.; Nazarian, A.

2002-02-28

402

Immobilization of radioactive and hazardous wastes in a developed sulfur polymer cement (SPC) matrix  

SciTech Connect

Available in abstract form only. Full text of publication follows: A process has been developed for the immobilization Cs, Sr, Ce, Pb, and Cr in forms that is non-dispersible and could be safely immobilized. The simulated radioactive wastes of Cs, Sr, and Ce, and the hazardous wastes of Cr, and Pb were immobilized in the stable form of sulfur polymer cement (SPC). In this process, the contaminants (in a single form) were added to the sulfur mixture of sulfur and aromatic /or aliphatic hydrocarbons that used as polymerizing agents for sulfur (95% S, and 5% organic polymer by weight). Durability of the fabricated SPC matrices was assessed in terms of their water of immersion, porosity, and compressive strength. The water immersion, and open porosity were found to be less than 2.5% for all the prepared matrices, whereas the compressive strength was in the range between 62.4 and 142.3 Kg.cm{sup -2}, depending on the composition of the prepared matrix. The prepared SPC matrices that characterized by X-ray diffraction (XRD) showed that the different added contaminants were stabilized during the solidification process during their reaction with sulfur and the organic polymer to form the corresponding metal sulfides. Toxicity Characteristic Leaching Procedure (TCLP), and the IAEA standard method have assessed the leachability of the prepared waste matrices. The TCLP results showed that most the concentration of the contaminants released were under their detection limit. The leach index for the investigated metals from the prepared SPC matrices was in the range of 9-11. The order of release of the investigated metals was Sr>Cs>Pb>Cr>Ce for the aliphatic polymer, and Sr>Cr>Pb>Cs>Ce for the aromatic one. The results obtained revealed a high performance for the prepared SPC matrices, as they are of low cost effect, highly available materials, and possessed good mechanical and leaching properties. Key Words: SPC/ Matrices/ Immobilization/ Wastes/ Leachability. (authors)

Wagdy, M.; Azim, Abdel; El-Gammal, Belal [Atomic Energy Authority, Nasr City, P.O. Box 7551, Cairo (Egypt); Husain, Ahmed [National Research Center, Cairo (Egypt)

2007-07-01

403

Status of activities: Low-level radioactive waste management in the United States  

Microsoft Academic Search

A primary objective of low-level radioactive waste management in the United States is to protect the health and safety of the public and the quality of the environment. In support of this objective is the development of waste treatment and disposal technologies designed to provide stabilization and long-term institutional control of low-level radioactive wastes. Presented herein is a technical review

C. B. Ozaki; R. C. Shilkett; T. D. Kirkpatrick

1989-01-01

404

Large-scale leaching of low-level radioactive wastes: Environmental Sciences Division publication No. 2737  

Microsoft Academic Search

The large-scale leaching of low-level radioactive wastes was conducted using 208- and 314-L drums containing radioactive wastes generated at Oak Ridge National Laboratory and Oak Ridge Gaseous Diffusion Plant. Ten 208-L drums containing low-level transuranic (TRU) wastes and four 314-L overpack drums containing compacted drums from a Westinghouse-Hittman drum compaction demonstration were leached with potable drinking water, using a unique

1986-01-01

405

Greater-than-Class-C low-level radioactive waste management concepts  

Microsoft Academic Search

In 1986, Public Law 99-240, the ''Low-Level Radioactive Waste Policy Amendments Act of 1985'' assigned to the federal government responsibility for the disposal of commercial greater-than-Class-C (GTCC) low-level radioactive waste (LLW). In 1987, DOE committed to Congress to accept GTCC LLW and provide storage and other waste management as necessary until disposal capacity is available. Current estimates are that about

Knecht

1988-01-01

406

Development of a universal solvent for the decontamination of acidic liquid radioactive wastes  

NASA Astrophysics Data System (ADS)

A teritiary solvent containing chlorinated cobalt dicarbollide, polyethylene glycol and diphenylcarbamoylmethylphosphine oxide was evaluated in different non-nitroaromatic diluents for the separation of cesium, strontium, actinides and rare earth elements from acidic liquid radioactive waste. Decontamination factors of >95% for Cs, 99.7% for Sr, and 99.99% for actinides were achieved in four successive batch contacts using actual radioactive waste. Pilot plant testing in centrifugal contactors using simulated wastes, has demonstrated removal of >99% of all targeted ions.

