Solidification of radioactive waste resins using cement mixed with organic material

International Nuclear Information System (INIS)

Laili, Zalina; Yasir, Muhamad Samudi; Wahab, Mohd Abdul

2015-01-01

Solidification of radioactive waste resins using cement mixed with organic material i.e. biochar is described in this paper. Different percentage of biochar (0%, 5%, 8%, 11%, 14% and 18%) was investigated in this study. The characteristics such as compressive strength and leaching behavior were examined in order to evaluate the performance of solidified radioactive waste resins. The results showed that the amount of biochar affect the compressive strength of the solidified resins. Based on the data obtained for the leaching experiments performed, only one formulation showed the leached of Cs-134 from the solidified radioactive waste resins

Polyethylene liners in radioactive mixed waste packages: An engineering study

International Nuclear Information System (INIS)

Whitney, G.A.

1991-05-01

Westinghouse Hanford Company manages and operates the Hanford Site 200 Area radioactive solid waste treatment, storage, and disposal facilities for the US Department of Energy-Richland Operations Office under contract AC06-87RL10930. These facilities include solid waste disposal sites and radioactive solid waste storage areas. This document is 1 in a series of 25 reports or actions identified in a Solid Waste Management Event Fact Sheet and critique report (Appendix E) to address the problem of stored, leaking 183-H Solar Evaporation Basin waste drums. It specifically addresses the adequacy of polyethylene liners used as internal packaging of radioactive mixed waste. This document is to be used by solid waste generators preparing solid waste for storage at Hanford Site facilities. This document is also intended for use by Westinghouse Hanford Company solid waste technical staff involved with approval and acceptance of radioactive solid waste

The Hybrid Treatment Process for mixed radioactive and hazardous waste treatment

International Nuclear Information System (INIS)

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

1992-06-01

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

The management of low-level radioactive and mixed wastes at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Malinauskas, A.P.

1991-01-01

The management of low-level radioactive wastes at Oak Ridge National Laboratory (ORNL) is complicated because of several factors: (1) some of the waste that had been disposed previously does not meet current acceptance criteria; (2) waste is presently being generated both because of ongoing operations as well as the remediation of former disposal sites; and (3) low-level radioactive waste streams that also contain chemically toxic species (mixed wastes) are involved. As a consequence, the waste management activities at ORNL range from the application of standard practices to the development of new technologies to address the various waste management problems. Considerable quantities of low-level radioactive wastes had been disposed in trenches at the ORNL site, and the trenches subsequently covered with landfill. Because the vadose zone is not very extensive in the waste burial area, many of these trenches were located partially or totally within the saturated zone. As a result, considerable amounts of radioactive cesium have been leached from the wastes and have entered the groundwater system. Efforts are currently underway to remediate the problem by excluding groundwater transport through the burial site. A number of waste streams have also been generated that not only contain low levels of radioactive species, but chemically noxious species as well. These ''mixed wastes'' are currently subject to storage and disposal restrictions imposed on both low-level radioactive materials and on substances subject to the Resource Conservation and Recovery Act (RCRA). Technologies currently under development at ORNL to treat these mixed wastes are directed toward separating the RCRA components from the radioactive species, either through destruction of the organic component using chemical or biochemical processes, or the application of solvent extraction or precipitation techniques to effect separation into dependent waste forms. 8 refs., 3 figs

Hanford Central Waste Complex: Radioactive mixed waste storage facility dangerous waste permit application

International Nuclear Information System (INIS)

1991-10-01

The Hanford Site is owned by the US Government and operated by the US Department of Energy Field Office, Richland. The Hanford Site manages and produces dangerous waste and mixed waste (containing both radioactive and dangerous components). The dangerous waste is regulated in accordance with the Resource Conversation and Recovery Act of 1976 and the State of Washington Hazardous Waste Management Act of 1976. The radioactive component of mixed waste is interpreted by the US Department of Energy to be regulated under the Atomic Energy Act of 1954; the nonradioactive dangerous component of mixed waste is interpreted to be regulated under the Resource Conservation and Recovery Act of 1976 and Washington Administrative Code 173--303. Westinghouse Hanford Company is a major contractor to the US Department of Energy Field Office, Richland and serves as co-operator of the Hanford Central Waste Complex. The Hanford Central Waste Complex is an existing and planned series of treatment, storage, and/or disposal units that will centralize the management of solid waste operations at a single location on the Hanford facility. The Hanford Central Waste Complex units include the Radioactive Mixed Waste Storage Facility, the unit addressed by this permit application, and the Waste Receiving and Processing Facility. The Waste Receiving and Processing Facility is covered in a separate permit application submittal

Characterization of radioactive mixed wastes: The scientific perspective

International Nuclear Information System (INIS)

Griest, W.H.; Stokely, J.R. Jr.

1992-01-01

This paper is concerned with the physical and chemical characterization of radioactive mixed wastes (RMW): what should be determined and how; the applications and limitations of current analytical methodologies, promising new technologies, and areas where further methodology research is needed. Constituents to be determined, sample collection, preparation, and analysis are considered. The scope concerns mainly low level and very low level RMW whose activities allow contact handling and analysis by Nuclear Regulatory Commission- or Agreement State-licensed commercial laboratories

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

International Nuclear Information System (INIS)

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

1992-04-01

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

Favorable Decision Upholding Radioactive/Hazardous Mixed Waste Storage Civil Enforcement Policy

Science.gov (United States)

This page contains a copy of the U.S. Court of Appeals (District of Columbia Circuit) decision in Edison Electric Institute, et al. v. EPA, No. 91-1586, which upheld the EPA's August 29, 1991, radioactive/hazardous 'mixed waste' storage civil enforcement policy

Environmental aspects of commercial radioactive waste management

International Nuclear Information System (INIS)

1979-05-01

Volume 2 contains chapters 6 through 10: environmental effects related to radioactive waste management associated with LWR fuel reprocessing - mixed-oxide fuel fabrication plant; environmental effects related to transporting radioactive wastes associated with LWR fuel reprocessing and fabrication; environmental effects related to radioactive waste management associated with LWR fuel reprocessing - retrievable waste storage facility; environmental effects related to geologic isolation of LWR fuel reprocessing wastes; and integrated systems for commercial radioactive waste management

Preparation of radioactive ''mixed'' waste samples for measurement of RCRA [Resource Conservation and Recovery Act] organic compounds

International Nuclear Information System (INIS)

Tomkins, B.A.; Caton, J.E.

1987-01-01

A radioactive ''mixed'' waste typically contains alpha-, beta-, or gamma-emitting radionuclides and varying quantities of semivolatile or volatile organic species, some or all of which may be named specifically by the Resource Conservation and Recovery Act (RCRA). Because there are no acceptable means available currently for disposing of these mixed wastes, they are presently stored above-ground in sealed drums. For this reason, analytical procedures which can determine RCRA organics in radioactive waste are necessary for deciding the proper approach for disposal. An important goal of this work is the development of methods for preparing mixed waste samples in a manner which allows the RCRA organics to be measured in conventional organic analysis laboratories without special precautions. Analytical procedures developed for handling mixed waste samples must satisfy not only the usual constraints present in any trace-level organic chemical determination, but also those needed to insure the protection of the operator from radioactive contamination. Consequently, procedures should be designed to use the least amount of radioactive sample commensurate with achieving acceptable sensitivity with the RCRA analytical methods. Furthermore, the unusual laboratory glassware which would normally be used should be replaced with disposable materials wherever possible, in order to reduce the ''clean-up'' time required, and thereby reduce the operator's exposure to radioactivity. Actual sample handling should be reduced to the absolute minimum. Finally, the final isolate must exhibit a sufficiently low level of alpha, beta, or gamma activity to permit detailed characterization in a conventional organic analysis laboratory. 4 refs., 5 tabs

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

International Nuclear Information System (INIS)

1991-09-01

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

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

International Nuclear Information System (INIS)

1991-07-01

The purpose of this document is to provide the acceptance criteria for the transfer of hazardous chemical, radioactive, and mixed waste to Lawrence Berkeley Laboratory's (LBL) Hazardous Waste Handling Facility (HWHF). These guidelines describe how a generator of wastes can meet LBL's acceptance criteria for hazardous chemical, radioactive, and mixed waste. 9 figs

Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility

International Nuclear Information System (INIS)

Albert, R.

1992-01-01

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

National profile on commercially generated low-level radioactive mixed waste

Energy Technology Data Exchange (ETDEWEB)

Klein, J.A.; Mrochek, J.E.; Jolley, R.L.; Osborne-Lee, I.W.; Francis, A.A.; Wright, T. [Oak Ridge National Lab., TN (United States)

1992-12-01

This report details the findings and conclusions drawn from a survey undertaken as part of a joint US Nuclear Regulatory Commission and US Environmental Protection Agency-sponsored project entitled ``National Profile on Commercially Generated Low-Level Radioactive Mixed Waste.`` The overall objective of the work was to compile a national profile on the volumes, characteristics, and treatability of commercially generated low-level mixed waste for 1990 by five major facility categories-academic, industrial, medical, and NRC-/Agreement State-licensed goverment facilities and nuclear utilities. Included in this report are descriptions of the methodology used to collect and collate the data, the procedures used to estimate the mixed waste generation rate for commercial facilities in the United States in 1990, and the identification of available treatment technologies to meet applicable EPA treatment standards (40 CFR Part 268) and, if possible, to render the hazardous component of specific mixed waste streams nonhazardous. The report also contains information on existing and potential commercial waste treatment facilities that may provide treatment for specific waste streams identified in the national survey. The report does not include any aspect of the Department of Energy`s (DOES) management of mixed waste and generally does not address wastes from remedial action activities.

National profile on commercially generated low-level radioactive mixed waste

International Nuclear Information System (INIS)

Klein, J.A.; Mrochek, J.E.; Jolley, R.L.; Osborne-Lee, I.W.; Francis, A.A.; Wright, T.

1992-12-01

This report details the findings and conclusions drawn from a survey undertaken as part of a joint US Nuclear Regulatory Commission and US Environmental Protection Agency-sponsored project entitled ''National Profile on Commercially Generated Low-Level Radioactive Mixed Waste.'' The overall objective of the work was to compile a national profile on the volumes, characteristics, and treatability of commercially generated low-level mixed waste for 1990 by five major facility categories-academic, industrial, medical, and NRC-/Agreement State-licensed goverment facilities and nuclear utilities. Included in this report are descriptions of the methodology used to collect and collate the data, the procedures used to estimate the mixed waste generation rate for commercial facilities in the United States in 1990, and the identification of available treatment technologies to meet applicable EPA treatment standards (40 CFR Part 268) and, if possible, to render the hazardous component of specific mixed waste streams nonhazardous. The report also contains information on existing and potential commercial waste treatment facilities that may provide treatment for specific waste streams identified in the national survey. The report does not include any aspect of the Department of Energy's (DOES) management of mixed waste and generally does not address wastes from remedial action activities

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

International Nuclear Information System (INIS)

1994-01-01

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

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

International Nuclear Information System (INIS)

1995-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-21

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.

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

International Nuclear Information System (INIS)

1994-01-01

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

In situ vitrification of a mixed radioactive and hazardous waste site

International Nuclear Information System (INIS)

Campbell, B.E.; Koegler, S.S.

1990-11-01

A large-scale test of the in situ vitrification (ISV) process was performed on a mixed radioactive and hazardous-chemical contaminated waste site on the Hanford Site in southeastern Washington State. A mixed-waste site was selected for this large-scale test to demonstrate the applicability of ISV to mixed wastes common to many US Department of Energy (DOE) sites. In situ vitrification is a thermal process that converts contaminated soil into a durable, leach-resistant product. Electrodes are inserted into the ground. The goals of the test are to demonstrate at least 99% retention of fission products and hazardous metals in the ISV glass during the test; demonstrate the ability of the ISV off-gas treatment system to process a waste site containing significant quantities of combustible material and demonstrate the ability of ISV to vitrify the site to a depth of 20 ft or greater. The test was completed in April 1990. 5 figs

Molten salt oxidation of mixed wastes: Separation of radioactive materials and Resource Conservation and Recovery Act (RCRA) materials

International Nuclear Information System (INIS)

Bell, J.T.; Haas, P.A.; Rudolph, J.C.

1993-01-01

The Oak Ridge National Laboratory (ORNL) is involved in a program to apply a molten salt oxidation (MSO) process to the treatment of mixed wastes at Oak Ridge and other Department of Energy (DOE) sites. Mixed wastes are defined as those wastes that contain both radioactive components, which are regulated by the atomic energy legislation, and hazardous waste components, which are regulated under the Resource Conservation and Recovery Act (RCRA). A major part of our ORNL program involves the development of separation technologies that are necessary for the complete treatment of mixed wastes. The residues from the MSO treatment of the mixed wastes must be processed further to separate the radioactive components, to concentrate and recycle residues, or to convert the residues into forms acceptable for final disposal. This paper is a review of the MSO requirements for separation technologies, the information now available, and the concepts for our development studies

Idaho National Engineering Laboratory hazardous and radioactive mixed waste identification and characterization report for CY 1986

International Nuclear Information System (INIS)

Nishimoto, D.D.

1987-05-01

This report provides updated tabulations of the hazardous and radioactive mixed wastes generated and/or handled during CY 1986 at each INEL facility operated by EG and G, or any other operating contractor at the Site. These wastes are described in tabular form, providing information such as composition, generating process, contact person, EPA hazardous waste designation, quantity shipped off site (if applicable), and quantity in storage. Waste generation projections for the next ten years are also included for all INEL facilities. Finally, since many of EG and G's inactive disposal sites may prove to be significant sources of either hazardous or radioactive mixed wastes as remedial action activities under RCRA or CERCLA progress, information on these sites is provided. 2 refs., 1 fig., 8 tabs

Environmental restoration and management of low-level radioactive and mixed waste at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Kendrick, C.M.

1994-01-01

Management of radioactive waste at Oak Ridge National Laboratory (ORNL) must address several major challenges. First, contaminants from some disposed wastes are leaching into the groundwater and these disposal sites must be remediated. Second, some of these ''legacy'' wastes, as well as currently generated radioactive wastes, are also contaminated with chemicals, including polychlorinated biphenyls (PCBs), solvents, and metals (i.e., mixed waste). Third, wastes containing long-lived radionuclides in concentrations above established limits have been determined unsuited for disposal on the Oak Ridge Reservation. Reflecting these challenges, ORNL's strategy for managing its radioactive wastes continues to evolve with the development of improved technologies and site-specific adaptation of some standard technologies

Los Alamos Controlled Air Incinerator for hazardous chemical and mixed radioactive wastes

International Nuclear Information System (INIS)

Vavruska, J.S.; Borduin, L.C.; Hutchins, D.A.; Koenig, R.A.; Warner, C.L.

1986-01-01

The Los Alamos Controlled Air Incinerator (CAI) is currently the only radioactive waste incineration facility in the US permitted to treat polychlorinated biphenyls (PCBs). The CAI was developed in the mid-1970's as a demonstration system for volume reduction of transuranic (TRU) contaminated combustible solid wastes. It has since undergone additions and modifications to accommodate hazardous chemical wastes in response to a need within the Department of Energy (DOE) to treat mixed radioactive/chemical wastes. An overview of these additions which include a liquid feed system, a high intensity liquid injection burner, and an activated carbon adsorption unit is presented here. Also included is a discussion of the procedures required for Toxic Substances Control Act (TSCA) and Resource Conservation and Recovery Act (RCRA) permitting of the CAI

Method of storing radioactive wastes

International Nuclear Information System (INIS)

Adachi, Toshio; Hiratake, Susumu.

1980-01-01

Purpose: To reduce the radiation doses externally irradiated from treated radioactive waste and also reduce the separation of radioactive nuclide due to external environmental factors such as air, water or the like. Method: Radioactive waste adhered with radioactive nuclide to solid material is molten to mix and submerge the radioactive nuclide adhered to the surface of the solid material into molten material. Then, the radioactive nuclide thus mixed is solidified to store the waste in solidified state. (Aizawa, K.)

Transportation of radioactive, hazardous, and mixed wastes: Material identification is the key

International Nuclear Information System (INIS)

Stancell, D.F.; Willaford, D.M.

1992-01-01

This paper will discuss how material identification and classification will result in an accurate determination of regulatory requirements, and will assure safe and compliant shipment of radioactive, hazardous, and mixed wastes. The primary focus of the paper is a discussion of lessons learned by the Department of Energy in making waste shipments, and how this can be applied to future mixed waste shipments. There will be a brief discussion of the Department's regulatory compliance program, including a presentation of compliance audit results, and how regulatory issues are addressed through effective information exchange, technical assistance, and compliance training. A detailed discussion will follow, which describes cases involving material identification and classification problems. Examples will include both RCRA waste and uranium mill tailings shipments. The paper will conclude with a discussion concerning the application of these lessons to future mixed waste shipments proposed by the Department. (author)

Long-term durability of polyethylene for encapsulation of low-level radioactive, hazardous, and mixed wastes

International Nuclear Information System (INIS)

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

1991-01-01

The durability of polyethylene waste forms for treatment of low-level radioactive, hazardous, and mixed wastes is examined. Specific potential failure mechanisms investigated include biodegradation, radiation, chemical attack, flammability, environmental stress cracking, and photodegradation. These data are supported by results from waste form performance testing including compressive yield strength, water immersion, thermal cycling, leachability of radioactive and hazardous species, irradiation, biodegradation, and flammability. Polyethylene was found to be extremely resistant to each of these potential failure modes under anticipated storage and disposal conditions. 16 refs., 3 figs., 1 tab

Groundwater flow analysis using mixed hybrid finite element method for radioactive waste disposal facilities

International Nuclear Information System (INIS)

Aoki, Hiroomi; Shimomura, Masanori; Kawakami, Hiroto; Suzuki, Shunichi

2011-01-01

In safety assessments of radioactive waste disposal facilities, ground water flow analysis are used for calculating the radionuclide transport pathway and the infiltration flow rate of groundwater into the disposal facilities. For this type of calculations, the mixed hybrid finite element method has been used and discussed about the accuracy of ones in Europe. This paper puts great emphasis on the infiltration flow rate of groundwater into the disposal facilities, and describes the accuracy of results obtained from mixed hybrid finite element method by comparing of local water mass conservation and the reliability of the element breakdown numbers among the mixed hybrid finite element method, finite volume method and nondegenerated finite element method. (author)

Measurement of the leaching rate of radionuclide 134Cs from the solidified radioactive sources in Portland cement mixed with microsilica and barite matrixes

International Nuclear Information System (INIS)

Shaaban, Ismail; Assi, Nasim

2011-01-01

Portland cement was mixed with radionuclide 134 Cs to produce low-level radioactive sources. These sources were surrounded with cement mixed with different materials like microsilica and barite. The leaching rate of 134 Cs from the solidified radioactive source in Portland cement alone was found to be 4.481 x 10 -4 g/cm 2 per day. Mixing this Portland cement with microsilica and with barite reduced significantly the leaching rate to 1.091 x 10 -4 g/cm 2 per day and 3.153 x 10 -4 g/cm 2 per day for 1 wt.% mixing, and to 1.401 x 10 -5 g/cm 2 per day and 1.703 x 10 -4 g/cm 2 per day for 3 wt.% mixing, respectively. It was also found that the application of a latex paint reduced these leaching rates by about 6.5%, 20.3% and 13.3% for Portland cement, cement mixed with microsilica and with barite, respectively. The leaching data were also analyzed using the polynomial method. The obtained results showed that cement mixed with microsilica and with barite can be effectively used for radioactive sources solidification.