Todd, T. A.; Brewer, K. N.; Law, J. D.; Wood, D. J.; Herbest, R. S.; Romanovskiy, V. N.; Esimantovskiy, V. M.; Smirnov, I. V.; Babain, V. A.

1999-01-01

407

Radioactive waste definitions, standards, criteria, and approaches in the United States of America  

SciTech Connect

This paper provides an overview of the structure of the radioactive waste management system in the United States. Included are definitions, standards, organizational structure, and general technical approaches to radioactive waste management. It must be noted that the US waste management systems have evolved with time toward more consistent, uniform approaches. There are specific exceptions to general practice, but they are not discussed here. 18 refs., 4 tabs.

Nelson, R. (USDOE, Washington, DC (USA)); Forsberg, C.W. (Oak Ridge National Lab., TN (USA))

1990-06-01

408

Environmental assessment for the Radioactive and Mixed Waste Management Facility: Sandia National Laboratories/New Mexico  

SciTech Connect

The Department of Energy (DOE) has prepared an environmental assessment (EA) (DOE/EA-0466) under the National Environmental Policy Act (NEPA) of 1969 for the proposed completion of construction and subsequent operation of a central Radioactive and Mixed Waste Management Facility (RMWMF), in the southeastern portion of Technical Area III at Sandia National Laboratory, Albuquerque (SNLA). The RMWMF is designed to receive, store, characterize, conduct limited bench-scale treatment of, repackage, and certify low-level waste (LLW) and mixed waste (MW) (as necessary) for shipment to an offsite disposal or treatment facility. The RMWMF was partially constructed in 1989. Due to changing regulatory requirements, planned facility upgrades would be undertaken as part of the proposed action. These upgrades would include paving of road surfaces and work areas, installation of pumping equipment and lines for surface impoundment, and design and construction of air locks and truck decontamination and water treatment systems. The proposed action also includes an adjacent corrosive and reactive metals storage area, and associated roads and paving. LLW and MW generated at SNLA would be transported from the technical areas to the RMWMF in containers approved by the Department of Transportation. The RMWMF would not handle nonradioactive hazardous waste. Based on the analysis in the EA, the proposed completion of construction and operation of the RMWMF does not constitute a major Federal action significantly affecting the quality of the human environment within the meaning of NEPA. Therefore, preparation of an environmental impact statement for the proposed action is not required.

Not Available

1993-06-01

409

Corrosion mechanisms of low level vitrified radioactive waste in a loamy soil M.I. Ojovan1  

E-print Network

Corrosion mechanisms of low level vitrified radioactive waste in a loamy soil M.I. Ojovan1 , W. INTRODUCTION Vitrification of low and intermediate level radioactive waste (LILW) is attracting great interest intermediate level operational nuclear power plant (NPP) radioactive waste. Some tonnes of this glass were

Sheffield, University of

410

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

SciTech Connect

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 dissimilar analytical methodologies, Open-Path Fourier Transform Infrared Spectroscopy (OP-FTIR) and ancillary SUMMA{reg_sign} canister sampling, following the US Environmental Protection Agency (EPA) analytical method TO-14, will be used to provide qualitative and quantitative volatile organic concentration data. The Open-Path Fourier Transform Infrared Spectroscopy will provide in situ, real time monitoring of volatile organic compound concentrations in the ambient air of the Waste Storage Facilities. To supplement the OP-FTIR data, air samples will be collected using SUMMA{reg_sign}, passivated, stainless steel canisters, following the EPA Method TO-14. These samples will be analyzed for volatile organic compounds with gas chromatograph/mass spectrometry analysis. The sampling strategy, procedures, and schedules are included in this monitoring plan. The development of this monitoring plan is driven by regulatory compliance to the Resource Conservation and Recovery Act, State of Idaho Toxic Air Pollutant increments, Occupational Safety and Health Administration. The various state and federal regulations address the characterization of the volatile organic compounds and the resultant ambient air emissions that may originate from facilities involved in industrial production and/or waste management activities.

Galloway, K.J.; Jolley, J.G.

1994-06-01

411

Greater-than-Class C low-level radioactive waste characterization. Appendix E-4: Packaging factors for greater-than-Class C low-level radioactive waste  

Microsoft Academic Search

This report estimates packaging factors for several waste types that are potential greater-than-Class C (GTCC) low-level radioactive waste (LLW). The packaging factor is defined as the volume of a GTCC LLW disposal container divided by the as-generated or ``unpackaged`` volume of the waste loaded into the disposal container. Packaging factors reflect any processes that reduce or increase an original unpackaged

G. Quinn; P. Grant; M. Winberg; K. Williams

1994-01-01

412

Enlargement of the Baldone near-surface radioactive waste repository  

SciTech Connect

A unified analysis of the enlargement of the Baldone near-surface radioactive waste (RW) repository RADONS considers the interplay of the existing engineering, safety and infrastructure premises, with the foreseen newly socio-technical features. This enlargement consists in construction of two additional RW disposal vaults and in building a long-term storage facility for spent sealed sources at the RADONS territory. Our approach is based on consecutive analysis of following basic elements: - the origin of enlargement - the RADONS safety analysis and a set of optimal socio-technical solutions of Salaspils research reactor decommissioning waste management; - the enlargement - a keystone of the national RW management concept, including the long-term approach; - the enlargement concept - the result of international co-operation and obligations; - arrangement optimization of new disposal and storage space; - environmental impact assessment for the repository enlargement - the update of socio-technical studies. The study of the public opinion revealed: negative attitude to repository enlargement is caused mainly due to missing information on radiation level and on the RADONS previous operations. These results indicate: basic measures to improve the public attitude to repository enlargement: the safety upgrade, public education and compensation mechanisms. A detailed stakeholders engagement and public education plan is elaborated. (author)

Dreimanis, A. [Radiation Safety Centre, 165 Maskavas Street, LV-1019 Riga (Latvia)

2007-07-01

413

Selected radionuclides important to low-level radioactive waste management  

SciTech Connect

The purpose of this document is to provide information to state representatives and developers of low level radioactive waste (LLW) management facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the environment. Extensive surveys of available literature provided information for this report. Certain radionuclides may contribute significantly to the dose estimated during a radiological performance assessment analysis of an LLW disposal facility. Among these are the radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha emitting transuranics with half-lives greater than 5 years). This report discusses these radionuclides and other radionuclides that may be significant during a radiological performance assessment analysis of an LLW disposal facility. This report not only includes essential information on each radionuclide, but also incorporates waste and disposal information on the radionuclide, and behavior of the radionuclide in the environment and in the human body. Radionuclides addressed in this document include technetium-99, carbon-14, iodine-129, tritium, cesium-137, strontium-90, nickel-59, plutonium-241, nickel-63, niobium-94, cobalt-60, curium -42, americium-241, uranium-238, and neptunium-237.

NONE

1996-11-01

414

Metals recovery from wastes. (Latest citations from Metadex (Metals Abstract/Alloys Index) database). Published Search  

SciTech Connect

The bibliography contains citations concerning the recovery and recycling or reuse of ferrous and nonferrous metals from various industrial wastes. Types of waste considered include waste water, sludge, scrap, battery waste, and waste liquors. (Contains 250 citations and includes a subject term index and title list.)

Not Available

1993-10-01

415

Management of radioactive waste in Belgium: ONDRAF/NIRAS and Belgoprocess as major actors of the waste acceptance system  