Development of Characterization Protocol for Mixed Liquid Radioactive Waste Classification

International Nuclear Information System (INIS)

Norasalwa Zakaria; Syed Asraf Wafa; Wo, Y.M.; Sarimah Mahat; Mohamad Annuar Assadat Husain

2017-01-01

Mixed organic liquid waste generated from health-care and research activities containing tritium, carbon-14, and other radionuclide posed specific challenges in its management. Often, this waste becomes legacy waste in many nuclear facilities and being considered as 'problematic' waste. One of the most important recommendations made by IAEA is to perform multistage processes aiming at declassification of the waste. At this moment, approximately 3000 bottles of mixed liquid waste, with estimated volume of 6000 litres are currently stored at the National Radioactive Waste Management Centre, Malaysia and some have been stored for more than 25 years. The aim of this study is to develop a characterization protocol towards reclassification of these wastes. The characterization protocol entails waste identification, waste screening and segregation, and analytical radionuclides profiling using analytical procedures involving gross alpha beta, and gamma spectrometry. The results obtained from the characterization protocol are used to establish criteria for speedy classification of the waste. (author)

Development of characterization protocol for mixed liquid radioactive waste classification

Energy Technology Data Exchange (ETDEWEB)

Zakaria, Norasalwa, E-mail: norasalwa@nuclearmalaysia.gov.my [Waste Technology Development Centre, Malaysian Nuclear Agency, 43000 Kajang, Selangor (Malaysia); Wafa, Syed Asraf [Radioisotop Technology and Innovation, Malaysian Nuclear Agency, 43000 Kajang, Selangor (Malaysia); Wo, Yii Mei [Radiochemistry and Environment, Malaysian Nuclear Agency, 43000 Kajang, Selangor (Malaysia); Mahat, Sarimah [Material Technology Group, Malaysian Nuclear Agency, 43000 Kajang, Selangor (Malaysia)

2015-04-29

Mixed liquid organic waste generated from health-care and research activities containing tritium, carbon-14, and other radionuclides posed specific challenges in its management. Often, these wastes become legacy waste in many nuclear facilities and being considered as ‘problematic’ waste. One of the most important recommendations made by IAEA is to perform multistage processes aiming at declassification of the waste. At this moment, approximately 3000 bottles of mixed liquid waste, with estimated volume of 6000 litres are currently stored at the National Radioactive Waste Management Centre, Malaysia and some have been stored for more than 25 years. The aim of this study is to develop a characterization protocol towards reclassification of these wastes. The characterization protocol entails waste identification, waste screening and segregation, and analytical radionuclides profiling using various analytical procedures including gross alpha/ gross beta, gamma spectrometry, and LSC method. The results obtained from the characterization protocol are used to establish criteria for speedy classification of the waste.

Characteristics of medically related low-level radioactive waste

International Nuclear Information System (INIS)

Weir, G.J. Jr.; Teele, B.

1986-07-01

This report describes a survey that identified the current sources of medically generated radioactive wastes. Included are recommendations on how to reduce the volume of medically-related material classified as low-level radioactive wastes, to improve handling techniques for long-lived radioisotopes, and for options for the use of radioactive materials in medical studies. 8 refs., 11 tabs

Environmental restoration and management of low-level radioactive and mixed waste at Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Kendrick, C.M.

1994-03-01

Management of radioactive waste at Oak Ridge National Laboratory (ORNL) must address several major challenges. First, contaminants from some disposed wastes are leaching into the groundwater and these disposal sites must be remediated. Second, some of these ``legacy`` wastes, as well as currently generated radioactive wastes, are also contaminated with chemicals, including polychlorinated biphenyls (PCBs), solvents, and metals (i.e., mixed waste). Third, wastes containing long-lived radionuclides in concentrations above established limits have been determined unsuited for disposal on the Oak Ridge Reservation. Reflecting these challenges, ORNL`s strategy for managing its radioactive wastes continues to evolve with the development of improved technologies and site-specific adaptation of some standard technologies.

Fire hazard analysis of the radioactive mixed waste trenchs

International Nuclear Information System (INIS)

McDonald, K.M.

1995-01-01

This Fire Hazards Analysis (FHA) is intended to assess comprehensively the risk from fire associated with the disposal of low level radioactive mixed waste in trenches within the lined landfills, provided by Project W-025, designated Trench 31 and 34 of the Burial Ground 218-W-5. Elements within the FHA make recommendations for minimizing risk to workers, the public, and the environment from fire during the course of the operation's activity. Transient flammables and combustibles present that support the operation's activity are considered and included in the analysis. The graded FHA contains the following elements: description of construction, protection of essential safety class equipment, fire protection features, description of fire hazards, life safety considerations, critical process equipment, high value property, damage potential--maximum credible fire loss (MCFL) and maximum possible fire loss (MPFL), fire department/brigade response, recovery potential, potential for a toxic, biological and/or radiation incident due to a fire, emergency planning, security considerations related to fire protection, natural hazards (earthquake, flood, wind) impact on fire safety, and exposure fire potential, including the potential for fire spread between fire areas. Recommendations for limiting risk are made in the text of this report and printed in bold type. All recommendations are repeated in a list in Section 18.0

Advanced Off-Gas Control System Design For Radioactive And Mixed Waste Treatment

International Nuclear Information System (INIS)

Nick Soelberg

2005-01-01

Treatment of radioactive and mixed wastes is often required to destroy or immobilize hazardous constituents, reduce waste volume, and convert the waste to a form suitable for final disposal. These kinds of treatments usually evolve off-gas. Air emission regulations have become increasingly stringent in recent years. Mixed waste thermal treatment in the United States is now generally regulated under the Hazardous Waste Combustor (HWC) Maximum Achievable Control Technology (MACT) standards. These standards impose unprecedented requirements for operation, monitoring and control, and emissions control. Off-gas control technologies and system designs that were satisfactorily proven in mixed waste operation prior to the implementation of new regulatory standards are in some cases no longer suitable in new mixed waste treatment system designs. Some mixed waste treatment facilities have been shut down rather than have excessively restrictive feed rate limits or facility upgrades to comply with the new standards. New mixed waste treatment facilities in the U. S. are being designed to operate in compliance with the HWC MACT standards. Activities have been underway for the past 10 years at the INL and elsewhere to identify, develop, demonstrate, and design technologies for enabling HWC MACT compliance for mixed waste treatment facilities. Some specific off-gas control technologies and system designs have been identified and tested to show that even the stringent HWC MACT standards can be met, while minimizing treatment facility size and cost

Vitrification of low level and mixed (radioactive and hazardous) wastes: Lessons learned from high level waste vitrification

International Nuclear Information System (INIS)

Jantzen, C.M.

1994-01-01

Borosilicate glasses will be used in the USA and in Europe immobilize radioactive high level liquid wastes (HLLW) for ultimate geologic disposal. Simultaneously, tehnologies are being developed by the US Department of Energy's (DOE) Nuclear Facility sites to immobilize low-level and mixed (radioactive and hazardous) wastes (LLMW) in durable glass formulations for permanent disposal or long-term storage. Vitrification of LLMW achieves large volume reductions (86--97 %) which minimize the associated long-term storage costs. Vitrification of LLMW also ensures that mixed wastes are stabilized to the highest level reasonably possible, e.g. equivalent to HLLW, in order to meet both current and future regulatory waste disposal specifications The tehnologies being developed for vitrification of LLMW rely heavily on the technologies developed for HLLW and the lessons learned about process and product control

Choosing solidification or vitrification for low-level radioactive and mixed waste treatment

International Nuclear Information System (INIS)

Gimpel, R.F.

1992-01-01

Solidification (making concrete) and vitrification (making glass) are frequently the treatment methods recommended for treating inorganic or radioactive wastes. Solidification is generally perceived as the most economical treatment method. Whereas, vitrification is considered (by many) as the most effective of all treatment methods. Unfortunately, vitrification has acquired the stigma that it is too expensive to receive further consideration as an alternative to solidification in high volume treatment applications. Ironically, economic studies, as presented in this paper, show that vitrification may be more competitive in some high volume applications. Ex-situ solidification and vitrification are the competing methods for treating in excess of 450 000m 3 of low-level radioactive and mixed waste at the Fernald Environmental Management Project (FEMP or simply, Fernald) located near Cincinnati, Ohio. This paper summarizes how Fernald is choosing between solidification and vitrification as the primary waste treatment method

Choosing solidification or vitrification for low-level radioactive and mixed waste treatment

International Nuclear Information System (INIS)

Gimpel, R.F.

1992-01-01

Solidification (making concrete) and vitrification (making glass) are frequently the treatment methods recommended for treating inorganic or radioactive wastes. Solidification is generally perceived as the most economical treatment method. Whereas, vitrification is considered (by many) as the most effective of all treatment methods. Unfortunately, vitrification has acquired the stigma that it is too expensive to receive further consideration as an alternative to solidification in high volume treatment applications. Ironically, economic studies, as presented in this paper, show that vitrification may be more competitive in some high volume applications. Ex-situ solidification and vitrification are the competing methods for treating in excess of 450,000 m 3 of low-level radioactive and mixed waste at the Fernald Environmental Management Project (FEMP or simply, Fernald) located near Cincinnati, Ohio. This paper summarized how Fernald is choosing between solidification and vitrification as the primary waste treatment method

Treatment of radioactive mixed wastes in commercial low-level wastes

International Nuclear Information System (INIS)

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

1985-01-01

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

Mixed-layered bismuth--oxygen--iodine materials for capture and waste disposal of radioactive iodine

Science.gov (United States)

Krumhansl, James L; Nenoff, Tina M

2015-01-06

Materials and methods of synthesizing mixed-layered bismuth oxy-iodine materials, which can be synthesized in the presence of aqueous radioactive iodine species found in caustic solutions (e.g. NaOH or KOH). This technology provides a one-step process for both iodine sequestration and storage from nuclear fuel cycles. It results in materials that will be durable for repository conditions much like those found in Waste Isolation Pilot Plant (WIPP) and estimated for Yucca Mountain (YMP). By controlled reactant concentrations, optimized compositions of these mixed-layered bismuth oxy-iodine inorganic materials are produced that have both a high iodine weight percentage and a low solubility in groundwater environments.

Mixed-layered bismuth-oxygen-iodine materials for capture and waste disposal of radioactive iodine

Science.gov (United States)

Krumhansl, James L; Nenoff, Tina M

2013-02-26

Materials and methods of synthesizing mixed-layered bismuth oxy-iodine materials, which can be synthesized in the presence of aqueous radioactive iodine species found in caustic solutions (e.g. NaOH or KOH). This technology provides a one-step process for both iodine sequestration and storage from nuclear fuel cycles. It results in materials that will be durable for repository conditions much like those found in Waste Isolation Pilot Plant (WIPP) and estimated for Yucca Mountain (YMP). By controlled reactant concentrations, optimized compositions of these mixed-layered bismuth oxy-iodine inorganic materials are produced that have both a high iodine weight percentage and a low solubility in groundwater environments.

Issues related to public perception of radioactive waste management options

International Nuclear Information System (INIS)

Taylor, D.M.

2007-01-01

Public perceptions about radioactive waste are generally rather or even strongly negative. They are also very poorly informed. This is rather unfortunate as it is these perceptions that appear to greatly influence the Public views on nuclear energy in general. This, in turn, has had an influence on political decisions. On the other hand, in a very clear majority of the Member States of the European Union, the Public have already indicated that they would be ready to accept the important role of nuclear in their future energy mix as long as all the radioactive wastes can be safely managed. However perceptions about nuclear energy and radioactive waste should be seen in the context of the Public wider perceptions on energy and, in particular, the role in the future of different sources. It may be wrong for political decisions on nuclear energy in the future to rely to heavily on the Public perceptions. (author)

Pretreatment method for radioactive iodine-containing liquid wastes and pretreatment device

International Nuclear Information System (INIS)

Wakaida, Yasuo.

1996-01-01

Heretofore, radioactive iodine-containing liquid wastes have been discharged directly to a storing and decaying storage vessel to conduct a water draining treatment. In the present invention, the radioactive iodine-containing liquid wastes to be discharged are not discharged to the storage vessel directly but injected to a filling tank, as a pretreatment, to distinguish whether proteins are mixed in the liquid wastes or not. When proteins are mixed, miscellaneous materials such as proteins are recovered and removed by a protein processing system. When proteins are not mixed, radioactive iodine is recovered and removed directly by an iodine processing system. With such procedures, water draining treatment in the storing and decaying storage vessel is mitigated, and even when the amount of the radioactive iodine-containing liquid wastes is increased, the existent maintaining and decaying storage vessel can be used as it is. Accordingly, a safe water draining treatment with good efficiency can be conducted relative to radioactive iodine-containing liquid wastes at a reduced cost. (T.M.)

Transient thermal analysis for radioactive liquid mixing operations in a large-scaled tank

International Nuclear Information System (INIS)

Lee, S. Y.; Smith, F. G. III

2014-01-01

A transient heat balance model was developed to assess the impact of a Submersible Mixer Pump (SMP) on radioactive liquid temperature during the process of waste mixing and removal for the high-level radioactive materials stored in Savannah River Site (SRS) tanks. The model results will be mainly used to determine the SMP design impacts on the waste tank temperature during operations and to develop a specification for a new SMP design to replace existing longshaft mixer pumps used during waste removal. The present model was benchmarked against the test data obtained by the tank measurement to examine the quantitative thermal response of the tank and to establish the reference conditions of the operating variables under no SMP operation. The results showed that the model predictions agreed with the test data of the waste temperatures within about 10%

Supplemental design requirements document enhanced radioactive and mixed waste storage Phase V Project W-112

International Nuclear Information System (INIS)

Ocampo, V.P.; Boothe, G.F.; Greager, T.M.; Johnson, K.D.; Kooiker, S.L.; Martin, J.D.

1994-11-01

This document provides additional and supplemental information to WHC-SD-W112-FDC-001, Project W-112 for radioactive and mixed waste storage. It provides additional requirements for the design and summarizes Westinghouse Hanford Company key design guidance and establishes the technical baseline agreements to be used for definitive design of the Project W-112 facilities

In situ vitrification of a mixed radioactive and hazardous waste site

International Nuclear Information System (INIS)

Koegler, S.S.

1990-01-01

This paper reports on a large-scale test of the in situ vitrification (ISV) process being performed on a mixed radioactive and hazardous-chemical contaminated waste site on the Hanford Site in southeastern Washington state. A mixed-waste site was selected for this large-scale test to demonstrate the applicability of ISV to mixed wastes common to many U.S. Department of Energy (DOE) sites. In situ vitrification is a thermal process that converts contaminated soil into a durable, leach-resistant product. Electrodes are inserted into the ground to the desired treatment depth, and a layer of electrically conductive material (a starter path) is placed between the electrodes. Electrical power is applied to the electrodes causing the conductive material to melt, thus melting the surrounding soil. Electrical energy is transferred to the molten soil through Joule (resistance) heating and the soil continues to melt to the desired depth, at which time the power to the electrodes is discontinued. A hood placed over the area to be vitrified allows the off gases from the process to be treated before their release to the atmosphere. After completion of the melt, the molten-soil cools and solidifies, and soil is backfilled over the subsided area

Cs+ and Sr2+ adsorption selectivity of zeolites in relation to radioactive decontamination

Directory of Open Access Journals (Sweden)

M.W. Munthali

2015-09-01

Full Text Available Zeolites are used as adsorbents of cationic elements in the radioactive decontamination process of water, soil and others. We determined Cs+ and Sr2+ adsorption selectivity of some zeolites to know effective zeolite species for the decontamination of radioactive Cs and Sr. A 30 mL mixed solution containing up to 15 mg L−1 of non-radioactive Cs+ or Sr+ and up to 0.50 M of Na+ or K+ was mixed with 0.5 g of Linde-type A, Na-P1, faujasite X, faujasite Y and mordenite. Among the zeolites, mordenite had the highest Cs+ adsorption selectivity, and the selectivity had no correlation to the cation exchange capacity (CEC of the zeolites. In contrast, Sr2+ adsorption selectivity of the zeolites positively correlated with the CEC of the zeolites; Linde-type A with the highest CEC showed the highest adsorption selectivity, and its adsorption rate was more than 99.9% even in the presence of 0.5 M K+. A simulated soil decontamination experiment of Cs from a Cs-retaining vermiculite by using mordenite and that of Sr from a Sr-retaining vermiculite by using Linde-type A showed decontamination rates of more than 90%.

Readiness assessment plan for the Radioactive Mixed Waste Land Disposal Facility (Trench 31)

International Nuclear Information System (INIS)

Irons, L.G.

1994-01-01

This document provides the Readiness Assessment Plan (RAP) for the Project W-025 (Radioactive Mixed Waste Land Disposal Facility) Readiness Assessment (RA). The RAP documents prerequisites to be met by the operating organization prior to the RA. The RAP is to be implemented by the RA Team identified in the RAP. The RA Team is to verify the facility's compliance with criteria identified in the RAP. The criteria are based upon the open-quotes Core Requirementsclose quotes listed in DOE Order 5480.31, open-quotes Startup and Restart of Nuclear Facilitiesclose quotes

Radioactive wastes

International Nuclear Information System (INIS)

Devarakonda, M.S.; Melvin, J.M.

1994-01-01

This paper is part of the Annual Literature Review issue of Water Environment Research. The review attempts to provide a concise summary of important water-related environmental science and engineering literature of the past year, of which 40 separate topics are discussed. On the topic of radioactive wastes, the present paper deals with the following aspects: national programs; waste repositories; mixed wastes; waste processing and decommissioning; environmental occurrence and transport of radionuclides; and remedial actions and treatment. 178 refs

Nuclide-related exemption limits for radioactive materials

International Nuclear Information System (INIS)

Przyborowski, S.; Scheler, R.

1984-01-01

A procedure has been proposed for setting nuclide-related exemption limits for radioactive materials. It consists in grading the radionuclides into 4 groups of radiotoxicity and assigning only one activity limit to each of them. Examples are given for about 200 radionuclides. The radiation exposures resulting from a continuous steady release of activity fractions or from short-period release of the entire activity were assessed to remain below 0.1 ALI in both of these borderline cases, thus justifying the license-free utilization of radioactive materials below the exemption limits. (author)

Summary of the law relating to atomic energy and radioactive substances

International Nuclear Information System (INIS)

Sim, D.F.; Ritchie, K.J.S.