SciTech Connect

The management of radioactive waste in Belgium is undertaken by the national agency for radioactive waste and enriched fissile materials, ONDRAF/NIRAS, and its industrial partner Belgoprocess. ONDRAF/NIRAS has set up a management system designed to guarantee that the general public and the environment are protected against the potential hazards arising from radioactive waste. Belgoprocess is a private company, founded in 1984 and located in Dessel, Belgium. It is a subsidiary of ONDRAF/NIRAS and its activities focus on the safe processing and storage of radioactive waste. The management system of ONDRAF/NIRAS includes two aspects: a) an integrated system and b) an acceptance system. The integrated system covers all aspects of management ranging from the origin of waste to its transport, processing, interim storage and long-term management. The safety of radioactive waste management not only depends on the quality of the design and construction of the processing, temporary storage or disposal infrastructure, but also on the quality of the waste accepted by ONDRAF/NIRAS. In order to be manage d safely, both in the short and the long term, the waste transferred to ONDRAF/NIRAS must meet certain specific requirements. To that end, ONDRAF/NIRAS has developed an acceptance system. (authors)

Zaelen, Gunter van [ONDRAF/NIRAS, Avenue des Arts 14, B 1210 Brussels (Belgium); Verheyen, Annick [Belgoprocess N.V., Gravenstraat 73, 2480 Dessel (Belgium)

2007-07-01

416

Electrochemical corrosion testing of metal waste forms  

SciTech Connect

Electrochemical corrosion tests have been conducted on simulated stainless steel-zirconium (SS-Zr) metal waste form (MWF) samples. The uniform aqueous corrosion behavior of the samples in various test solutions was measured by the polarization resistance technique. The data show that the MWF corrosion rates are very low in groundwaters representative of the proposed Yucca Mountain repository. Galvanic corrosion measurements were also conducted on MWF samples that were coupled to an alloy that has been proposed for the inner lining of the high-level nuclear waste container. The experiments show that the steady-state galvanic corrosion currents are small. Galvanic corrosion will, hence, not be an important mechanism of radionuclide release from the MWF alloys.

Abraham, D. P.; Peterson, J. J.; Katyal, H. K.; Keiser, D. D.; Hilton, B. A.

1999-12-14

417

The IAEA CRP on Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste  

SciTech Connect

In 2003, the IAEA has initiated the Coordinated Research Project (CRP) on 'Studies of Advanced Reactor Technology Options for Effective Incineration of Radioactive Waste'. The overall objective of the CRP, performed within the framework of IAEA's Nuclear Energy Department's Technical Working Group on Fast Reactors, is to increase the capability of Member States in developing and applying advanced technologies in the area of long-lived radioactive waste utilization and transmutation. Twenty institutions from 15 Member States and one international organization participated in this CRP. The CRP concentrated on the assessment of the dynamic behavior of various transmutation systems. The reactor systems investigated comprise critical reactors, sub-critical accelerator driven systems with heavy liquid metal and gas cooling, critical molten salt systems, and hybrid fusion/fission systems. Both fertile and fertile-free fuel options have been investigated. Apart from the benchmarking of steady state core configurations (including the investigation of transmutation potential, burn-up behavior and decay heat of minor actinide (MA) bearing fuels), the CRP participants determined the safety coefficients for the individual systems and, in a second stage, performed transient analyses which reflected the generic safety related behavior of the various reactors types. (authors)

Maschek, W.; Chen, X.; Rineiski, A.; Schikorr, M. [Forschungszentrum Karlsruhe, P.O.Box 3640, D-76021 Karlsruhe (Germany); Stanculescu, A. [International Atomic Energy Agency, Wagramer Strasse 5, Post Office Box 100, A-1400 Vienna (Austria); Arien, B.; Malambu, E. [Belgian Nuclear Research Centre (SCK.CEN), Boeretang 200, B-2400 Mol (Belgium); Bai, Y.; Li, J.; Wu, Y.; Zheng, S. [Chinese Academy of Sciences, ASIPP, P.O. Box 1126, Hefei, Anhui, 230031 (China); Chabert, C.; Peneliau, Y. [CEA Cadarache, F-13108 Saint Paul Lez Durance Cedex (France); Chebeskov, A.; Dekoussar, V.; Vorotyntsev, M. [SSC-IPPE, Bondarenko Square 1, Obninsk 249033, Kaluga Region (Russian Federation); da Cruz, D.F. [Nuclear Research and Consultancy Group - NRG, P.O. Box 25, 1755 ZG Petten (Netherlands); Devan, K.; Gopalakrishnan, V.; Harish, R.; Mohanakrishnan, P.; Pandikumar, G. [Indira Gandhi Centre for Atomic Research, Kalpakkam-603 102, Tamil Nadu (India); Dulla, S.; Ravetto, P. [Politecnico di Torino, Corso Duca degli Abruzzi, 2, 10129 Torino (Italy); Feynberg, O.; Ignatiev, V.; Subbotin, V.; Surenkov, A.; Zakirov, R. [RRC - Kurchatov Institute, Kurchatov Sq., 1, 123182 Moscow (Russian Federation); Kophazi, J.; Szieberth, M. [Budapest University of Technology and Economics, Muegyetem rkp. 9, H-1111 Budapest (Hungary); Morita, K. [Kyushu University, 6-10-1 Hakozaki, Higashi-ku, Fukuoka 812-8581 (Japan); Srivenkatesan, R. [Bhabha Atomic Research Centre, Trombay, Mumbai 400 085 (India); Taczanowski, S. [AGH University of Science and Technology, Al. Mickiewicza 30, 30-059 Krakow (Poland); Tucek, K.; Wider, H. [Joint Research Centre of the European Commission, Westerduinweg 3, 1755 LE Petten (Netherlands); Vertes, P. [Atomic Energy Research Institute, P.O.Box 49, H-1525 Budapest (Hungary); Uhlir, J. [Nuclear Research Institute Rez plc., CZ-250 68 Husinec - Rez 13 (Czech Republic)

2007-07-01

418

Subsurface migration of radionuclides at the Radioactive Waste Management Complex: 1978  

Microsoft Academic Search

This report describes the 1978 core drilling campaign at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. The campaign is part of a continuing program to define radionuclide migration from buried waste. Samples of subsurface materials were collected from core drilled wells and from sample trenches excavated beneath buried waste. The sample materials were radiochemically analyzed and

1980-01-01

419

Chemistry of technetium and rhenium species during low-level radioactive waste vitrification  

Microsoft Academic Search

Radioactive wastes at the Hanford Reservation will be separated into high-level and low-level waste streams for processing. The low-level wastes will be vitrified. Volatile components and technetium compounds may pose potential problems in the vitrification process. In this paper, the chemistry of technetium species is described.

John G. Darab; Peter A. Smith

1996-01-01

420

Interim report to the Nuclear Regulatory Commission on radioactive waste classification  

Microsoft Academic Search

The Lawrence Livermore Laboratory assisted the Nuclear Regulatory Commission in the development of a radioactive waste classification system that will satisfy technical, environmental, and societal concerns. This is an interim report to the NRC on work accomplished to date. It describes a proposed waste-classification system that is based on the final disposition of waste material. The system consists of three

W. C. King; J. J. Cohen

1977-01-01

421

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

Federal Register 2010, 2011, 2012, 2013

...materials and/or 02, 11005699. waste including tons or about radioactive various 1,000 tons waste that is materials (e.g...and be returned per rubber, plastic, 500 tons liquid, appropriate...human-animal combinations. U.S. waste) Activity levels...

2012-08-28

422

Final Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement Richland, Washington  

Microsoft Academic Search

The Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement (HSW EIS) provides environmental and technical information concerning U.S. Department of Energy (DOE) proposed waste management practices at the Hanford Site. The HSW EIS updates analyses of environmental consequences from previous documents and provides evaluations for activities that may be implemented consistent with the Waste Management Programmatic Environmental

M. S. Collins C. M. Borgstrom

2004-01-01

423

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

SciTech Connect

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

Wiersma, B.; Hansen, A.

2013-11-13

424

Wyoming State Briefing Book for low-level radioactive waste management  

SciTech Connect

The Wyoming State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Wyoming. The profile is the result of a survey of NRC licensees in Wyoming. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Wyoming.

Not Available

1981-10-01

425

Connecticut State Briefing Book for low-level radioactive-waste management  

SciTech Connect

The Connecticut State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Connecticut. The profile is the result of a survey of Nuclear Regulatory Commission licensees in Connecticut. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may affect waste management practices in Connecticut.

none,

1981-06-01

426

Mississippi State Briefing Book for low-level radioactive waste management  

SciTech Connect

The Mississippi State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state an federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Mississippi. The profile is the result of a survey of NRC licensees in Mississippi. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Mississippi.

none,

1981-08-01

427

North Carolina State Briefing Book for low-level radioactive waste management  

SciTech Connect

The North Carolina State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in North Carolina. The profile is the result of a survey of NRC licensees in North Carolina. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in North Carolina.