1982-04-01

The law relating to atomic energy and radioactive substances in the United Kingdom is summarized under the following headings: the Common Law; legislation (Atomic Energy Act 1946; Radioactive Substances Acts 1948 and 1960; Electricity (Amendment) Act 1961; Nuclear Installations Act 1965 and 1969 (and subordinate legislation); Secretary of State for Trade and Industry Order 1970; Radiological Protection Act 1970 (as amended); Air Navigation (Restriction of Flying)(Atomic Energy Establishments) Regulations 1981; Nuclear Safeguards and Electricity (Finance) Act 1978; legislation relating to the UK Atomic Energy Authority); Regulations under the Factories Act 1961; Regulations relating to educational establishments; Regulations and Orders relating to food and medicines; Regulations, etc., affecting the transport of radioactive materials; Regulations under the Social Security Act 1975; control of import and export; the Euratom Treaty; important non-statutory Codes of Practice, etc.; international conventions, etc., relating to the peaceful use of atomic energy and radioactive substances, in which the United Kingdom is interested; foreign legislation. (U.K.)

Adsorption of Radioactive Cesium to Illite-Sericite Mixed Clays

Science.gov (United States)

Hwang, J. H.; Choung, S.; Park, C. S.; Jeon, S.; Han, J. H.; Han, W. S.

2016-12-01

Once radioactive cesium is released into aquatic environments through nuclear accidents such as Chernobyl and Fukushima, it is harmful to human and ecological system for a long time (t1/2 = 30.2 years) because of its chemical toxicity and γ-radiation. Sorption mechanism is mainly applied to remove the cesium from aquatic environments. Illite is one of effective sorbent, considering economical cost for remediation. Although natural illite is typically produced as a mixture with sericite formed by phyllic alteration in hydrothermal ore deposits, the effects of illite-sericite mixed clays on cesium sorption was rarely studied. This study evaluated the sorption properties of cesium to natural illite collected at Yeongdong in Korea as the world-largest illite producing areas (termed "Yeongdong illite"). The illite samples were analyzed by XRF, XRD, FT-IR and SEM-EDX to determine mineralogy, chemical composition, and morphological characteristics, and used for batch sorption experiments. Most of "Yeongdong illite" samples predominantly consist of sericite, quartz, albite, plagioclase feldspar and with minor illite. Cesium sorption distribution coefficients (Kd,Cs) of various "Yeongdong illite" samples ranged from 500 to 4000 L/kg at low aqueous concentration (Cw 10-7 M). Considering Kd,Cs values were 400 and 6000 using reference sericite and illite materials, respectively, in this study, these results suggested that high contents of sericite significantly affect the decrease of sorption capabilities for radiocesium by natural illite (i.e., illite-sericite mixed clay).

Radioactive-site-remediation technologies seminar. Speaker slide copies

International Nuclear Information System (INIS)

1992-06-01

The contents of this report include the following: approaches to sampling radioactive heterogeneous waste; soil characterization methodology for determining application of soil washing; vorce (volume reduction/chemical extraction) program; treatment of radioactive compounds in water; polymer solidification of low-level radioactive, hazardous, and mixed waste; in situ vitrification of soils contaminated with radioactive and mixed wastes; decontamination of contaminated buildings; incineration of radioactive waste; in situ stabilization/solidification with cement-based grouts; environmental restoration and waste management; removal of contaminants from soils by electrokinetics; and treatment, compaction, and disposal of residual radioactive waste

Virtual cascade impactors for the collection of radioactive atmospheric aerosols

International Nuclear Information System (INIS)

Berner, A.

1988-01-01

Starting from impaction theory, the properties of virtual impaction stages are discussed and compared to classical impactors. Virtual impaction stages offer the benefit of sampling coarse particles without bouncing and reentrainment, but turbulent mixing affects the performance of virtual stages. Future research should concentrate on special configurations for reducing the effects of turbulent mixing. Virtual impaction stages for sampling radioactive aerosols are to be designed in regard of the analytical requirements, the purpose of the measurements, and the aerosol. Therefore, the aerosol components expected in radioactive aerosols are discussed on the background of the multimodal model, which relates the size distribution to the genesis and the history of the aerosol. Reference is made to recent data of the radioactive atmospheric aerosol

Summary of the law relating to atomic energy and radioactive substances

International Nuclear Information System (INIS)

Sim, D.F.; Ritchie, K.J.S.

1981-04-01

A summary is given of the law relating to atomic energy and radioactive substances revised as at 31 March 1981 under the following headings: (1) The common law. (2) The legislation. (3) Regulations under the factories act 1961. (4) Regulations relating to educational establishments. (5) Regulations and orders relating to food and medicines. (6) Regulations, rules, etc. affecting the transport of radioactive materials. (7) Regulations under the social security act 1975. (8) Control of import and export. (9) The Euratom treaty. (10) Important nonstatutory codes of practice, etc.. (11) International conventions, regulations, etc. relating to the peaceful use of atomic energy and radioactive substances, in which the United Kingdom is interested. (12) Foreign legislation. (U.K.)

Delisting efforts for mixed radioactive and chemically hazardous waste at the Oak Ridge Gaseous Diffusion Plant

International Nuclear Information System (INIS)

Goodpasture, S.T.

1987-01-01

Presently, there are four hazardous wastes at the Oak Ridge Gaseous Diffusion Plant that are candidates for the delisting from the Resource Conservation and Recovery Act (RCRA) hazardous waste regulations. These candidates are the sludges from K-1407-B and C ponds, Central Neutralization Facility sludges, mixed sludges from Y-12 and the ash generated by the RCRA/Toxic Substances Control Act (TSCA) Incinerator. All of these hazardous wastes contain radioactive constituents as well as hazardous constituents. The delisting will be based upon the nonradioactive constituents. Whether the delisting petition is granted or not, the wastes will be handled according to the Department of Energy guidelines for radioactive wastes. The presentation discusses the methodologies for delisting these wastes and the rationale behind the processes

Testing and evaluation of alternative process systems for immobilizing radioactive mixed particulate waste in cement

International Nuclear Information System (INIS)

Weingardt, K.M.; Weber, J.R.

1994-03-01

Radioactive and Hazardous Mixed Wastes have accumulated at the Department of Energy (DOE) Hanford Site in south-central Washington State. Ongoing operations and planned facilities at Hanford will also contribute to this waste stream. To meet the Resource Conservation and Recovery Act (RCRA) Land Disposal Restrictions most of this waste will need to be treated to permit disposal. In general this treatment will need to include stabilization/solidification either as a sole method or as part of a treatment train. A planned DOE facility, the Waste Receiving and Processing (WRAP) Module 2A, is scoped to provide this required treatment for containerized contact-handled (CH), mixed low-level waste (MLLW) at Hanford. An engineering development program has been conducted by Westinghouse Hanford Company (WHC) to select the best system for utilizing a cement based process in WRAP Module 2A. Three mixing processes were developed for analysis and testing; in-drum mixing, continuous mixing, and batch mixing. Some full scale tests were conducted and 55 gallon drums of solidified product were produced. These drums were core sampled and examined to evaluate mixing effectiveness. Total solids loading and the order of addition of waste and binder constituents were also varied. The highest confidence approach to meet the WRAP Module 2A waste immobilization system needs appears to be the out-of-drum batch mixing concept. This system is believed to offer the most flexibility and efficiency, given the highly variable and troublesome waste streams feeding the facility

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

International Nuclear Information System (INIS)

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

1986-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1986-01-01

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

Theory of soil decontamination in mixing liquid

International Nuclear Information System (INIS)

Polyakov, A.S.; Emets, E.P.; Poluehktov, P.P.; Rybakov, K.A.

1997-01-01

The theory of soil decontamination from radioactive pollution in mixing liquid flow is described. It is shown that there exists the threshold intensity of liquid mixing up to which there is no decontamination. Beyond the threshold and by increasing the mixing intensity the decontamination of large soil fractions is allowable whereby the higher is the mixing intensity and lower is the soil contamination, the laser is the characteristic decontamination time. The above theory is related to cases of uniform pollution of the particles surface

Buried pipeline leak-detection technique and instruments using radioactive tracers

International Nuclear Information System (INIS)

Zhou Shuxuan; Lu Qingqian; Tang Yonghua

1987-01-01

For detecting and locating leaks on buried pipelines, a leak-detection technique and related instruments have been developed. Some quantity of fluid mixed with a radioactive tracer is injected. After the pipeline is cleaned, a leak-detector is put into and moves along the pipline to monitor the leaked radioactivity and to record both the radioactive signal and the time signal on a magnetic tape. From the signal curves, it can be judged whether there are any leaks on the pipeline and, if any, where they are

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

International Nuclear Information System (INIS)

Vanderberg, L.A.; Foreman, T.M.; Attrep, M. Jr.; Brainard, J.R.; Sauer, N.

1999-01-01

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 biodegradation of volatile organics, enzymatic digestion of cellulosics, and metal ion extraction--was effective in treating a radiologically contaminated heterogeneous paint-stripping waste. Treatment of VOCs using a modified bioreactor avoided radioactive contamination of byproduct biomass and inhibition of biodegradation by toxic metal ions in the waste. Cellulase digestion of bulk cellulose minimized the final solid waste volume by 80%. Moreover, the residue passed TCLP for RCRA metals. Hazardous metals and radioactivity in byproduct sugar solutions were removed using polymer filtration, which employs a combination of water-soluble chelating polymers and ultrafiltration to separate and concentrate metal contaminants. Polymer filtration was used to concentrate RCRA metals and radioactivity into <5% of the original wastewater volume. Permeate solutions had no detectable radioactivity and were below RCRA-allowable discharge limits for Pb and Cr

Issues in radioactive mixed waste compliance with RCRA [Resource Conservation and Recovery Act]: Some examples from ongoing operations at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Eaton, D.L.; Smith, T.H.; Clements, T.L. Jr.; Hodge, V.

1990-01-01

Radioactive mixed waste is subject to regulation under both the Resource Conservation and Recovery Act (RCRA) and the Atomic Energy Act (AEA). The regulation of such waste is the responsibility of the Environmental Protection Agency (EPA) and either the Nuclear Regulatory Commission (NRC) or the Department of Energy (DOE), depending on whether the waste is commercially generated or defense-related. The recent application of the RCRA regulations to ongoing operations at the DOE's Idaho National Engineering Laboratory (INEL) are described in greater detail. 8 refs., 2 figs

Regulatory aspects of mixed waste

International Nuclear Information System (INIS)

Boyle, R.R.; Orlando, D.A.

1990-01-01

Mixed waste is waste that satisfies the definition of low-level radioactive waste in the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) and contains hazardous waste that is either: (1) listed as a hazardous waste in 40 CFR 261, Subpart D; or (2) causes the waste to exhibit any of the characteristics identified in 40 CFR 261, Subpart C. Low-level radioactive waste is defined in the LLRWPAA as radioactive material that is not high level waste, spent nuclear fuel, or byproduct material, as defined in Section 11e(2) of the Atomic Energy Act of 1954, and is classified as low-level waste by the U.S. Nuclear Regulatory Commission (NRC). This paper discusses dual regulatory (NRC and Environmental Protection Agency) responsibility, overview of joint NRC/EPA guidance, workshops, national mixed waste survey, and principal mixed waste uncertainties

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

International Nuclear Information System (INIS)

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

1986-01-01

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

The projected relative index of consequence equivalence of transport of radioactive materials

International Nuclear Information System (INIS)

Nandakumar, A.N.

1999-01-01

The need exists for defining a unit risk factor to enable analysis to make a proper decision when faced with many options relating to the transport of radioactive materials between sites. A method is discussed for deriving such a factor with reference to the collective dose receivable due to the transport of radioactive material incidental to the production of one GWe.a of nuclear power. This quantity would enable the analyst to determine the projected relative index of consequence equivalence (PRICE) for the transport of various types of radioactive materials. (author)

Radioactivity and nuclear energy

International Nuclear Information System (INIS)

Hoffmann, J.; Kuczera, B.

2001-05-01

The terms radioactivity and nuclear energy, which have become words causing irritation in the political sphere, actually represent nothing but a large potential for innovative exploitation of natural resources. The contributions to this publication of the Karlsruhe Research Center examine more closely three major aspects of radioactivity and nuclear energy. The first paper highlights steps in the history of the discovery of radioactivity in the natural environment and presents the state of the art in health physics and research into the effects of exposure of the population to natural or artificial radionuclides. Following contributions focus on: Radiochemical methods applied in the medical sciences (diagnostic methods and devices, therapy). Nuclear energy and electricity generation, and the related safety policies, are an important subject. In this context, the approaches and pathways taken in the field of nuclear science and technology are reported and discussed from the angle of nuclear safety science, and current trends are shown in the elaboration of advanced safety standards relating to nuclear power plant operation and ultimate disposal of radioactive wastes. Finally, beneficial aspects of nuclear energy in the context of a sustainable energy policy are emphasized. In particular, the credentials of nuclear energy in the process of building an energy economy based on a balanced energy mix which combines economic and ecologic advantages are shown. (orig./CB) [de

Method of removing radioactive waste from oil

International Nuclear Information System (INIS)

Belanger, R.L.

1986-01-01

This patent describes a method of removing particulates, radioactive contaminants, and moisture from oil, which consists of: straining out the particulates by passing the oil through a coarse filter screen to a receiving vessel; forming an upper stratum of oil and a lower stratum of sludge, consisting of mud, oil, particulates, and moisture, by heating the upper two-thirds of the receiving vessel; skimming off the stratum of oil from the receiving vessel; transferring the sludge from the receiving vessel to a container; transferring additional separated oil to the receiving vessel; conveying the oil skimmed from the receiving vessel to a mixing vessel; adding an effective amount of Calcium Hypochlorite crystals containing 65% free Chlorine to the mixing vessel to initiate salt formation with the radioactive contaminants; mixing the contents of the mixing vessel for at least ten minutes; transferring the mixture from the mixing vessel to a circulating heater; outputting the mixture from the circulating heater to a second mixing vessel; removing moisture from the oil; and filtering from the oil, the solid radioactive contaminant-salts and residual particulate matter

Adaptation of SW-846 methodology for the organic analysis of radioactive mixed wastes

International Nuclear Information System (INIS)

Griest, W.H.; Schenley, R.L.; Tomkins, B.A.; Caton, J.E. Jr.; Fleming, G.S.; Harmon, S.H.; Wachter, L.J.; Garcia, M.E.; Edwards, M.D.

1990-01-01

Modifications to SW-846 sample preparation methodology permit the organic analysis of radioactive mixed waste with minimum personal radiation exposure and equipment contamination. This paper describes modifications to SW-846 methods 5030 and 3510-3550 for sample preparation in radiation-zoned facilities (hood, glove box, and hot cell) and GC-MS analysis of the decontaminated organic extracts in a conventional laboratory for volatile and semivolatile organics by methods 8240 and 8270 (respectively). Results will be presented from the analysis of nearly 70 nuclear waste storage tank liquids and 17 sludges. Regulatory organics do not account for the organic matter suggested to be present by total organic carbon measurements. 7 refs., 5 tabs

Process for processing and conditioning radioactive effluents of low and medium activity

International Nuclear Information System (INIS)

Taponier, Jean; Pierlas, Rene.

1979-01-01

Preferably continuous process for processing radioactive effluents of low and medium activity, comprising an effluent pre-treatment: precipitation of radioactive compounds to form a stable suspension that can be concentrated. Then a mix is made of 0.6 to 2 parts of cement by weight for one part by weight of suspension, from 0.5 to 5% by weight, in relation to the cement, of asbestos fibre and, if necessary, added water for the cement to set, this suspension containing from 15 to 75% by weight of dry extract and a suspension agent. The homogeneous mix achieved is poured into a container [fr

The IAEA inventory databases related to radioactive material entering the marine environment

International Nuclear Information System (INIS)

Rastogi, R.C.; Sjoeblom, K.L.

1999-01-01

Contracting Parties to the Convention on the Prevention of Marine Pollution by Dumping of Wastes and other Matter (LC 1972) have requested the IAEA to develop an inventory of radioactive material entering the marine environment from all sources. The rationale for developing and maintaining the inventory is related to its use as an information base with which the impact of radionuclides entering the marine environment from different sources can be assessed and compared. Five anthropogenic sources of radionuclides entering the marine environment can be identified. These sources are: radioactive waste disposal at sea; accidents and losses at sea involving radioactive material; discharge of low level liquid effluents from land-based nuclear facilities; the fallout from nuclear weapons testing; and accidental releases from land-based nuclear facilities. The first two of these sources are most closely related to the objective of the LC 1972 and its request to the IAEA. This paper deals with the Agency's work on developing a database on radioactive material entering the marine environment from these two sources. The database has the acronym RAMEM (RAdioactive Material Entering the Marine Environment). It includes two modules: inventory of radioactive waste disposal at sea and inventory of accidents and losses at sea involving radioactive material

Degradation of hazardous chemicals in liquid radioactive wastes from biomedical research using a mixed microbial population

International Nuclear Information System (INIS)

Wolfram, J.H.; Radtke, M.; Wey, J.E.; Rogers, R.D.; Rau, E.H.

1997-10-01

As the costs associated with treatment of mixed wastes by conventional methods increase, new technologies will be investigated as alternatives. This study examines the potential of using a selected mixed population of microorganisms to treat hazardous chemical compounds in liquid low level radioactive wastes from biomedical research procedures. Microorganisms were isolated from various waste samples and enriched against compounds known to occur in the wastes. Individual isolates were tested for their ability to degrade methanol, ethanol, phenol, toluene, phthalates, acetonitrile, chloroform, and trichloroacetic acid. Following these tests, the organisms were combined in a media with a mixture of the different compounds. Three compounds: methanol, acetonitrile, and pseudocumene, were combined at 500 microliter/liter each. Degradation of each compound was shown to occur (75% or greater) under batch conditions with the mixed population. Actual wastes were tested by adding an aliquot to the media, determining the biomass increase, and monitoring the disappearance of the compounds. The compounds in actual waste were degraded, but at different rates than the batch cultures that did not have waste added. The potential of using bioprocessing methods for treating mixed wastes from biomedical research is discussed

Disposal of low-level and mixed low-level radioactive waste during 1990

International Nuclear Information System (INIS)

1993-08-01

Isotopic inventories and other data are presented for low-level radioactive waste (LLW) and mixed LLW disposed (and occasionally stored) during calendar year 1990 at commercial disposal facilities and Department of Energy (DOE) sites. Detailed isotopic information is presented for the three commercial disposal facilities located near Barnwell, SC, Richland, WA, and Beatty, NV. Less information is presented for the Envirocare disposal facility located near Clive, UT, and for LLW stored during 1990 at the West Valley site. DOE disposal information is included for the Savannah River Site (including the saltstone facility), Nevada Test Site, Los Alamos National Laboratory, Idaho National Engineering Laboratory, Hanford Site, Y-12 Site, and Oak Ridge National Laboratory. Summary information is presented about stored DOE LLW. Suggestions are made about improving LLW disposal data

DOE Land Disposal Restrictions Strategy Report for Radioactive Mixed Waste

International Nuclear Information System (INIS)

1989-09-01

This report represents an effort by the Department of Energy (DOE) and its contractors to develop a strategy for achieving radioactive mixed waste (RMW) compliance with the Resource Conservation and Recovery Act (RCRA) Land Disposal Restrictions (LDR). Preliminary information provided by the Operations Offices has been reviewed to formulate an overall strategy that will enable DOE operations to comply with the Land Disposal Restrictions. The effort has concluded that all DOE Operations Offices are impacted by LDR due to the inability to meet existing and future LDR storage prohibition requirements or treatment standards for RMW. A total of 178 RMW streams subject to LDR are identified in this report. Quantities of RMW impacted by LDR have been estimated at approximately 710,785 cubic meters. DOE must place a high priority on resolving LDR compliance issues. Failure to resolve these issues could result in the curtailment of waste generating operations at DOE facilities. Actions will be required from both DOE (Headquarters and Operations Offices) and EPA in order to achieve DOE complex-wide compliance. Specific recommendations are included. 1 fig., 4 tabs

Remediation of sites with mixed contamination of radioactive and other hazardous substances

International Nuclear Information System (INIS)

2006-01-01

The IAEA attaches great importance to the dissemination of information that can assist Member States with the development, implementation, maintenance and continuous improvement of systems, programmes and activities that support the management of the legacies of past practices and accidents. In response to this, the IAEA has initiated a comprehensive programme of work covering all aspects of environmental remediation. Mixed radioactive and hazardous substances contamination poses a particular challenge because of the combination of types of hazards and potential exposures. While radionuclides and toxic (heavy) metals pose similar and mostly compatible challenges, organic contaminants often require different approaches that may not be compatible with the former. Additional complexity is introduced into the problem by a different and sometimes conflicting regulatory framework for radiological and non-radiological contamination, including the prescribed waste management routes. In consideration of the added complexities of remediating (mixed) contamination, the IAEA has determined that this subject sufficiently warrants the development of a specialized report for assisting Member States. Topics discussed are types of sites, hazards and contaminant behaviour; regulatory implications; implications for worker health and safety; implications for sampling and analysis; elements of the remediation process; technology evaluation and selection; monitored non-intervention; blocking of pathways; removal of the source term; ex-situ treatment followed by case studies and a glossary

Selection of innovative technologies for the remediation of soils contaminated with radioactive and mixed wastes

International Nuclear Information System (INIS)

Steude, J.; Tucker, B.