Not Available

1981-08-01

428

Wisconsin State Briefing Book for low-level radioactive waste management  

SciTech Connect

The Wisconsin State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Wisconsin. The profile is the result of a survey of NRC licensees in Wisconsin. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Wisconsin.

Not Available

1980-11-01

429

Ohio State Briefing Book for low-level radioactive waste management  

SciTech Connect

The Ohio State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Ohio. The profile is the result of a survey of NRC licensees in Ohio. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Ohio.

Not Available

1981-04-01

430

New Jersey State Briefing Book for low-level radioactive waste management  

SciTech Connect

The New Jersey state Briefing Book is one of a series of State briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in New Jersey. The profile is the result of a survey of NRC licensees in New Jersey. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in New Jersey.

Not Available

1981-04-01

431

Proposed low-level radioactive waste handling building at Fermi National Accelerator Laboratory, Batavia, Illinois  

SciTech Connect

The US Department of Energy (DOE) has prepared an Environmental Assessment (EA), evaluating the impacts associated with the proposed Low-Level Radioactive Waste Building at the Fermi National Accelerator Laboratory (Fermilab) in Batavia, Illinois. As a result of the high energy physics program at Fermilab, small quantities of low-level radioactive wastes are generated. These wastes are collected, sorted and packaged for shipment to an off-site disposal facility in Hanford, Washington. The proposed project includes the construction of a new building to house, all low-level radioactive waste handling operations. The building would provide workspace for five full-time workers. The proposed project would improve the efficiency and safety of the low-level radioactive waste handling at Fermilab by upgrading equipment and consolidating operations into one facility.

NONE

1995-06-01

432

Radioactive waste management in the USSR: A review of unclassified sources. Volume 2  

SciTech Connect

The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of contaminated areas. Meanwhile, many treatment, solidification, and disposal options for radioactive waste management are being investigated by the Soviets.

Bradley, D.J.

1991-03-01

433

Radioactive waste management in the USSR: A review of unclassified sources  

SciTech Connect

The Soviet Union does not currently have an overall radioactive waste management program or national laws that define objectives, procedures, and standards, although such a law is being developed, according to the Soviets. Occupational health and safety does not appear to receive major attention as it does in Western nations. In addition, construction practices that would be considered marginal in Western facilities show up in Soviet nuclear power and waste management operations. The issues involved with radioactive waste management and environmental restoration are being investigated at several large Soviet institutes; however, there is little apparent interdisciplinary integration between them, or interaction with the USSR Academy of Sciences. It is expected that a consensus on technical solutions will be achieved, but it may be slow in coming, especially for final disposal of high-level radioactive wastes and environmental restoration of contaminated areas. Meanwhile, many treatment, solidification, and disposal options for radioactive waste management are being investigated by the Soviets.

Bradley, D.J.

1991-03-01

434

South Dakota State Briefing Book for low-level radioactive waste management  

SciTech Connect

The South Dakota State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in South Dakota. The profile is the result of a survey of NRC licensees in South Dakota. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in South Dakota.

Not Available

1981-10-01

435

South Carolina State Briefing Book for low-level radioactive waste management  

SciTech Connect

The South Carolina State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in South Carolina. The profile is the result of a survey of NRC licensees in South Carolina. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as definied by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in South Carolina.

Not Available

1981-08-01

436

Pennsylvania State Briefing Book for low-level radioactive waste management  

SciTech Connect

The Pennsylvania State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Pennsylvania. The profile is the result of a survey of NRC licensees in Pennsylvania. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Pennsylvania.