1991-01-01

The remediation of sites containing radioactive and mixed wastes is in a period of rapid growth. The state of the art of remediation is progressing to handle the shortcomings of conventional pump and treat or disposal technologies. The objective of this paper is to review the status of selected innovative technologies which treat soils contaminated with radioactive and mixed waste. Technologies are generally classified as innovative if they are fully developed, but lack sufficient cost or performance data for comparison with conventional technologies. The Environmental Protection Agency recommends inclusion of innovative technologies in the RI/FS screening process if there is reason to believe that they would offer advantages in performance, implementability, cost, etc. This paper serves as a compilation of the pertinent information necessary to gain an overview of the selected innovative technologies to aid in the RI/F'S screening process. The innovative technologies selected for evaluation are listed below. Bioremediation, although innovative, was not included due to the combination of the vast amount of literature on this subject and the limited scope of this project. 1. Soil washing and flushing; 2. Low temperature thermal treatment; 3. Electrokinetics; 4. Infrared incineration; 5. Ultrasound; 6. In situ vitrification; 7. Soil vapor extraction; 8. Plasma torch slagging; 9. In situ hot air/steam extraction; 10. Cyclone reactor treatment; 11. In situ radio frequency; 12. Vegetative radionuclide uptake; and 13. In situ soil heating. The information provided on each technology includes a technical description, status, summary of results including types of contaminants and soils treated, technical effectiveness, feasibility and estimated cost

An approach to regulatory compliance with radioactive mixed waste regulations

International Nuclear Information System (INIS)

Baker, G.G.; Mihalovich, G.S.; Provencher, R.B.

1991-01-01

On May 7, 1990, radioactive mixed waste (RMW) at the West Valley Demonstration Project (WVDP) became subject to the State Of New York hazardous waste regulations. The facility was required to be in full compliance by June 6, 1990. Achievement of this goal was difficult because of the short implementation time frame. Compliance with the hazardous waste regulations also presented some potential conflicts between the hazardous waste requirements and other regulatory requirements specifically applicable to nuclear facilities. The potential conflicts involved construction, operation, and control measures. However, the facility had been working extensively with EPA Region 2 and the New York State Department of Environmental Conservation (NYSDEC) on the application of the hazardous waste regulations to the facility. During these preliminary contacts, WVDP identified three issues that related to the potential conflicts: 1. Equivalency of Design and Equipment, 2. Land Disposal Restrictions (LDR), and 3. The Principle of As Low As Reasonable Achievable (ALARA) Radiation Exposure. The equivalency of nuclear facility design and equipment to the hazardous waste requirements is based in part on the increased construction criteria for nuclear facilities, the use of remote radiological monitoring for leak detection, and testing of system components that are not accessible to personnel due to high levels of radiation. This paper discusses in detail: 1. The implementation and results of the WVDP's interaction with its regulators, 2. How the regulators were helped to understand the different situations and conditions of nuclear and chemical facilities, and 3. How, by working together, the result was not only mutually advantageous to the NWDP and the agencies, but it also assured that the health and safety of workers, the public, and the environment were protected

USE OF RECYCLED POLYMERS FOR ENCAPSULATION OF RADIOACTIVE, HAZARDOUS AND MIXED WASTES

International Nuclear Information System (INIS)

LAGERRAAEN, P.R.; KALB, P.D.

1997-01-01

Polyethylene encapsulation is a waste treatment technology developed at Brookhaven National Laboratory using thermoplastic polymers to safely and effectively solidify hazardous, radioactive and mixed wastes for disposal. Over 13 years of development and demonstration with surrogate wastes as well as actual waste streams on both bench and full scale have shown this to be a viable and robust technology with wide application. Process development efforts have previously focused on the use of virgin polymer feedstocks. In order to potentially improve process economics and serve to lessen the municipal waste burden, recycled polymers were investigated for use as encapsulating agents. Recycled plastics included low-density polyethylene, linear low-density polyethylene, high-density polyethylene and polypropylene, and were used as a direct substitute for or blended together with virgin resin. Impacts on processing and final waste form performance were examined

Method for processing powdery radioactive wastes

International Nuclear Information System (INIS)

Yasumura, Keijiro; Matsuura, Hiroyuki; Tomita, Toshihide; Nakayama, Yasuyuki.

1978-01-01

Purpose: To solidify radioactive wastes with ease and safety at a high reaction speed but with no boiling by impregnating the radioactive wastes with chlorostyrene. Method: Beads-like dried ion exchange resin, powdery ion exchange resin, filter sludges, concentrated dried waste liquor or the like are mixed or impregnated with a chlorostyrene monomer dissolving therein a polymerization initiator such as methyl ethyl ketone peroxide and benzoyl peroxide. Mixed or impregnated products are polymerized to solid after a predetermined of time through curing reaction to produce solidified radioactive wastes. Since inflammable materials are used, this process has a high safety. About 70% wastes can be incorporated. The solidified products have a strength as high as 300 - 400 kg/cm 3 and are suitable to ocean disposal. The products have a greater radioactive resistance than other plastic solidification products. (Seki, T.)

An overview of radioactive waste management in the United States of America

International Nuclear Information System (INIS)

Luik, A.E. van

1991-01-01

The U.S. radioactive waste management program is implemented by the U.S. Department of Energy (U.S. DOE) for high-level radioactive wastes and spent nuclear fuel; defense-related transuranic wastes; and U.S. DOE-generated low-level and mixed wastes. The various states are responsible for the disposal of civilian low-level wastes. Selected radioactive waste management and disposal topics will be overviewed, followed by a more detailed discussion of the high-level and low-level waste disposal regulatory framework and some issues involved in showing compliance with the applicable regulations. (author)

Sulfur polymer cement, a new stabilization agent for mixed and low- level radioactive waste

International Nuclear Information System (INIS)

Darnell, G.R.

1991-01-01

Solidification and stabilization agents for radioactive, hazardous, and mixed wastes are failing to pass governmental tests at alarming rates. The Department of Energy's National Low-Level Waste Management Program funded testing of Sulfur Polymer Cement (SPC) by Brookhaven National Laboratory during the 1980s. Those tests and tests by the US Bureau of Mines (the original developer of SPC), universities, states, and the concrete industry have shown SPC to be superior to hydraulic cements in most cases. Superior in what wastes can be successfully combined and in the quantity of waste that can be combined and still pass the tests established by the US Environmental Protection Agency and the US Nuclear Regulatory Commission

What a public-relations-model regarding radioactive waste implicates

Energy Technology Data Exchange (ETDEWEB)

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

1996-12-31

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.

Significance of chemotoxic admixtures in radioactive wastes

International Nuclear Information System (INIS)

Merz, E.R.

1989-01-01

The double hazard potential of mixed wastes is characterized by several criteria: radioactivity on the one hand, and chemical toxicity, in flammability, corrosiveness as well as chemical reactivity on the other. The author argues that mixed wastes assigned for ultimate disposal should therefore be thoroughly detoxified, inertized, or mineralized, prior to conditioning and packaging. Strategies and techniques are presented which ensure the elimination of hazardous organic chemicals and minimizing waste volumes to be disposed of. Advantage can be taken of mixing mineralized filter dusts, arising in the combustion of hazardous chemical wastes with low-activity inertized radioactive wastes as a solidifying reagent. Simultaneous geological disposal of such mixed waste is feasible without any drawbacks

Proceedings of the workshop on radioactive, hazardous, and/or mixed waste sludge management

International Nuclear Information System (INIS)

Lomenick, T.F.

1992-01-01

A workshop sponsored by the US Department of Energy (DOE) Field Office, Oak Ridge, was held on December 4--6, 1990, in Knoxville, Tennessee. The primary objective of the workshop was the exchange of information, experiences, solutions, and future plans of DOE and its prime contractors who are engaged in work on the packaging, grouting, storage, and transport of waste sludges. In addition, the group met with industrial participants in an open forum to discuss problems and needs in the management of these wastes and to learn of possible industrial experiences, approaches, and solutions, including demonstrations of potential tools and techniques. Topics discussed include the following: mixed waste sludge issue at the K-25 site; processing saltstone from waste streams at the Savannah River Plant; the Hanford Grout Treatment Facility; treatment of pond sludge at the Rocky Flats Plant; cement solidification of low-level radioactive sludge at the West Valley Demonstration Project; studies on the solidification of low-level radioactive wastes in cement at INEL; cement solidification systems at Los Alamos National Laboratory; emergency avoidance solidification campaign at ORNL; diffusion plant sludge storage problems at the Portsmouth Gaseous Diffusion Plant; the proposed fixation of sludge in cement at the feed materials production center; regulatory aspects of sludge management; and delisting efforts for K-1407-C pond sludges. Individual projects are processed separately for the data bases

A process for treating radioactive water-reactive wastes

International Nuclear Information System (INIS)

Dziewinski, J.; Lussiez, G.; Munger, D.

1995-01-01

Los Alamos National Laboratory and other locations in the complex of experimental and production facilities operated by the United States Department of Energy (DOE) have generated an appreciable quantity of hazardous and radioactive wastes. The Resource Conservation and Recovery Act (RCRA) enacted by the United States Congress in 1976 and subsequently amended in 1984, 1986, and 1988 requires that every hazardous waste must be rendered nonhazardous before disposal. Many of the wastes generated by the DOE complex are both hazardous and radioactive. These wastes, called mixed wastes, require applying appropriate regulations for radioactive waste disposal and the regulations under RCRA. Mixed wastes must be treated to remove the hazardous waste component before they are disposed as radioactive waste. This paper discusses the development of a treatment process for mixed wastes that exhibit the reactive hazardous characteristic. Specifically, these wastes react readily and violently with water. Wastes such as lithium hydride (LiH), sodium metal, and potassium metal are the primary wastes in this category

Mixed waste: The treatment of organic radioactive waste by means of adsorbents

International Nuclear Information System (INIS)

Sanhueza-Mir, A.; Morales-Galarce, T.

2001-01-01

Full text: The work described in this paper has been carried in the radioactive waste treatment facilities of the Nuclear Research Center Lo Aguirre, CEN LA, which are operated by Radioactive Waste Management Unit, UGDR. This last, centralizes its activities in order to manage all radioactive waste generated in the country due to the nuclear development. Features of danger and risks presented by organic radioactive liquid waste, make the need to develop a practicable alternative for its treatment and to allow the conditioning towards a suitable final disposal The raw material for this work, is an organic liquid waste arising from scintillation techniques, contaminated with Tritium. This mixed waste has to be treated and then conditioned in a solid form within a 200 I container, according with actual acceptance criteria for our temporary store for radioactive waste. The best formulation which allows to immobilize the liquid waste was determined. The first step consists in the adsorption treatment that waste is humbled. From the available adsorbents, two types were studied: adsorption granulat and diatomaceous earth. From the waste management standpoint, results with diatomaceous earth present physical characteristics better than the other Following, the second stage is the immobilization, which is achieved in a cement matrix made with puzzolanic cement (Polpaico 400) made in Chile. Later, due to cost and availability in the country, the diatomaceous earth is selected for the study, in the form of celite which is comparatively economic. The best mixture, with regard to physical feature, has the following composition: a 0.35 (w/w) water/cement ratio, which represents the needed quantity to obtain workability in the mixture, and it is the minimum amount of water to hydrating the cement; a waste/adsorbent ratio of 0.5 (v/v), in which the organic liquid is completely adsorbed and it is incorporated into the crystalline system of the solid form; and an adsorbed waste

Contamination of fodder and radioactivity in turkeys

International Nuclear Information System (INIS)

Kossakowski, S.; Olszewska, K.

1985-01-01

Radioactivity was determined in mixed fodder (IB, IC, IE) and in turkeys which were given that feeding stuff. In animals (25 males and 25 females) fed with the above mixed fodder for 16-24 weeks radioactivity was assessed in internal organs and in their tissues. It was found that radioactivity ranged from 322.2 Bq/kg to 190.6 Bq/kg. In males the highest contamination was found in the spleen (average 0.108 Bq/g), in skeletal muscles (0.082 Bq/g), and in the liver (0.080 Bq/g), and the lowest in the skin (0.046 Bq per 1 g). The findings indicate that radioactivity of carcasses and internal organs in turkeys fed with contamined fodder was much lower than that in fodder. 6 refs., 1 tab. (author)

Application of EPA regulations to low-level radioactive waste

International Nuclear Information System (INIS)

Bowerman, B.S.; Piciulo, P.L.

1985-01-01

The survey reported here was conducted with the intent of identifying categories of low-level radioactive wastes which would be classified under EPA regulations 40 CFR Part 261 as hazardous due to the chemical properties of the waste. Three waste types are identified under these criteria as potential radioactive mixed wastes: wastes containing organic liquids; wastes containing lead metal; and wastes containing chromium. The survey also indicated that certain wastes, specific to particular generators, may also be radioactive mixed wastes. Ultimately, the responsibility for determining whether a facility's wastes are mixed wastes rest with the generator. However, the uncertainties as to which regulations are applicable, and the fact that no legal definition of mixed wastes exists, make such a determination difficult. In addition to identifying mixed wastes, appropriate methods for the management of mixed wastes must be defined. In an ongoing study, BNL is evaluating options for the management of mixed wastes. These options will include segregation, substitution, and treatments to reduce or eliminate chemical hazards associated with the wastes listed above. The impacts of the EPA regulations governing hazardous wastes on radioactive mixed waste cannot be assessed in detail until the applicability of these regulations is agreed upon. This issue is still being discussed by EPA and NRC and should be resolved in the near future. Areas of waste management which may affect generators of mixed wastes include: monitoring/tracking of wastes before shipment; chemical testing of wastes; permits for treatment of storage of wastes; and additional packaging requirements. 3 refs., 1 fig., 2 tabs

Radioactive waste management: the relation between geological disposal and advanced nuclear technologies

International Nuclear Information System (INIS)

Schroder, Jantine

2013-01-01

Throughout this paper we aim to scope the most pregnant themes, issues and research questions concerning the relation between geological disposal and advanced nuclear technologies in the broad context of radioactive waste management. Especially from a socio-technical point of view the mutual impacts, divergences and complementarities between both strategies seem to have received limited dedicated examination up until today. Specific attention is paid to the main arguments that seem to underpin both research streams, related to how the issue of radioactive waste is contextualized and which problems and solutions are consequently identified and proposed. Ultimately we aim to encourage scientifically integer communication and constructive dialogue between both fields, to investigate the common possibilities of enhancing radioactive waste management as a whole. (authors)

Abstract of the law relating to the nuclear industry and radioactive substances

International Nuclear Information System (INIS)

Anon.

1980-01-01

This summary of the law relating to Atomic Energy and Radioactive substances as at March 1980 is divided into sections headed: (1) The common law. (2) Legislation. (3) Regulations under the Factories Act 1961. (4) Regulations, rules etc. affecting the transport of radioactive materials. (5) The Euratom treaty. (U.K.)

Managing a mixed waste program

International Nuclear Information System (INIS)

Koch, J.D.

1994-01-01

IT Corporation operates an analytical laboratory in St. Louis capable of analyzing environmental samples that are contaminated with both chemical and radioactive materials. Wastes generated during these analyses are hazardous in nature; some are listed wastes others exhibit characteristic hazards. When the original samples contain significant quantities of radioactive material, the waste must be treated as a mixed waste. A plan was written to document the waste management program describing the management of hazardous, radioactive and mixed wastes. This presentation summarizes the methods employed by the St. Louis facility to reduce personnel exposures to the hazardous materials, minimize the volume of mixed waste and treat the materials prior to disposal. The procedures that are used and the effectiveness of each procedure will also be discussed. Some of the lessons that have been learned while dealing with mixed wastes will be presented as well as the solutions that were applied. This program has been effective in reducing the volume of mixed waste that is generated. The management program also serves as a method to manage the costs of the waste disposal program by effectively segregating the different wastes that are generated

Pump Jet Mixing and Pipeline Transfer Assessment for High-Activity Radioactive Wastes in Hanford Tank 241-AZ-102

Energy Technology Data Exchange (ETDEWEB)

Y Onishi; KP Recknagle; BE Wells

2000-08-09

The authors evaluated how well two 300-hp mixer pumps would mix solid and liquid radioactive wastes stored in Hanford double-shell Tank 241-AZ-102 (AZ-102) and confirmed the adequacy of a three-inch (7.6-cm) pipeline system to transfer the resulting mixed waste slurry to the AP Tank Farm and a planned waste treatment (vitrification) plant on the Hanford Site. Tank AZ-102 contains 854,000 gallons (3,230 m{sup 3}) of supernatant liquid and 95,000 gallons (360 m{sup 3}) of sludge made up of aging waste (or neutralized current acid waste). The study comprises three assessments: waste chemistry, pump jet mixing, and pipeline transfer. The waste chemical modeling assessment indicates that the sludge, consisting of the solids and interstitial solution, and the supernatant liquid are basically in an equilibrium condition. Thus, pump jet mixing would not cause much solids precipitation and dissolution, only 1.5% or less of the total AZ-102 sludge. The pump jet mixing modeling indicates that two 300-hp mixer pumps would mobilize up to about 23 ft (7.0 m) of the sludge nearest the pump but would not erode the waste within seven inches (0.18 m) of the tank bottom. This results in about half of the sludge being uniformly mixed in the tank and the other half being unmixed (not eroded) at the tank bottom.

Pump Jet Mixing and Pipeline Transfer Assessment for High-Activity Radioactive Wastes in Hanford Tank 241-AZ-102

International Nuclear Information System (INIS)

Onishi, Y.; Recknagle, K.P.; Wells, B.E.

2000-01-01

The authors evaluated how well two 300-hp mixer pumps would mix solid and liquid radioactive wastes stored in Hanford double-shell Tank 241-AZ-102 (AZ-102) and confirmed the adequacy of a three-inch (7.6-cm) pipeline system to transfer the resulting mixed waste slurry to the AP Tank Farm and a planned waste treatment (vitrification) plant on the Hanford Site. Tank AZ-102 contains 854,000 gallons (3,230 m 3 ) of supernatant liquid and 95,000 gallons (360 m 3 ) of sludge made up of aging waste (or neutralized current acid waste). The study comprises three assessments: waste chemistry, pump jet mixing, and pipeline transfer. The waste chemical modeling assessment indicates that the sludge, consisting of the solids and interstitial solution, and the supernatant liquid are basically in an equilibrium condition. Thus, pump jet mixing would not cause much solids precipitation and dissolution, only 1.5% or less of the total AZ-102 sludge. The pump jet mixing modeling indicates that two 300-hp mixer pumps would mobilize up to about 23 ft (7.0 m) of the sludge nearest the pump but would not erode the waste within seven inches (0.18 m) of the tank bottom. This results in about half of the sludge being uniformly mixed in the tank and the other half being unmixed (not eroded) at the tank bottom

Method of solidifying radioactive wastes with plastics

International Nuclear Information System (INIS)

Matsuura, Hiroyuki; Yasumura, Keijiro; Minami, Yuji; Tomita, Toshihide

1980-01-01

Purpose: To prevent solidification of solidifying agents in the mixer by conducting the mixing process for the solidifying agents and the radioactive wastes at a temperature below the initiation point for the solidification of the agents thereby separating the mixing process from the solidification-integration process. Method: Catalyst such as cobalt naphthenate is charged into an unsaturated polyester resin in a mixer previously cooled, for example, to -10 0 C. They are well mixed with radioactive wastes and the mixture in the mixer is charged in a radioactive waste storage container. The temperature of the mixture, although kept at a low temperature initially, gradually increases to an ambient temperature whereby curing reaction is promoted and the reaction is completed about one day after to provide firm plastic solidification products. This can prevent the solidification of the solidifying agents in the mixer to thereby improve the circumstance's safety. (Kawakami, Y.)

Method of encapsulating waste radioactive material

International Nuclear Information System (INIS)

Forrester, J.A.; Rootham, M.W.

1982-01-01

When encapsulating radioactive waste including radioactive liquid having a retardant therein which retards the setting of cements by preventing hydration at cement particles in the mix, the liquid is mixed with ordinary Portland cement and subjected, in a high shear mixer, to long term shear far in excess of that needed to form ordinary grout. The controlled utilization of the retardants plus shear produces a thixotropic paste with extreme moldability which will not bleed, and finally sets more rapidly than can be expected with normal cement mixtures forming a very strong product. (author)

Chemical decontamination method for radioactive metal waste

International Nuclear Information System (INIS)

Onuma, Tsutomu; Akimoto, Hidetoshi

1991-01-01

The invention relates to a decontamination method for radioactive metal waste products derived from equipment that handles radioactive materials whose surfaces have been contaminated; in particular it concerns a decontamination method that reduces the amount of radioactive waste by decontaminating radioactive waste substances to a level of radioactivity in line with normal waste products. In order to apply chemical decontamination to metal waste products whose surfaces are divided into carbon steel waste and stainless steel waste; the carbon steel waste is treated using only a primary process in which the waste is immersed in a sulfuric acid solution, while the stainless steel waste must be treated with both the primary process and then electrolytically reduces it for a specific length of time and a secondary process that uses a solution of sulfuric acid mixed with oxidizing metal salts. The method used to categorize metal waste into carbon steel waste and stainless steel waste involves determining the presence, or absence, of magnetism. Voltage is applied for a fixed duration; once that has stopped, electrolytic reduction repeats the operative cycle of applying, then stopping voltage until the potential of the radioactive metal waste is retained in the active region. 1 fig. 2 tabs

Molten salt oxidation of mixed wastes: Separation of radioactive materials and Resource Conservation and Recovery Act (RCRA) materials

International Nuclear Information System (INIS)

Bell, J.T.; Haas, P.A.; Rudolph, J.C.

1995-01-01

The Oak Ridge National Laboratory (ORNL) is participating in a program to apply a molten salt oxidation (MSO) process to treatment of mixed (radioactive and RCRA) wastes. The salt residues from the MSO treatment will require further separations or other processing to prepare them for final disposal. A bench-scale MSO apparatus is being installed at ORNL and will be operated on real Oak Ridge wastes. The treatment concepts to be tested and demonstrated on the salt residues from real wastes are described

Feed Basis for Processing Relatively Low Radioactivity Waste Tanks

International Nuclear Information System (INIS)

Pike, J.A.

2002-01-01

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

MIxed Waste Integrated Program (MWIP): Technology summary

International Nuclear Information System (INIS)

1994-02-01

The mission of the Mixed Waste Integrated Program (MWIP) is to develop and demonstrate innovative and emerging technologies for the treatment and management of DOE's mixed low-level wastes (MLLW) for use by its customers, the Office of Waste Operations (EM-30) and the Office of Environmental Restoration (EM-40). The primary goal of MWIP is to develop and demonstrate the treatment and disposal of actual mixed waste (MMLW and MTRU). The vitrification process and the plasma hearth process are scheduled for demonstration on actual radioactive waste in FY95 and FY96, respectively. This will be accomplished by sequential studies of lab-scale non-radioactive testing followed by bench-scale radioactive testing, followed by field-scale radioactive testing. Both processes create a highly durable final waste form that passes leachability requirements while destroying organics. Material handling technology, and off-gas requirements and capabilities for the plasma hearth process and the vitrification process will be established in parallel

Recycling of radioactive oil sludge waste into pavement brick

International Nuclear Information System (INIS)

Meor Yusoff Meor Sulaiman; Hishamuddin Hussein; Choo Thye Foo; Nurul Wahida Ahmad Khairuddin; MAsliana MUslimin; Wilfred Sylvester Paulus

2010-01-01

Malaysia produces about 1450 tons of radioactive oil sludge waste per year and there is an urgent need to find a permanent solution to the storage and disposal of this radioactive waste problem. Several treatment methods such bacteria farming, ultracentrifuge, steam reforming and incineration are currently being used but the core issue of the radioactive material in the oil sludge had not been solved. The paper relates a study on utilizing the radioactive component of the oil sludge and turning them into pavement brick. Characteristic study of this radioactive component by XRD and XRF show that it mainly comprised of quartz and anorthite minerals. While the radioactivity analysis by gamma technique shows that more than 90 % of this radioactivity comes from this soil component with Ra-226 and Ra-228 as the main radionuclides. A vitrified brick was then produced from this sediment by mixing it with low radioactive local red clay. The result also shows that the formation of the vitrified layer may be due high content of K in the red clay. Tensile test on the brick shows that it has more than four times the strength of commercial clay brick. Long duration leaching test on the brick also shows that there is no dissolution of radionuclide from the brick. (author)

Melting method for radioactive solid wastes and device therefor

Energy Technology Data Exchange (ETDEWEB)

Komatsu, Masahiko; Abe, Takashi; Nakayama, Junpei; Kusamichi, Tatsuhiko; Sakamoto, Koichi

1998-11-17

Upon melting radioactive solid wastes mixed with radioactive metal wastes and non metal materials such as concrete by cold crucible high frequency induction heating, induction coils are wound around the outer circumference of a copper crucible having a water cooling structure to which radioactive solid wastes are charged. A heating sleeve formed by a material which generates heat by an induction heating function of graphite is disposed to the inside of the crucible at a height not in contact with molten metals in the crucible vertically movably. Radioactive solid wastes are melted collectively by the induction heat of the induction coils and thermal radiation and heat conduction of the heating sleeve heated by the induction heat. With such procedures, non metal materials such as concrete and radioactive metal wastes in a mixed state can be melt collectively continuously highly economically. (T.M.)

Mixed Low-Level Radioactive Waste (MLLW) Primer

International Nuclear Information System (INIS)

Schwinkendorf, W.E.

1999-01-01

This document presents a general overview of mixed low-level waste, including the regulatory definitions and drivers, the manner in which the various kinds of mixed waste are regulated, and a discussion of the waste treatment options

Mixed Low-Level Radioactive Waste (MLLW) Primer

Energy Technology Data Exchange (ETDEWEB)

W. E. Schwinkendorf

1999-04-01

This document presents a general overview of mixed low-level waste, including the regulatory definitions and drivers, the manner in which the various kinds of mixed waste are regulated, and a discussion of the waste treatment options.

Development of the Remedial Action Priority System: an improved risk assessment tool for prioritizing hazardous and radioactive-mixed waste disposal sites

International Nuclear Information System (INIS)

Whelan, G.; Strenge, D.L.; Steelman, B.L.; Hawley, K.A.

1985-08-01

The Remedial Action Priority System (RAPS) represents a methodology that prioritizes inactive hazardous and radioactive mixed-waste disposal sites in a scientific and objective manner based on limited site information. This methodology is intended to bridge the technology gap that exists between the initial site evaluation using the Hazard Ranking System (HRS) and the time-consuming process of actual field site characterization, assessment, and remediation efforts. The HRS was designed as an initial screening tool to discriminate between hazardous waste sites that do not and those that are likely to pose significant problems to human health, safety, and/or the environment. The HRS is used by the US Environmental Protection Agency to identify sites for nomination to the National Priorites List (NPL). Because the HRS is not designed to evaluate sites containing radionuclides, a modified Hazard Ranking System (mHRS) addressing both hazardous and radioactive mixed wastes was developed by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). Neither the HRS nor the mHRS was designed to prioritize sites that are nominated to the NPL according to their potential risks. 15 refs., 6 figs., 3 tabs

Conversion of three mixed-waste streams

International Nuclear Information System (INIS)

Harmer, D.E.; Porter, D.L.; Conley, C.W.

1990-01-01

At the present time, commercial mixed waste (containing both radioactive and hazardous components) is not handled by any disposal site in this country. Thus, a generator of such material is faced with the prospect of separating or altering the nature of the waste components. A chemical or physical separation may be possible. However, if separation fails there remains the opportunity of chemically transforming the hazardous ingredients to non-hazardous substances, allowing disposal at an existing radioactive burial site. Finally, chemical or physical stabilization can be used as a tool to achieve an acceptable waste form lacking the characteristics of mixed waste. A practical application of these principles has been made in the case of certain mixed waste streams at Aerojet Ordnance Tennessee. Three different streams were involved: (1) lead and lead oxide contaminated with uranium, (2) mixed chloride salts including barium chloride, contaminated with uranium, and (3) bricks impregnated with the barium salt mixture. This paper summarizes the approach of this mixed-waste problem, the laboratory solutions found, and the intended field remediations to be followed. Mixture (1), above, was successfully converted to a vitreous insoluble form. Mixture (2) was separated into radioactive and non-radioactive streams, and the hazardous characteristics of the latter altered chemically. Mixture (3) was treated to an extraction process, after which the extractant could be treated by the methods of Mixture (2). Field application of these methods is scheduled in the near future

Expediting the commercial disposal option: Low-level radioactive waste shipments from the Mound Plant

Energy Technology Data Exchange (ETDEWEB)

Rice, S.; Rothman, R.

1995-12-31

In April, Envirocare of Utah, Inc., successfully commenced operation of its mixed waste treatment operation. A mixed waste which was (a) radioactive, (b) listed as a hazardous waste under the Resource Conservation and Recovery Act (RCRA), and (c) prohibited from land disposal was treated using Envirocare`s full-scale Mixed Waste Treatment Facility. The treatment system involved application of chemical fixation/stabilization technologies to reduce the leachability of the waste to meet applicable concentration-based RCRA treatment standards. In 1988, Envirocare became the first licensed facility for the disposal of naturally occurring radioactive material. In 1990, Envirocare received a RCRA Part B permit for commercial mixed waste storage and disposal. In 1994, Envirocare was awarded a contract for the disposal of DOE mixed wastes. Envirocare`s RCRA Part B permit allows for the receipt, storage, treatment, and disposal of mixed wastes that do not meet the land-disposal treatment standards of 40 CFR (Code of Federal Regulations) 268. Envirocare has successfully received, managed, and disposed of naturally occurring radioactive material, low-activity radioactive waste, and mixed waste from government and private generators.

Soil treatment to remove uranium and related mixed radioactive contaminants. Final report September 1992--October 1995

International Nuclear Information System (INIS)

1996-07-01

A research and development project to remove uranium and related radioactive contaminants from soil by an ultrasonically-aided chemical leaching process began in 1993. The project objective was to develop and design, on the basis of bench-scale and pilot-scale experimental studies, a cost-effective soil decontamination process to produce a treated soil containing less than 35 pCi/g. The project, to cover a period of about thirty months, was designed to include bench-scale and pilot-scale studies to remove primarily uranium from the Incinerator Area soil, at Fernald, Ohio, as well as strontium-90, cobalt-60 and cesium-137 from a Chalk River soil, at the Chalk River Laboratories, Ontario. The project goal was to develop, design and cost estimate, on the basis of bench-scale and pilot-scale ex-situ soil treatment studies, a process to remove radionuclides form the soils to a residual level of 35 pCi/g of soil or less, and to provide a dischargeable water effluent as a result of soil leaching and a concentrate that can be recovered for reuse or solidified as a waste for disposal. In addition, a supplementary goal was to test the effectiveness of in-situ soil treatment through a field study using the Chalk River soil

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

International Nuclear Information System (INIS)

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

1985-12-01

Regulations governing the management and disposal of hazardous wastes have been promulgated by the US Environmental Protection Agency under authority of the Resource Conservation and Recovery Act. These were reviewed and compared with the available information on the properties and characteristics of low-level radioactive wastes (LLW). In addition, a survey was carried out to establish a data base on the nature and composition of LLW in order to determine whether some LLW streams could also be considered hazardous as defined in 40 CFR Part 261. For the survey, an attempt was made to obtain data on the greatest volume of LLW; hence, as many large LLW generators as possible were contacted. The list of 238 generators contacted was based on information obtained from NRC and other sources. The data base was compiled from completed questionnaires which were returned by 97 reactor and non-reactor facilities. The waste volumes reported by these respondents corresponded to approximately 29% of all LLW disposed of in 1984. The analysis of the survey results indicated that three broad categories of LLW may be radioactive mixed wastes. They include: waste containing organic liquids, disposed of by all types of generators; wastes containing lead metal, i.e., discarded shielding or lead containers; wastes containing chromates, i.e., nuclear power plant process wastes where chromates are used as corrosion inhibitors. Certain wastes, specific to particular generators, were identified as potential mixed wastes as well. 8 figs., 48 tabs

Two stage, low temperature, catalyzed fluidized bed incineration with in situ neutralization for radioactive mixed wastes

International Nuclear Information System (INIS)

Wade, J.F.; Williams, P.M.

1995-01-01

A two stage, low temperature, catalyzed fluidized bed incineration process is proving successful at incinerating hazardous wastes containing nuclear material. The process operates at 550 degrees C and 650 degrees C in its two stages. Acid gas neutralization takes place in situ using sodium carbonate as a sorbent in the first stage bed. The feed material to the incinerator is hazardous waste-as defined by the Resource Conservation and Recovery Act-mixed with radioactive materials. The radioactive materials are plutonium, uranium, and americium that are byproducts of nuclear weapons production. Despite its low temperature operation, this system successfully destroyed poly-chlorinated biphenyls at a 99.99992% destruction and removal efficiency. Radionuclides and volatile heavy metals leave the fluidized beds and enter the air pollution control system in minimal amounts. Recently collected modeling and experimental data show the process minimizes dioxin and furan production. The report also discusses air pollution, ash solidification, and other data collected from pilot- and demonstration-scale testing. The testing took place at Rocky Flats Environmental Technology Site, a US Department of Energy facility, in the 1970s, 1980s, and 1990s

Solidifying processing device for radioactive waste

International Nuclear Information System (INIS)

Sueto, Kumiko; Toyohara, Naomi; Tomita, Toshihide; Sato, Tatsuaki

1990-01-01

The present invention concerns a solidifying device for radioactive wastes. Solidifying materials and mixing water are mixed by a mixer and then charged as solidifying and filling materials to a wastes processing container containing wastes. Then, cleaning water is sent from a cleaning water hopper to a mixer to remove the solidifying and filling materials deposited in the mixer. The cleaning liquid wastes are sent to a separator to separate aggregate components from cleaning water components. Then, the cleaning water components are sent to the cleaning water hopper and then mixed with dispersing materials and water, to be used again as the mixing water upon next solidifying operation. On the other hand, the aggregate components are sent to a processing mechanism as radioactive wastes. With such procedures, since the discharged wastes are only composed of the aggregates components, and the amount of the wastes are reduced, facilities and labors for the processing of cleaning liquid wastes can be decreased. (I.N.)

In situ stabilization of mixed radioactive waste storage tanks and contaminated soil areas

International Nuclear Information System (INIS)

Matthern, G.E.; Meservey, R.H.

1997-01-01

Within the Department of Energy (DOE) Complex, there are a number of small (<50,000 gallons) underground Storage tanks containing mixed waste materials. The radioactive content of wastes eliminates the feasibility for hazardous waste treatment in accordance with previously prescribed Resource Conservation and Recovery Act (RCRA) technologies. As a result, DOE is funding in situ stabilization technology development for these tanks, Some of this development work has been done at the Idaho National Engineering and Environmental Laboratory (INEEL) and the initial efforts there were concentrated on the stabilization of the contents of the Test Area North (TAN) V-9 Tank. This is a 400 gallon underground tank filled with about 320 gallons of liquids and silty sediments. Sampling data indicates that approximately 50 wt% of the tank contents is aqueous-phase liquids. The vertically oriented cylindrical tank has a conical bottom and a chordal baffle that separates the tank inlet from its outlet. Access to the tank is through a six inch diameter access pipe on top of the tank. Because of the high volume, and the high concentration of aqueous-phase materials, Tank V-9 stabilization efforts have focussed on applying in situ agitation with dry feed addition to stabilize its contents. Materials selected for dry feed addition to this tank include a mixture of Aquaset IIH, and Type I/II Portland cement. This paper describes the results of proof-of-concept tests performed on full scale mockups of the Tank V-9. This proof-of-concept test were used to set operating parameters for in situ mixing, as well as evaluate how variations in Aquaset IIH/Portland cement ratio and sediment to liquid volume affected mixing of the tank

Hybrid Microwave Treatment of SRS TRU and Mixed Wastes

International Nuclear Information System (INIS)

Wicks, G.G.

1999-01-01

A new process, using hybrid microwave energy, has been developed as part of the Strategic Research and Development program and successfully applied to treatment of a wide variety of non-radioactive materials, representative of SRS transuranic (TRU) and mixed wastes. Over 35 simulated (non-radioactive) TRU and mixed waste materials were processed individually, as well as in mixed batches, using hybrid microwave energy, a new technology now being patented by Westinghouse Savannah River Company (WSRC)

Summary of the law relating to atomic energy and radioactive substances

International Nuclear Information System (INIS)

Sim, D.F.; Ritchie, K.J.S.