Not Available

1981-04-01

437

Washington State Briefing Book for low-level radioactive waste management  

SciTech Connect

The Washington State Briefing Book is one of a series of state briefing books on low-level radioactive waste management practices. It has been prepared to assist state and federal agency officials in planning for safe low-level radioactive waste disposal. The report contains a profile of low-level radioactive waste generators in Washington. The profile is the result of a survey of NRC licensees in Washington. The briefing book also contains a comprehensive assessment of low-level radioactive waste management issues and concerns as defined by all major interested parties including industry, government, the media, and interest groups. The assessment was developed through personal communications with representatives of interested parties, and through a review of media sources. Lastly, the briefing book provides demographic and socioeconomic data and a discussion of relevant government agencies and activities, all of which may impact waste management practices in Washington.

Not Available

1980-12-01

438

Accumulation of heavy metals by vegetables grown in mine wastes  

SciTech Connect

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 compared to 0% and 25% survival for tomatoes and beans, respectively. Metal concentrations were determined in plant tissues to determine uptake and distribution of metals in the edible plant parts. Individual soil samples were collected beneath each plant to assess metal content in the immediate plant environment. This analysis verified heterogeneous metal content of the mine wastes. The four plant species effectively accumulated and translocated lead, cadmium, arsenic, and zinc. Tomato and bean plants contained the four metals mainly in the roots and little was translocated to the fruits. Radish roots accumulated less metals compared to the leaves, whereas lettuce roots and leaves accumulated similar concentrations of the four metals. Lettuce leaves and radish roots accumulated significantly more metals than bean and tomato fruits. This accumulation pattern suggests that consumption of lettuce leaves or radish roots from plants grown in mine wastes would pose greater risks to humans and wildlife than would consumption of beans or tomatoes grown in the same area. The potential risk may be mitigated somewhat in humans, as vegetables grown in mine wastes exhibited stunted growth and chlorosis.

Cobb, G.P.; Sands, K.; Waters, M.; Wixson, B.G.; Dorward-King, E.

2000-03-01

439

The Hybrid Treatment Process for mixed radioactive and hazardous waste treatment  

SciTech Connect

This paper describes a new process for treating mixed hazardous and radioactive waste, commonly called mixed waste. The process is called the Hybrid Treatment Process (HTP), so named because it is built on the 20 years of experience with vitrification of wastes in melters, and the 12 years of experience with treatment of wastes by the in situ vitrification (ISV) process. It also uses techniques from several additional technologies. Mixed wastes are being generated by both the US Department of Energy (DOE) and by commercial sources. The wastes are those that contain both a hazardous waste regulated under the US Environmental Protection Agency`s (EPA) Resource, Conservation, and Recovery Act (RCRA) regulations and a radioactive waste with source, special nuclear, or byproduct materials. The dual regulation of the wastes increases the complexity of the treatment, handling, and storage of the waste. The DOE is the largest holder and generator of mixed waste. Its mixed wastes are classified as either high-level, transuranic (TRU), or low-level waste (LLW). High-level mixed wastes will be treated in vitrification plants. Transuranic wastes may be disposed of without treatment by obtaining a no-migration variance from the EPA. Lowlevel wastes, however, will require treatment, but treatment systems with sufficient capacity are not yet available to DOE. Various facilities are being proposed for the treatment of low-level waste. The concept described in this paper represents one option for establishing that treatment capacity.

Ross, W.A.; Kindle, C.H.

1992-06-01

440

The Hybrid Treatment Process for mixed radioactive and hazardous waste treatment  

SciTech Connect

This paper describes a new process for treating mixed hazardous and radioactive waste, commonly called mixed waste. The process is called the Hybrid Treatment Process (HTP), so named because it is built on the 20 years of experience with vitrification of wastes in melters, and the 12 years of experience with treatment of wastes by the in situ vitrification (ISV) process. It also uses techniques from several additional technologies. Mixed wastes are being generated by both the US Department of Energy (DOE) and by commercial sources. The wastes are those that contain both a hazardous waste regulated under the US Environmental Protection Agency's (EPA) Resource, Conservation, and Recovery Act (RCRA) regulations and a radioactive waste with source, special nuclear, or byproduct materials. The dual regulation of the wastes increases the complexity of the treatment, handling, and storage of the waste. The DOE is the largest holder and generator of mixed waste. Its mixed wastes are classified as either high-level, transuranic (TRU), or low-level waste (LLW). High-level mixed wastes will be treated in vitrification plants. Transuranic wastes may be disposed of without treatment by obtaining a no-migration variance from the EPA. Lowlevel wastes, however, will require treatment, but treatment systems with sufficient capacity are not yet available to DOE. Various facilities are being proposed for the treatment of low-level waste. The concept described in this paper represents one option for establishing that treatment capacity.

Ross, W.A.; Kindle, C.H.

1992-06-01

441

Development in Waste Volume Reduction Technologies for Highly Contaminated Organic Radioactive Compounds  

SciTech Connect

In nuclear facilities, there is highly contaminated organic radioactive waste such as ion exchange resins for water purification in nuclear power plants. In the future, it is desired that this waste be decomposed to reduce the volume and to become stable. Toshiba has developed a waste treatment system using supercritical water. Furthermore, the new demineralization system without using ion exchange resin has been examined. By this new system, it is possible to reduce the volume of ion exchange resin waste. First, supercritical water was applied to the decomposition of ion exchange resin. The supercritical water whose temperature and pressure exceed 647 K and 22 MPa is an excellent solvent for organic compound decomposition, since oxygen and organic compounds can exist in a single homogeneous fluid phase. Organic compounds can be rapidly and completely decomposed using supercritical water. Almost all the reactants can be kept in the water during organic compound decomposition. Therefore, applying supercritical water to treat organic radioactive waste is an attractive proposition. Actual plant-size apparatus was constructed with a treatment capacity of 1 kg of ion exchange resin per hour. The test revealed that more than 99.9% of the ion exchange resin was decomposed at 723 K and 30 MPa. By this system, ion exchange resin decomposes rapidly and completely, and the volume of ion exchange resin waste can be largely reduced. Secondly, the new demineralization system without using ion exchange resin is described. The new demineralization system consists of a filter and a demineralization cell. A metal mesh filter is adopted to remove crud, and the demineralization cell removes ionic impurities. In this system, it is important whether demineralization can take place at high temperature. Thus, this report describes the test results of the new demineralization process. This demineralization cell consists of an anode, a cathode, and a membrane made of inorganic material. The water containing ion species passes through the inside of the two films between electrodes. The ions pass a film according to an electric charge, and are collected into the room with an electrode. Since all these pieces of the cell consist of inorganic material, it is possible to supply high-temperature water to a direct system. In the bench-scale test, it was confirmed that 90% of cobalt and 80% of sulfuric ion was recovered at 553 K and 8 MPa. By this system, ion exchange resin is unnecessary, and the amount of ion exchange resin waste can be largely reduced. (authors)

AKAI, Yoshie; OHMURA, Hisao; FUJIE, Makoto; MONIWA, Shinobu; SEKI, Shuji; YOTSUYANAGI, Tadasu; EBATA, Masaaki; TAKAGI, Junichi [Toshiba Corporation, 4-1, Ukishima-cho, Kawasaki-ku, Kawasaki 210-0862 (Japan)

2006-07-01

442

Radioactive waste management: review on clearance levels and acceptance criteria legislation, requirements and standards.  

PubMed

In 2011 the joint research project Metrology for Radioactive Waste Management (MetroRWM)(1) of the European Metrology Research Programme (EMRP) started with a total duration of three years. Within this project, new metrological resources for the assessment of radioactive waste, including their calibration with new reference materials traceable to national standards will be developed. This paper gives a review on national, European and international strategies as basis for science-based metrological requirements in clearance and acceptance of radioactive waste. PMID:23582494

Maringer, F J; Surá?, J; Ková?, P; Chauvenet, B; Peyres, V; García-Torańo, E; Cozzella, M L; De Felice, P; Vodenik, B; Hult, M; Rosengĺrd, U; Merimaa, M; Szücs, L; Jeffery, C; Dean, J C J; Tymi?ski, Z; Arnold, D; Hinca, R; Mirescu, G

2013-11-01

443

INNOVATIVE PRACTICES FOR TREATING WASTE STREAMS CONTAINING HEAVY METALS: A WASTE MINIMIZATION APPROACH  

EPA Science Inventory

Innovative practices for treating waste streams containing heavy metals often involve technologies