1983-04-01

Intended as a signpost to the relevant law no aspect is covered in detail but a full summary is given. For further details reference has to be made to Acts or regulations themselves. The summary covers the Common Law, the laws in force, regulations under the Factories Act 1961, regulations and orders relating to food and medicines, those concerned with the transport of radioactive materials, regulations under the Social Security Act 1975, Control of Import and Export, the Euratom treaty, important non-statutory codes of practice etc., international conventions, regulations etc. relating to the peaceful use of atomic energy and radioactive substances in which the UK is interested and finally, foreign legislation. The details have been revised as at 31 March 1983. (U.K.)

Method of solidifying and disposing radioactive waste plastic

International Nuclear Information System (INIS)

Matsuura, Hiroyuki; Yasumura, Keijiro

1981-01-01

Purpose: To solidify radioactive waste as it is with plastic by forming a W/O (Water-in-Oil) emulsion with the radioactive waste and a plastic solidifier, and treating it with a polymerization starting agent, an accelerator, and the like. Method: A predetermined amount of alkaline substance such as sodium hydroxide, triethanol, or the like is added quantitatively to radioactive waste and it is mixed by an agitator. A predetermined amount of solidifier such as unsaturated polyester or the like is added to the mixture and it is further mixed by the agitator to form a stable W/O emulsion. Subsequently, predetermined amounts of polymerization starting agent such as methyl ethyl ketone peroxide and polymerization accelerator such as cobalt naphthenate or the like are added thereto, the mixture is mixed, and is then allowed to stand for at room temperature for the plastic solidification thereof. No reaction occurs after the solidification. (Sekiya, K.)

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

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Spent fuel, high-level radioactive waste, or reactor... RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE Siting Evaluation Factors § 72.108 Spent fuel, high-level radioactive waste, or reactor-related greater than Class C waste transportation. The...

Radioactivity reveals how crisps mix

Energy Technology Data Exchange (ETDEWEB)

Parker, David [School of Physics and Astronomy, University of Birmingham, Birmingham (United Kingdom)

2000-01-01

Many of the ''fluids'' processed in the food industry have strange flow properties that cannot easily be predicted. This is an important question in industry, since engineers need to know how such systems flow through pipes in production plants or how different components mix together. To counter this lack of knowledge, the fluids are generally processed for longer than necessary, which often proves expensive and may affect the quality of the final product. The University of Birmingham Positron Imaging Centre has developed a powerful technique to study the behaviour of crisps, yoghurt and ice cream - together with many other granular materials and viscous fluids - in a variety of industrial processes. In one case, the group labelled a single crisp using a positron-emitting radioisotope and added it to a rotating drum full of crisps. By tracking the movement of the labelled crisp, they could determine how uniformly the crisps were exposed to the flavouring that was added in the mixing process. In this article the author describes the research at the university's Positron Imaging Centre. (UK)

Radioactivity reveals how crisps mix

International Nuclear Information System (INIS)

Parker, David

2000-01-01

Many of the ''fluids'' processed in the food industry have strange flow properties that cannot easily be predicted. This is an important question in industry, since engineers need to know how such systems flow through pipes in production plants or how different components mix together. To counter this lack of knowledge, the fluids are generally processed for longer than necessary, which often proves expensive and may affect the quality of the final product. The University of Birmingham Positron Imaging Centre has developed a powerful technique to study the behaviour of crisps, yoghurt and ice cream - together with many other granular materials and viscous fluids - in a variety of industrial processes. In one case, the group labelled a single crisp using a positron-emitting radioisotope and added it to a rotating drum full of crisps. By tracking the movement of the labelled crisp, they could determine how uniformly the crisps were exposed to the flavouring that was added in the mixing process. In this article the author describes the research at the university's Positron Imaging Centre. (UK)

Scope and approach to management of mixed wastes: introduction to the session

International Nuclear Information System (INIS)

Ausmus, B.S.

1986-01-01

Mixed wastes are those that are termed both radioactive and chemically hazardous based on regulatory criteria in the United States. Historically, mixed wastes that could be classified as radioactive wastes were treated, stored, and disposed under statutes governing radioactive wastes. In recent years, it has become apparent that: (a) hazardous wastes are generated in nuclear facilities; (b) many wastes are both radioactive and chemically hazardous; and (c) the management of chemically hazardous wastes and mixed wastes requires reexamination of current waste treatment/disposal methods and development/implementation of modified methods. The purpose of this session is to discuss specific aspects of the mixed waste management problems and to provide a forum for discussion of the technical and institutional barriers to problem solutions. The paper addresses several mixed waste problems and current approaches to their solutions, including: (1) mixed waste management in fuel cycle facilities; (2) mixed waste management in a US Dept. of Energy production facility; and (3) mixed wastes impacts on 10CFR61 compliance. Technical and institutional approaches to mixed waste management are explored in three areas: (1) alternatives for treatment prior to shallow land disposal; (2) potential benefits of recovery of strategic/critical materials from mixed wastes; and (3) shallow land disposal system compatibilities/problems

Radioactive lightning rods: radiologic evaluation and regulatory policy related to its use in Cuba

International Nuclear Information System (INIS)

Lopez Forteza, Yamil; Quevedo Garcia, Jose R.; Diaz Guerra, Pedro I.; Cruz Dumenico, Gonzalez; Fuente Puch, Andres de la

2001-01-01

The radioactive lightning rod employment for the protection of facilities against atmospheric discharges reached its maximum splendor in the eighties. It was in fact at the end of this decade when the technical considerations related to the justification of this practice finally conclude that the production of such teams was abolished. For the regulatory authorities, however, it continues having validity the question related to the control of lightning rod still in use as well as the question related to the establishment of a coherent with the international practice national policy. The paper shows the results of the last 10 years of control of the radioactive lightning rod use in Cuba and the radiological evaluation carried out on the base of this experience. Lastly, it exposes the regulatory policy referred to the employment of the radioactive lightning rod in the country. (author)

Incineration systems for low level and mixed wastes

International Nuclear Information System (INIS)

Vavruska, J.

1986-01-01

A variety of technologies has emerged for incineration of combustible radioactive, hazardous, and mixed wastes. Evaluation and selection of an incineration system for a particular application from such a large field of options are often confusing. This paper presents several current incineration technologies applicable to Low Level Waste (LLW), hazardous waste, and mixed waste combustion treatment. The major technologies reviewed include controlled-air, rotary kiln, fluidized bed, and liquid injection. Coupled with any incineration technique is the need to select a compatible offgas effluent cleaning system. This paper also reviews the various methods of treating offgas emissions for acid vapor, particulates, organics, and radioactivity. Such effluent control systems include the two general types - wet and dry scrubbing with a closer look at quenching, inertial systems, fabric filtration, gas absorption, adsorption, and various other filtration techniques. Selection criteria for overall waste incineration systems are discussed as they relate to waste characterization

National Institutes of Health: Mixed waste stream analysis

International Nuclear Information System (INIS)

Kirner, N.P.; Faison, G.P.; Johnson, D.R.

1994-08-01

The Low-Level Radioactive Waste Policy Amendments Act of 1985 requires that the US Department of Energy (DOE) provide technical assistance to host States, compact regions, and unaffiliated States to fulfill their responsibilities under the Act. The National Low-Level Waste Management Program (NLLWMP) operated for DOE by EG ampersand G Idaho, Inc. provides technical assistance in the development of new commercial low-level radioactive waste disposal capacity. The NLLWMP has been requested by the Appalachian Compact to help the biomedical community become better acquainted with its mixed waste streams, to help minimize the mixed waste streams generated by the biomedical community, and to provide applicable treatment technologies to those particular mixed waste streams. Mixed waste is waste that satisfies the definition of low-level radioactive waste (LLW) in the Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA) and contains hazardous waste that either (a) is listed as a hazardous waste in Subpart D of 40 CFR 261, or (b) causes the LLW to exhibit any of the hazardous waste characteristics identified in 40 CFR 261. The purpose of this report is to clearly define and characterize the mixed waste streams generated by the biomedical community so that an identification can be made of the waste streams that can and cannot be minimized and treated by current options. An understanding of the processes and complexities of generation of mixed waste in the biomedical community may encourage more treatment and storage options to become available

Sim and Ritchie's summary of the law relating to atomic energy and radioactive substances

International Nuclear Information System (INIS)

Grazebrook, D.; Turner, M.

1984-12-01

The law is summarised under the headings: the Common Law; the Legislation; Regulations under the Factories Act 1961; Regulations relating to educational establishments; Regulations and Orders relating to food and medicines; Regulations, Rules, etc. affecting the transport of radioactive materials; Regulations under the Social Security Act 1975; control of import and export; the Euratom Treaty; important non-statutory Codes of Practice, etc.; international Conventions, Regulations, etc. relating to the peaceful use of atomic energy and radioactive substances, in which the United Kingdom is interested; foreign legislation. (U.K.)

AECL's mixed waste management program

International Nuclear Information System (INIS)

Peori, R.; Hulley, V.

2006-01-01

Every nuclear facility has it, they wish that they didn't but they have generated and do possess m ixed waste , and until now there has been no permanent disposition option; it has been for the most been simply maintained in interim storage. The nuclear industry has been responsibly developing permanent solutions for solid radioactive waste for over fifty years and for non-radioactive, chemically hazardous waste, for the last twenty years. Mixed waste (radioactive and chemically hazardous waste) however, because of its special, duo-hazard nature, has been a continuing challenge. The Hazardous Waste and Segregation Program (HW and SP) at AECL's CRL has, over the past ten years, been developing solutions to deal with their own in-house mixed waste and, as a result, have developed solutions that they would like to share with other generators within the nuclear industry. The main aim of this paper is to document and describe the early development of the solutions for both aqueous and organic liquid wastes and to advertise to other generators of this waste type how these solutions can be implemented to solve their mixed waste problems. Atomic Energy of Canada Limited (AECL) and in particular, CRL has been satisfactorily disposing of mixed waste for the last seven years. CRL has developed a program that not only disposes of mixed waste, but offers a full service mixed waste management program to customers within Canada (that could eventually include U.S. sites as well) that has developed the experience and expertise to evaluate and optimize current practices, dispose of legacy inventories, and set up an efficient segregation system to reduce and effectively manage, both the volumes and expense of, the ongoing generation of mixed waste for all generators of mixed waste. (author)

Determining how much mixed waste will require disposal

International Nuclear Information System (INIS)

Kirner, N.P.

1990-01-01

Estimating needed mixed-waste disposal capacity to 1995 and beyond is an essential element in the safe management of low-level radioactive waste disposal capacity. Information on the types and quantities of mixed waste generated is needed by industry to allow development of treatment facilities and by states and others responsible for disposal and storage of this type of low-level radioactive waste. The design of a mixed waste disposal facility hinges on a detailed assessment of the types and quantities of mixed waste that will ultimately require land disposal. Although traditional liquid scintillation counting fluids using toluene and xylene are clearly recognized as mixed waste, characterization of other types of mixed waste has, however, been difficult. Liquid scintillation counting fluids comprise most of the mixed waste generated and this type of mixed waste is generally incinerated under the supplemental fuel provisions of the Resource Conservation and Recovery Act (RCRA) Because there are no Currently operating mixed waste land disposal facilities, it is impossible to make projections of waste requiring land disposal based on a continuation of current waste disposal practices. Evidence indicates the volume of mixed waste requiring land disposal is not large, since generators are apparently storing these wastes. Surveys conducted to date confirm that relatively small volumes of commercially generated mixed waste volume have relied heavily oil generators' knowledge of their wastes. Evidence exists that many generators are confused by the differences between the Atomic Energy Act and the Resource Conservation and Recovery Act (RCRA) on the issue of when a material becomes a waste. In spite of uncertainties, estimates of waste volumes requiring disposal can be made. This paper proposes an eight-step process for such estimates

Summary of the law relating to atomic energy and radioactive substances as at March 1979

International Nuclear Information System (INIS)

Sim, D.F.; Ritchie, K.J.S.

1979-01-01

This summary is intended to be a 'signpost' to the relevant law in the United Kingdom, but does not cover any aspect in detail. It falls under the following headings: common law; legislation (Atomic Energy Act 1946 and subordinate legislation; Radioactive Substances Act 1948 and subordinate legislation; Radioactive Substances Act 1960; Electricity (Amendment) Act 1961; Nuclear Installations Acts 1965 and 1969 and subordinate legislation; the Secretary of State for Trade and Industry Order 1970; Radiological Protection Act 1970 as amended by the Health and Safety at Work etc. Act 1974; Air Navigation (Restriction of Flying)(Atomic Energy Establishments) Regulations 1976; Nuclear Safeguards and Electricity (Finance) Act 1978; legislation relating to the United Kingdom Atomic Energy Authority); regulations under the Factories Act 1961; regulations relating to educational establishments; regulations and orders relating to food and medicines; regulations, rules etc. affecting the transport of radioactive materials; regulations under the Social Security Act 1975; control of import and export; the Euratom Treaty; important non-statutory codes of practice etc.; international conventions, regulations etc. relating to the peaceful use of atomic energy and radioactive substances, in which the United Kingdom is interested; foreign legislation. (U.K.)

Indoor-atmospheric radon-related radioactivity affected by a change of ventilation strategy

International Nuclear Information System (INIS)

Kobayashi, Tuneo

2006-01-01

The present author has kept observation for concentrations of atmospheric radon, radon progeny and thoron progeny for several years at the campus of Fukushima Medical University. Accidentally, in the midst of an observation term, i.e., February 2005, the facility management group of the university changed a strategy for the manner of ventilation, probably because of a recession: tidy everyday ventilation of 7:30-24:00 into shortened weekday ventilation of 8:00-21:00 with weekend halts. This change of ventilation manner brought a clear alteration for the concentrations of radon-related natural radioactivity in indoor air. The present paper concerns an investigation of the effect of the ventilation strategy on the indoor-atmospheric radon-related radioactivity. (author)

Loopholes of laws and regulations related to redevelopment of former sites of radioactive material control area

International Nuclear Information System (INIS)

Akatsuka, Hiroshi

2003-01-01

We found loopholes of laws and regulations for supervising radioactive materials. It is not obliged to measure the soil radioactivity of the sites that were formerly used as scientific or engineering institutes, or hospitals with a radioactive material control area. If the former institutes or hospitals made studies with radioactive materials before the enforcement of the law concerning prevention from radiation hazards due to isotopes and its detailed regulations, it is concluded that there was the period when the radioactive materials were not under management. If it is found that the radioactive materials were applied at the former site before the enforcement of the related laws and regulations, the radioactivity in the soil of the redeveloped area should be examined, which should be obliged by some laws or regulations. (author)

An overview of radioactive waste management in Canada

International Nuclear Information System (INIS)

Liblong, S.W.; Wong, C.F.

2014-01-01

As a Tier I nuclear nation, with a comprehensive nuclear sector whose beginnings date back to the 1940's, Canada is faced with radioactive waste management challenges for a diverse range of radioactive material - from very low-level to high-level. The nuclear fuel cycle is fully realized in Canada, from uranium mines and mills through to significant reliance on nuclear energy thorough to a broad-based science & technology platform. Natural Resources Canada is responsible for Canadian nuclear policy, while the provincial governments decide on the management of their resources and energy mix within their jurisdictions. While the fundamental policy regarding responsibility for radioactive waste places the onus on the generator, the means by which this is accomplished is not prescriptive beyond meeting regulatory requirements. As a result, approaches to dealing with radioactive waste have evolved according to the needs and abilities of the various generators. This paper will provide an overview of radioactive waste management in Canada, highlighting the approaches used within various sectors for the different classifications of waste, and will also look at plans for future waste management capabilities being developed at this time (including issues related to disposal vs. management). Challenges to the development of an effective and comprehensive 'Canadian solution' will also be discussed. (author)

Method for ultimate disposition of borate containing radioactive wastes by vitrification

International Nuclear Information System (INIS)

Bege, D.; Faust, H.J.; Puthawala, A.; Stunkel, H.

1984-01-01

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

Radioactivity metrology

International Nuclear Information System (INIS)

Legrand, J.

1979-01-01

Some aspects of the radioactivity metrology are reviewed. Radioactivity primary references; absolute methods of radioactivity measurements used in the Laboratoire de Metrologie des Rayonnements Ionisants; relative measurement methods; traceability through international comparisons and interlaboratory tests; production and distribution of secondary standards [fr

An industry perspective on commercial radioactive waste disposal conditions and trends.

Science.gov (United States)

Romano, Stephen A

2006-11-01

The United States is presently served by Class-A, -B and -C low-level radioactive waste and naturally-occurring and accelerator-produced radioactive material disposal sites in Washington and South Carolina; a Class-A and mixed waste disposal site in Utah that also accepts naturally-occurring radioactive material; and hazardous and solid waste facilities and uranium mill tailings sites that accept certain radioactive materials on a site-specific basis. The Washington site only accepts low-level radioactive waste from 11 western states due to interstate Compact restrictions on waste importation. The South Carolina site will be subject to geographic service area restrictions beginning 1 July 2008, after which only three states will have continued access. The Utah site dominates the commercial Class-A and mixed waste disposal market due to generally lower state fees than apply in South Carolina. To expand existing commercial services, an existing hazardous waste site in western Texas is seeking a Class-A, -B and -C and mixed waste disposal license. With that exception, no new Compact facilities are proposed. This fluid, uncertain situation has inspired national level rulemaking initiatives and policy studies, as well as alternative disposal practices for certain low-activity materials.

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

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Criteria for spent fuel, high-level radioactive waste, reactor-related greater than Class C waste, and other radioactive waste storage and handling. 72.128... STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C...

Savannah River Plant Separations Department mixed waste program

International Nuclear Information System (INIS)

Wierzbicki, W.M.

1988-01-01

The Department of Energy's (DOE) Savannah River Plant (SRP) generates radioactive and mixed waste as a result of the manufacture of nuclear material for the national defense program. The radioactive portion of the mixed waste and all nonhazardous radioactive wastes would continue to be regulated by DOE under the Atomic Energy Act. The Separations Department is the largest generator of solid radioactive waste at the Savannah River Plant. Over the last three years, the Separations Department has developed and implemented a program to characterize candidate mixed-waste streams. The program consisted of facility personnel interviews, a waste-generation characterization program and waste testing to determine whether a particular waste form was hazardous. The Separations Department changed waste-handling practices and procedures to meet the requirements of the generator standards. For each Separation Department Facility, staging areas were established, inventory and reporting requirements were developed, operating procedures were revised to ensure proper waste handling, and personnel were provided hazardous waste training. To emphasize the importance of the new requirements, a newsletter was developed and issued to all Separations supervisory personnel

Method and apparatus for glass solidification porcessing for radioactive liquid waste

International Nuclear Information System (INIS)

Torada, Shin-ichiro; Masaki, Toshio; Sakai, Akira.

1989-01-01

Glass material supplied to a glass melting furnace is made in the form of a glass container. Then, radioactive liquid wastes are directly injected into the glass vessel and the glass vessel injected with the radioactive liquid wastes is charged into the glass melting furnace. The glass material and the radioactive liquid wastes are supplied simultaneously to the glass melting furnace. Then, corresponding to the amount of the glass material used for the glass vessel, the amount of the radioactive liquid wastes injected to the inside thereof is controlled to thereby set the mixing ratio between the glass material and the radioactive liquid wastes. Further, by controlling the number of the glass vessels injected with the radioactive liquid wastes to be charged into the glass melting furnace, the amount of supplying the radioactive liquid wastes and the glass material is controlled. This can easily maintain constant the amount of the glass material and the radioacative liquid wastes supplied to the glass melting furnace and the mixing ratio thereof. (T.M.)

DEPO-related to Radioactive Sources.

Energy Technology Data Exchange (ETDEWEB)

Miller, James Christopher [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-02-24

Design and Evaluation Process Outline (DEPO) is discussed as it pertains to protection of radioactive sources. The bulk of the report describes features of various kinds of detection systems, and follows this with systems for entry control and personnel identification.

Mixed Waste Integrated Program: A technology assessment for mercury-containing mixed wastes

International Nuclear Information System (INIS)

Perona, J.J.; Brown, C.H.

1993-03-01

The treatment of mixed wastes must meet US Environmental Protection Agency (EPA) standards for chemically hazardous species and also must provide adequate control of the radioactive species. The US Department of Energy (DOE) Office of Technology Development established the Mixed Waste Integrated Program (MWIP) to develop mixed-waste treatment technology in support of the Mixed Low-Level Waste Program. Many DOE mixed-waste streams contain mercury. This report is an assessment of current state-of-the-art technologies for mercury separations from solids, liquids, and gases. A total of 19 technologies were assessed. This project is funded through the Chemical-Physical Technology Support Group of the MWIP

IAEA mode-related research in the safe transport of radioactive material

Energy Technology Data Exchange (ETDEWEB)

Blalock, L.G.; Rawl, R.R. [International Atomic Energy Agency, IAEA, Vienna (Austria)

1998-07-01

The International Atomic Energy Agency sponsors Co-ordinated Research Programmes (CRP) in the safe transport of radioactive material. The CRPs are intended to encourage research by Member States in identified areas and to facilitate co-ordination of exchange of information and resources to reach a common understanding of the problem and alternative solutions. Two of these programmes are: Accident Severity at Sea During the Transport of Radioactive Material and Accident Severity During the Air Transport of Radioactive Material. This paper will discuss these two programmes and their relationship to the continuing regulatory revision process and interfaces with the International Maritime Organization (IMO) and the International Civil Aviation Organization (ICAO). Some Member States and non-governmental organizations in IMO meetings expressed concerns that accidents on board ships may be more severe than the IAEA regulatory tests account for, and that package failure with subsequent release of radioactive material may occur. The CRP on accident severity at sea was established to develop further quantitative information on potential accident severities during the transport of radioactive material by ships. The primary objective of this programme is to collect and evaluate statistical data of marine accidents, perform analyses of potential accident conditions and evaluate the risks resulting from such shipments. The CRP on air transport was established to make a major international effort to collect relevant frequency and severity data and to analyze it so the accident forces to which a packages of radioactive material might be subjected to in a severe air accident can be more confidently quantified. Several countries have ongoing data collection activities related to aircraft accidents and severity and other sources of statistics for in-flight aircraft accidents will be explored. The International Civil Aviation Organization informed the IAEA of their plans to improve

IAEA mode-related research in the safe transport of radioactive material

International Nuclear Information System (INIS)

Blalock, L.G.; Rawl, R.R.

1998-01-01

The International Atomic Energy Agency sponsors Co-ordinated Research Programmes (CRP) in the safe transport of radioactive material. The CRPs are intended to encourage research by Member States in identified areas and to facilitate co-ordination of exchange of information and resources to reach a common understanding of the problem and alternative solutions. Two of these programmes are: Accident Severity at Sea During the Transport of Radioactive Material and Accident Severity During the Air Transport of Radioactive Material. This paper will discuss these two programmes and their relationship to the continuing regulatory revision process and interfaces with the International Maritime Organization (IMO) and the International Civil Aviation Organization (ICAO). Some Member States and non-governmental organizations in IMO meetings expressed concerns that accidents on board ships may be more severe than the IAEA regulatory tests account for, and that package failure with subsequent release of radioactive material may occur. The CRP on accident severity at sea was established to develop further quantitative information on potential accident severities during the transport of radioactive material by ships. The primary objective of this programme is to collect and evaluate statistical data of marine accidents, perform analyses of potential accident conditions and evaluate the risks resulting from such shipments. The CRP on air transport was established to make a major international effort to collect relevant frequency and severity data and to analyze it so the accident forces to which a packages of radioactive material might be subjected to in a severe air accident can be more confidently quantified. Several countries have ongoing data collection activities related to aircraft accidents and severity and other sources of statistics for in-flight aircraft accidents will be explored. The International Civil Aviation Organization informed the IAEA of their plans to improve

Defense radioactive waste management

International Nuclear Information System (INIS)

Hindman, T.B. Jr.

1988-01-01

The Office of Defense Programs (DP), U.S. Department of Energy, is responsible for the production of nuclear weapons and materials for national defense. Pursuant to this mission, DP operates a large industrial complex that employs over 60,000 people at various installations across the country. As a byproduct of their activities, these installations generate radioactive, hazardous, or mixed wastes that must be managed in a safe and cost-effective manner in compliance with all applicable Federal and STate environmental requirements. At the Federal level such requirements derive primarily from the Atomic Energy Act, the Resource Conservation and Recovery Act (RCRA), the comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and the Superfund Amendments and Reauthorization Act (SARA). Responsibility for DP activities in connection with the disposal of defense wastes is consolidated within the Office of Defense Waste and Transportation Management (DWTM). This paper discusses these activities which consist of five principal elements: the environmental restoration of inactive DP facilities and sites, the processing storage and disposal of wastes associated with ongoing operations at active DP facilities, research and development directed toward the long-term disposal of radioactive, hazardous, mixed wastes, technology development directly supporting regulatory compliance, and the development of policies, procedures, and technologies for assuring the safe transportation of radioactive and hazardous materials

Migration barrier covers for radioactive and mixed waste landfills

International Nuclear Information System (INIS)

Hakonson, T.E.; Manies, K.L.; Warren, R.W.; Bostick, K.V.; Trujillo, G.; Kent, J.S.

1993-01-01

Migration barrier cover technology will likely serve as the remediation alternative of choice for most of DOE's radioactive and mixed waste landfills simply because human and ecological risks can be effectively managed without the use of more expensive alternatives. However, very little testing and evaluation has been done, either before or after installation, to monitor how effective they are in isolating waste or to develop data that can be used to evaluate model predictions of long term performance. Los Alamos National Laboratory has investigated the performance of a variety of landfill capping alternatives since 1981 using large field lysimeters to monitor the fate of precipitation falling on the cap surface. The objective of these studies is to provide the risk manager with a variety of field tested capping designs, of various complexities and costs, so that design alternatives can be matched to the need for hydrologic control at the site. Four different landfill cap designs, representing different complexities and costs, were constructed at Hill Air Force Base (AFB) in October and November, 1989. The designs were constructed in large lysimeters and instrumented to provide estimates of all components of water balance including precipitation, runoff (and soil erosion), infiltration, leachate production, evapotranspiration, and capillary/hydraulic barrier flow. The designs consisted of a typical soil cover to serve as a baseline, a modified EPA RCRA cover, and two versions of a Los Alamos design that contained erosion control measures, an improved vegetation cover to enhance evapotranspiration, and a capillary barrier to divert downward flow of soil water. A comprehensive summary of the Hill AFB demonstration will be available in October 1993, when the project is scheduled to terminate

Treating agent for urea containing radioactive materials

International Nuclear Information System (INIS)

Ogawa, Hiroshi; Maki, Kentaro.

1973-01-01

Object: To add a coagulant into urea containing radioactive material to precipitate and remove the radioactive material in the urea. Structure: Iodosalt is added into urea and next, a mixed reagent in which silver ion or silver acetic ion and iron hydroxide precipitation or ferrite ion coexist is added therein. The urea is treated to have a sufficient alkaline, after which it is introduced into a basket type centrifuge formed with a filter layer in combination of an upper glass fiber layer and a lower active carbon layer. The treating agent can uniformly remove radioactive ion and radioactive chelate within urea containing inorganic salt and various metabolites. (Nakamura, S.)

The role of the California Base Closure Environmental Committee's (CBCEC) Radioactive and Mixed Waste Process Action Team (RMWPAT) in expediting site restoration and reuse

International Nuclear Information System (INIS)

Laudon, L.S.

1994-01-01

The Base Realignment and Closure Act (BRAC) mandated the closing and transfer of Department of Defense (DoD) properties within specific timeframes. Due to requirements of federal and state laws, closing bases must be environmentally remediated to alleviate threats to human health and the environment upon transfer. Certain barriers such as legislative, regulatory, administrative, and technical issues, have been identified which threaten the timely restoration and transfer of these BRAC properties. The state of California, faced with the scheduled closure or realignment of 26 military bases, recognized the need to establish a base closure environmental committee to address issues affecting the timely cleanup and reuse of DoD properties and promote accelerated restoration. Accordingly, the California Base Closure Environmental Committee (CBCEC) was formed by executive order of Governor Pete Wilson. One of the barriers identified by the CBCEC is the potential contamination of DoD facilities with radioactive materials. As a result of the difficulties encountered in assessing the nature and extent of radioactive contamination at DoD sites in California, the CBCEC formed the Radioactive and Mixed Waste Process Action Team (RMWPAT). The RMWPAT was tasked with ''demystifying'' and working to address issues associated with radioactive contamination

Treatment technology analysis for mixed waste containers and debris

International Nuclear Information System (INIS)

Gehrke, R.J.; Brown, C.H.; Langton, C.A.; Askew, N.M.; Kan, T.; Schwinkendorf, W.E.

1994-03-01

A team was assembled to develop technology needs and strategies for treatment of mixed waste debris and empty containers in the Department of Energy (DOE) complex, and to determine the advantages and disadvantages of applying the Debris and Empty Container Rules to these wastes. These rules issued by the Environmental Protection Agency (EPA) apply only to the hazardous component of mixed debris. Hazardous debris that is subjected to regulations under the Atomic Energy Act because of its radioactivity (i.e., mixed debris) is also subject to the debris treatment standards. The issue of treating debris per the Resource Conservation and Recovery Act (RCRA) at the same time or in conjunction with decontamination of the radioactive contamination was also addressed. Resolution of this issue requires policy development by DOE Headquarters of de minimis concentrations for radioactivity and release of material to Subtitle D landfills or into the commercial sector. The task team recommends that, since alternate treatment technologies (for the hazardous component) are Best Demonstrated Available Technology (BDAT): (1) funding should focus on demonstration, testing, and evaluation of BDAT on mixed debris, (2) funding should also consider verification of alternative treatments for the decontamination of radioactive debris, and (3) DOE should establish criteria for the recycle/reuse or disposal of treated and decontaminated mixed debris as municipal waste

Cauchy inequality and uncertainty relations for mixed states

International Nuclear Information System (INIS)

Shirokov, M.I.

2004-01-01

Cauchy inequality (CI) relates scalar products of two vectors and their norms. I point out other similar inequalities (SI). Starting with CI Schroedinger derived his uncertainty relation (UR). By using SI other various UR can be obtained. It is shown that they follow from the Schroedinger UR. Two generalizations of CI are obtained for mixed states described by density matrices. Using them two generalizations of UR for mixed states are derived. Both differ from the UR generalization known from the literature. The discussion of these generalizations is given

Principles for disposal of radioactive and chemical hazardous wastes

International Nuclear Information System (INIS)

Merz, E. R.

1991-01-01

The double hazard of mixed wastes is characterized by several criteria: radioactivity on the one hand, and chemical toxicity, flammability, corrosiveness as well as chemical reactivity on the other hand. Chemotoxic waste normally has a much more complex composition than radioactive waste and appears in much larger quantities. However, the two types of waste have some properties in common when it comes to their long-term impact on health and the environment. In order to minimize the risk associated with mixed waste management, the material assigned for ultimate disposal should be thoroughly detoxified, inertized, or mineralized prior to conditioning and packaging. Good control over the environmental consequence of waste disposal requires that detailed criteria for tolerable contamination should be established, and that compliance with these criteria can be demonstrated. For radioactive waste, there has been an extensive international development of criteria to protect human health. For non-radioactive waste, derived criteria exist only for a limited number of substances

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

International Nuclear Information System (INIS)

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

2003-01-01

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

Method and device for solidifying radioactive waste

International Nuclear Information System (INIS)

Hayashi, Tadamasa.

1981-01-01

Purpose: To solidify radioactive waste without producing radioactive dusts by always heating and evaporating the water from liquid radioactive waste in a mixture of liquid plastic and exhausting the molten mixture of the waste residue and the plastic material. Constitution: Liquid plastic material in a tank cooled to prevent polymerization or changes of its properties is continuously supplied to the top of a heating and mixing evaporator by a constant supply pump. After the heat transfer surface of the evaporator is covered with the plastic material, radioactive waste in the tank is supplied to the evaporator via the constant supply pump. The waste is abruptly mixed with the plastic material by an agitating rotor, heated by a heater, and the evaporated water is fed to a condenser. An anhydrous molten mixture is continuously exhausted from the bottom of the evaporator into a mixture cooler, a polymerizing agent and catalyst are introduced thereinto from a polymerizing agent tank and a catalyst tank, inhibitor is introduced thereinto from a polymerization inhibitor tank as required, and is filled with the mixture a solidifying container while it is cooled for its polymerization and solidification. (Yoshino, Y.)

Mixed waste: A proposed solution that focuses on the underlying problem rather than on its symptoms

International Nuclear Information System (INIS)

Thompson, A.J.; Goo, M.L.

1993-01-01

Viewed critically, it is apparent that the current mixed waste stream is the result of conflicting regulatory regimes. The current mixed waste system is neither functional nor rational. Despite numerous and elaborate attempts by NRC, EPA, and DOE to minimize and avoid conflicts between the existing regulatory schemes for radioactive and hazardous waste, the fundamental conflict between Atomic Energy Act and Resource Conservative and Recovery Act requirements remains obvious and unabated. Regulatory paralysis is the result. In this article, the authors outline some of the key inconsistencies between hazardous and radioactive waste management and disposal requirements and trace the effect these conflicts have had on the existing mixed waste system. The authors argue that mixed waste is of two primary types: Waste that is either primarily radioactively hazardous or primarily chemically hazardous and that regulatory requirements should reflect this fact. Hence, where a mixed waste contains only low levels of radioactivity and is primarily chemically hazardous, RCRA controls should predominate. Where a mixed waste contains any significant amount of radioactivity, however, AEA requirements, not RCRA should control

Method of plastic solidification of radioactive wastes

International Nuclear Information System (INIS)

Oikawa, Yasuo; Tokimitsu, Fujio.

1986-01-01

Purpose: To prevent occurrence of deleterious cracks to the inside and the surface of solidification products, as well as eliminate gaps between the products and the vessel inner wall upon plastic solidification processing for powdery or granular radioactive wastes. Method: An appropriate amount of thermoplastic resins such as styrenic polymer or vinyl acetate type polymer as a low shrinking agent is added and mixed with unsaturated polyester resins to be mixed with radioactive wastes so as to reduce the shrinkage-ratio to 0 % upon curing reaction. Thus, a great shrinkage upon hardening the mixture is suppressed to prevent the occurrence of cracks to the surface and the inside of the solidification products, as well as prevent the gaps between the inner walls of a drum can vessel and the products upon forming solidification products to the inside of the drum can. The resultant solidification products have a large compression strength and can sufficiently satisfy the evaluation standards as the plastic solidification products of radioactive wastes. (Horiuchi, T.)

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

International Nuclear Information System (INIS)

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

1990-01-01

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

Costs related to radioactive residues from nuclear power

International Nuclear Information System (INIS)

1988-06-01

The nuclear power enterprises are responsible for proper actions for safe handling and final storage of spent nuclear fuel and radioactive waste from Swedish nuclear power facilities. The most important actions are to plan, build and operate necessary plants and systems. The nuclear power enterprises have designated Swedish Nuclear Fuel and Waste Management Co., (SKB), to perform these tasks. In this report calculations concerning costs to carry out these tasks are presented. The calculations are based upon a plan prepared by SKB. The plan is described in the report. As final storage of the long lived and highly radioactive waste is planned to take place in the 21st century continuing research and development may indicate new methods which may affect system design as well as costs in a simplifying way. Plants and systems already operational are: Transport systems for radioactive waste products; A central temporary storage for spent nuclear fuel, 'CLAB'; A final storage for radioactive waste from operating nuclear facilities, 'SFR 1'. (L.F.)

Photochemical oxidation: A solution for the mixed waste dilemma

Energy Technology Data Exchange (ETDEWEB)

Prellberg, J.W.; Thornton, L.M.; Cheuvront, D.A. [Vulcan Peroxidation Systems, Inc., Tucson, AZ (United States)] [and others

1995-12-31

Numerous technologies are available to remove organic contamination from water or wastewater. A variety of techniques also exist that are used to neutralize radioactive waste. However, few technologies can satisfactorily address the treatment of mixed organic/radioactive waste without creating unacceptable secondary waste products or resulting in extremely high treatment costs. An innovative solution to the mixed waste problem is on-site photochemical oxidation. Liquid-phase photochemical oxidation has a long- standing history of successful application to the destruction of organic compounds. By using photochemical oxidation, the organic contaminants are destroyed on-site leaving the water, with radionuclides, that can be reused or disposed of as appropriate. This technology offers advantages that include zero air emissions, no solid or liquid waste formation, and relatively low treatment cost. Discussion of the photochemical process will be described, and several case histories from recent design testing, including cost analyses for the resulting full-scale installations, will be presented as examples.

Incineration of low level and mixed wastes: 1986

International Nuclear Information System (INIS)

Anon.

1986-01-01

The University of California at Irvine, in cooperation with the Department of Energy, American Society of Mechanical Engineers, and chapters of the Health Physics Society, coordinated this conference on the Incineration of Low-Level Radioactive and Mixed Wastes, with the guidance of professionals active in the waste management community. The conference was held in April 22-25, 1986 at Sheraton airport hotel Charlotte, North Carolina. Some of the papers' titles were: Protection and safety of different off-gas treatment systems in radioactive waste incineration; performance assessment of refractory samples in the Los Alamos controlled-Air incinerator; incineration systems for low-level and mixed wastes; incineration of low-level radioactive waste in Switzerland-operational experience and future activities

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

Science.gov (United States)

2013-02-11

... NUCLEAR REGULATORY COMMISSION Request To Amend a License To Export Radioactive Waste Pursuant to... radioactive disposition. Amend which was imported mixed waste) in to: 1) add four from Canada under NRC a....; docket No. country Diversified Scientific Class A radioactive Up to a maximum Return of non- Canada...

Analyzing relation between the radioactivity in lanthanum products and the origins of RE chlorides

International Nuclear Information System (INIS)

Wan Rongsheng

2004-01-01

Objective: To analyze the relation between the radioactivity in Lanthanum products and the origins of RE Chlorides. Methods: Using JY-38 plus sequential ICP spectrometer to examine the content of the uranium in the RE Chlorides. Using FJ-2603 low background alpha, beta measurement apparatus to measure total alpha and total beta activities of Lanthanum products. Results: The content of the uranium in the RE Chlorides is much lower in Baotou's than Hunan's. The radioactivity in Lanthanum products are made from the RE Chlorides of Baotou is much lower than that in Hunan's too. The radioactivity in Lanthanum products depends on the origins of RE Chlorides. Conclusion: The basic data were provided for radioactivity in Lanthanum products which are made from RE Chlorides of different places of China. The mathematical model was founded for the reasonable use of resource RE Chlorides

Governance relative to radioactive waste management - the Act of 28 June 2006

International Nuclear Information System (INIS)

Chevet, P.F.

2011-01-01

In France, the Act of 30 December 1991, relative to research on radioactive waste management, known as the 'Bataille Act' (Act No.91-1381) can be thought of as the legislative act that provided the foundations for implementation of a long-term management policy regarding high-level nuclear waste, the most radio toxic type of waste. To begin with, this involved establishing the framework for a research programme based on three possible long-term management solutions: deep geological repositories, long-term surface storage and advanced partitioning and transmutation of radioactive waste. The Act sets a deadline in 2006, the end of a period of fifteen years of research, to draw up a review and draft a new legislative framework for the future. Nonetheless, this only covered high-level radioactive waste. A table reports all the decrees taken within the framework of the Bataille Act

Radioactive air emissions 1992 summary

International Nuclear Information System (INIS)

Wahl, L.

1993-10-01

This report summarizes, by radionuclide or product and by emitting facility, the Laboratory's 1992 radioactive air emissions. In 1992, the total activity of radionuclides emitted into the air from Laboratory stacks was approximately 73,500 Ci. This was an increase over the activity of the total 1991 radioactive air emissions, which was approximately 62,400 Ci. Total 1992 Laboratory emissions of each radionuclide or product are summarized by tables and graphs in the first section of this report. Compared to 1991 radioactive air emissions, total tritium activity was decreased, total plutonium activity was decreased, total uranium activity was decreased, total mixed fission product activity was increased, total 41 Ar activity was decreased, total gaseous/mixed activation product (except 41 Ar) activity was increased, total particulate/vapor activation product activity was increased, and total 32 P activity was decreased. Radioactive emissions from specific facilities are detailed in this report. Each section provides 1992 data on a single radionuclide or product and is further divided by emitting facility. For each facility from which a particular radionuclide or product was emitted, a bar chart displays the air emissions of each radionuclide or product from each facility over the 12 reporting periods of 1992, a line chart shows the trend in total emissions of that radionuclide or product from that facility for the past three years, the greatest activity during the 1990--1992 period is discussed, and unexpected or unusual results are noted

Radioactive waste management in Belgium

International Nuclear Information System (INIS)

Detilleux, E.

1984-01-01

The first part of this paper briefly describes the nuclear industry in Belgium and the problem of radioactive wastes with regard to their quality and quantity. The second part emphasizes the recent guidelines regarding the management of the nuclear industry in general and the radioactive wastes in particular. In this respect, important tasks are the reinforcement of administrative structures with regard to the supervision and the control of nuclear activities, the establishment of a mixed company entrusted with the covering of the needs of nuclear plants in the field of nuclear fuels and particularly the setting up of a public autonomous and specialized organization, the 'Public Organization for the Management of Radioactive Waste and Fissile Materials', in short 'O.N.D.R.A.F.'. This organization is in charge of the management of the transport, the conditioning, the storage and the disposal of radioactive wastes. (Auth.)

Method of solidifying radioactive wastes

International Nuclear Information System (INIS)

Fukazawa, Tetsuo; Ootsuka, Masaharu; Uetake, Naoto; Ozawa, Yoshihiro.

1984-01-01

Purpose: To prepare radioactive solidified wastes excellent in strength, heat resistance, weather-proof, water resistance, dampproof and low-leaching property. Method: A hardening material reactive with alkali silicates to form less soluble salts is used as a hardener for alkali silicates which are solidification filler for the radioactive wastes, and mixed with cement as a water absorbent and water to solidify the radioactive wastes. The hardening agent includes, for example, CaCO 3 , Ca(ClO 4 ) 2 , CaSiF 6 and CaSiO 3 . Further, in order to reduce the water content in the wastes and reduce the gap ratio in the solidification products, the hardener adding rate, cement adding rate and water content are selected adequately. As the result, solidification products can be prepared with no deposition of easily soluble salts to the surface thereof, with extremely low leaching of radioactive nucleides. (Kamimura, M.)

Aspects related to the testing of sealed radioactive sources

International Nuclear Information System (INIS)

Olteanu, C. M.; Nistor, V.; Valeca, S. C.

2016-01-01

Sealed radioactive sources are commonly used in a wide range of applications, such as: medical, industrial, agricultural and scientific research. The radioactive material is contained within the sealed source and the device allows the radiation to be used in a controlled way. Accidents can result if the control over a small fraction of those sources is lost. Sealed nuclear sources fall under the category of special form radioactive material, therefore they must meet safety requirements during transport according to regulations. Testing sealed radioactive sources is an important step in the conformity assessment process in order to obtain the design approval. In ICN Pitesti, the Reliability and Testing Laboratory is notified by CNCAN to perform tests on sealed radioactive sources. This paper wants to present aspects of the verifying tests on sealed capsules for Iridium-192 sources in order to demonstrate the compliance with the regulatory requirements and the program of quality assurance of the tests performed. (authors)

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

International Nuclear Information System (INIS)

Michael J.; Daly, Ph.D.

2005-01-01

2000 closely matches the Aims proposed in our second NABIR application and is summarized as follows. We have further refined expression vectors for D. radiodurans and successfully tested engineered strains in natural DOE sediment and groundwater samples. Further, we have shown that D. geothermalis is transformable with plasmids and integration vectors designed for D. radiodurans. This was demonstrated by engineering Hg(II)-resistant D. geothermalis strains capable of reducing Hg(II) at elevated temperatures and under chronic irradiation. Additionally, we showed that D. geothermalis, like D. radiodurans, is naturally capable of reducing U(VI), Cr(VI), and Fe(III). These characteristics support the prospective development of this thermophilic radiophile for bioremediation of radioactive mixed waste environments with temperatures as high as 55 C, of which there are many examples. Our annotation of the D. radiodurans genome has been an important guide throughout this project period and continues to be a source of inspiration in the development of new genetic technologies dedicated to this bacterium. For example, our genome analyses have enabled us to achieve engineering goals that were unattainable in our first NABIR project (1997-2000), where uncertainties relating to its metabolic configuration prevented efforts to expand its metabolic capabilities. As just one example, we showed that D. radiodurans has a functioning tricarboxylic acid (TCA) cycle glyoxylate bypass which could be integrated with toluene oxidation. And, we successfully engineered D. radiodurans to derive carbon and energy from complete toluene mineralization and showed that toluene oxidation can be coupled to cellular biosynthesis, survival, as well as its native and engineered metal reducing capabilities. We have also constructed a whole genome microarray for D. radiodurans covering ∼94% of its predicted genes and have successfully used the array to examine the response of cells to radiation and other

Private sector participation for the treatment of DOE and commercial radioactive mixed wastes

International Nuclear Information System (INIS)

Harris, T.L.; Steele, S.M.; Bohrer, H.A.; Garrison, T.W.; Owens, C.M.

1993-01-01

The ability of the US DOE to accept commercial low-level mixed waste (LLMW) for disposal has been identified as a technically feasible alternative in developing a strategy for managing commercial mixed waste. This document is an estimation of DOE's capabilities to assist the state compacts and the commercial sector with the difficult issues related to the treatment and disposal of LLMW. The first step in determining DOE's capabilities to assist the commercial sector and the state compacts in managing their LLMW is to establish how closely DOE's LLMW resembles the LLMW generated commercially. This report established that a large portion of the low-level mixed waste streams are common to both the DOE and private sectors. A united approach between the DOE and the host states and compacts to cooperatively manage the low-level mixed wastes (LLMW) would prove to be beneficial to all

Cementification for radioactive waste including high-concentration sodium sulfate and high-concentration radioactive nuclide

International Nuclear Information System (INIS)

Miyamoto, Shinya; Sato, Tatsuaki; Sasoh, Michitaka; Sakurai, Jiro; Takada, Takao

2005-01-01

For the cementification of radioactive waste that has large concentrations of sodium sulfate and radioactive nuclide, a way of fixation for sulfate ion was studied comprising the pH control of water in contact with the cement solid, and the removal of the excess water from the cement matrix to prevent hydrogen gas generation with radiolysis. It was confirmed that the sulfate ion concentration in the contacted water with the cement solid is decreased with the formation of ettringite or barium sulfate before solidification, the pH value of the pore water in the cement solid can control less than 12.5 by the application of zeolite and a low-alkali cement such as alumina cement or fly ash mixed cement, and removal of the excess water from the cement matrix by heating is possible with aggregate addition. Consequently, radioactive waste including high-concentration sodium sulfate and high-concentration radioactive nuclide can be solidified with cementitious materials. (author)

Analysis of the suitability of DOE facilities for treatment of commercial low-level radioactive mixed waste

International Nuclear Information System (INIS)

1996-02-01

This report evaluates the capabilities of the United States Department of Energy's (DOE's) existing and proposed facilities to treat 52 commercially generated low-level radioactive mixed (LLMW) waste streams that were previously identified as being difficult-to-treat using commercial treatment capabilities. The evaluation was performed by comparing the waste matrix and hazardous waste codes for the commercial LLMW streams with the waste acceptance criteria of the treatment facilities, as identified in the following DOE databases: Mixed Waste Inventory Report, Site Treatment Plan, and Waste Stream and Technology Data System. DOE facility personnel also reviewed the list of 52 commercially generated LLMW streams and provided their opinion on whether the wastes were technically acceptable at their facilities, setting aside possible administrative barriers. The evaluation tentatively concludes that the DOE is likely to have at least one treatment facility (either existing or planned) that is technically compatible for most of these difficult-to-treat commercially generated LLMW streams. This conclusion is tempered, however, by the limited amount of data available on the commercially generated LLMW streams, by the preliminary stage of planning for some of the proposed DOE treatment facilities, and by the need to comply with environmental statutes such as the Clean Air Act

Radioactivity measurement in imported food and food related items

International Nuclear Information System (INIS)

Sombrito, E.Z.; Santos, F.L.; Rosa, A.M. de la; Tangonan, M.C.; Bulos, A.D.; Nuguid, Z.F.

1989-01-01

The Philippine Nuclear Research Institute (PNRI), formerly Philippine Atomic Energy Commission (PAEC) undertook the radioactivity monitoring of imported food and food-related products after the Chernobyl Plant accident in April 1986. Food samples were analyzed for 137 Cs and 134 Cs by gamma spectral method of analysis. This report deals with the measurement process and gives the result of the activity covering the period June 1986 to December 1987. (Auth.). 9 tabs., 7 figs., 4 refs

Development of the remedial action priority system: An improved risk assessment tool for prioritizing hazardous and radioactive-mixed waste disposal sites

International Nuclear Information System (INIS)

Whelan, G.; Strenge, D.L.; Steelman, B.L.; Hawley, K.A.

1985-01-01

The Remedial Action Priority System (RAPS) represents a methodology that prioritizes inactive hazardous and radioactive mixed-waste disposal sites in a scientific and objective manner based on limited site information. This methodology is intended to bridge the technology gap that exists between the initial site evaluation using the Hazard Ranking System (HRS) and the time-consuming process of actual field site characterization, assessment and remediation efforts. The HRS was designed as an initial screening tool to discriminate between hazardous waste sites that do not and those that are likely to power significant problems to human health, safety and/or the environment. The HRS is used by the U.S. EPA to identify sites for nomination to the National Priorities List (NPL). Because the HRS is not designed to evaluate sites containing radionuclides, a modified Hazard Ranking System (mHRS) addressing both hazardous and radioactive mixed wastes was developed by Pacific Northwest Laboratory (PNL) for the U.S. Department of Energy (DOE). Neither the HRS nor the mHRS was designed to prioritize sites that are nominated to the NPL according to their potential risks. To provide DOE with a better management tool for prioritizing funding and human resource allocations for further investigations and possible remediations at its inactive waste sites, PNL is developing the risk assessment methodology called RAPS. Use of RAPS will help DOE ensure that those sites posing the highest potential risk are addressed first

Radioactive waste processing method

International Nuclear Information System (INIS)

Kikuchi, Makoto; Kamiya, Kunio; Yusa, Hideo.

1976-01-01

Object: To form radioactive wastes into a pellet-like solid body having high strength. Structure: Liquid waste containing a radioactive material is heated into a powdery body. Granular solid matter such as sand greater in diameter than grain size of the powdery body are mixed into the powdery body, and thereafter the mixture is formed by a granulator into a pellet-like solid body. The thus formed material is introduced into a drum can, into which a thermoplastic material such as asphalt is poured into the can and cooled so that the asphalt is impregnated inside the pellet to obtain a solid having high strength. (Furukawa, Y.)

Processing method for radioactive sludge

International Nuclear Information System (INIS)

Shoji, Yuichi; Kaneko, Masaaki.

1993-01-01

The concentration of radioactive sludges contained in a storage tank is controlled, thereafter, a filter is charged into a processing vessel to continuously conduct dewatering. Then, the radioactive sludges and an oxidizer are mixed by stirring using a stirring impeller and by vibrations using a vibrator. At the same time, thermic rays are irradiated by using infrared ray lamps to heat and decompose them. Since thermic rays reach the center of the radioactive sludges by the infrared ray lamps, ion exchange resins are sufficiently decomposed and carbonized into inorganic material. Then, a filling hardener such as mortar cement having a good flowability is charged to solidify the wastes. With such procedures, radioactive sludges can be stored under a stable condition for a long period of time by decomposing organic materials into inorganic materials and solidifying them. Further, an operator's radiation exposure dose can remarkably be reduced by applying a predetermined and a stabilization treatment in an identical processing vessel. (N.H.)

Surrogate formulations for thermal treatment of low-level mixed waste

International Nuclear Information System (INIS)

Stockdale, J.A.D.; Bostick, W.D.; Hoffmann, D.P.; Lee, H.T.

1994-01-01

The evaluation and comparison of proposed thermal treatment systems for mixed wastes can be expedited by tests in which the radioactive components of the wastes are replaced by surrogate materials chosen to mimic, as far as is possible, the chemical and physical properties of the radioactive materials of concern. In this work, sponsored by the Mixed Waste Integrated Project of the US Department of Energy, the authors have examined reported experience with such surrogates and suggest a simplified standard list of materials for use in tests of thermal treatment systems. The chief radioactive nuclides of concern in the treatment of mixed wastes are 239 Pu, 238 U, 235 U, 137 Cs, 103 Ru, 99 Tc, and 90 Sr. These nuclides are largely by-products of uranium enrichment, reactor fuel reprocessing, and weapons program activities. Cs, Ru, and Sr all have stable isotopes that can be used as perfect surrogates for the radioactive forms. Technetium exists only in radioactive form, as do plutonium and uranium. If one wishes to preclude radioactive contamination of the thermal treatment system under trial burn, surrogate elements must be chosen for these three. For technetium, the authors suggest the use of natural ruthenium, and for both plutonium and uranium, they recommend cerium. The seven radionuclides listed can therefore be simulated by a surrogate package containing stable isotopes of ruthenium, strontium, cesium, and cerium

Conditioning the radioactive oils released from the Cernavoda NPP operation

International Nuclear Information System (INIS)

Popescu, I.; Deneanu, N.; Dulama, M.; Baboiescu, E.

2001-01-01

The radioactive oils released during the Cernavoda NPP operation are lubricating oils used in the primary circuit pumps, hydraulic oils used in the reactor charging machine, as well as, waste turbine oils. The primary cooling circuit is the main way of contamination. This waste contain variable amounts of tritium of activities up to 10 8 Bq/l and relatively small amounts of β/γ emitting radionuclides. The radioactive oils resulting of the heat transport system may contain as much as 1.8 TBq/l of tritium. At INR Pitesti, Department of Radioactive Waste Processing, studies were done concerning the radioactive oils conditioning in concrete. It was found that the minimal compression level required for disposal, of 50 MPa, was exceeded. As consequence, the conditioned waste fulfils the conditions of acceptance provided by the Radioactive Waste National Repository at Baita-Bihor. The main stages of the process are: - dosing the radioactive oil, water and NOFOX9 and NOFOX4 emulsion additives for the 220 l or 80 l barrel; - mixing these ingredients up to reaching the emulsion state; - dosing the cement and lime; - adding the enhancing silicate and shaking the mixture to get a homogeneous matrix; - closing the barrel; - conditioning the 80 l barrel within the 220 l container. The production capacity is of 5 to 8 barrels/shift

Process for recovering xenon from radioactive gaseous wastes

International Nuclear Information System (INIS)

Kishimoto, Tsuneo.

1980-01-01

Purpose: To recover pure xenon economically and efficiently by amply removing radioactive krypton mixed in xenon without changing the rectifying capacity of an xenon rectifying system itself. Method: Xe containing radioactive Kr(Kr-85) is rectified to reduce the concentration of radioactive Kr. Thereafter, non-radioactive Kr or Ar is added to Xe and further the rectification is carried out. The raw material Xe from the Xe adsorption system of, for example, a radioactive gaseous waste disposal system is cooled to about 100 0 C by a heat-exchanger and thereafter supplied to a rectifying tower to carry out normal rectification of Xe thereby to reduce the concentration of Kr contained in Xe at the tower bottom to the rectification limit concentration. Then, non-radioactive Kr is supplied via a precooler to the tower bottom to continue the rectification, thus the Xe fractions at the tower bottom, in which the concentration of radioactive Kr is reduced, being compressed and recovered. (Kamimura, M.)

Comparison of scientific and engineering approaches to the treatment of mixed wastes

International Nuclear Information System (INIS)

Gilbert, K.V.; Bowers, J.S.

1993-12-01

This paper discusses two approaches to the treatment of mixed waste. (Mixed waste, defined as radioactive waste that is co-contaminated with hazardous waste as defined in the Resource Conservation and Conservation Act, is presently stored throughout the United States awaiting the establishment of treatment capability.)The first approach employs conventional engineering that focuses on low risk technology which has been proven in other industries in similar applications and is adaptable for waste treatment use. The term ''low risk'' means that implementation success is relatively certain, and the major uncertainty is the degree of success. Technologies under consideration include centrifugation, evaporation, microfiltration and stabilization. Process offgases are treated with traditional scrubbers and carbon absorption units.For the scientific approach, Lawrence Livermore National Laboratory is in the conceptual design phase of a project to demonstrate incinerator alternatives to destroy organic contaminants in radioactive waste streams without the use of incineration. This Mixed Waste Management Facility will use approximately 15000 square feet of an existing facility to demonstrate an integrated waste management system. Robotic and telerobotic systems will be employed for waste segregation, characterization and feed preparation. Waste feeds will be treated using molten salt oxidation, mediated electrochemical oxidation and wet oxidation. Residues, which can be managed as radioactive-only waste, will be immobilized in an organic matrix prior to shipment to an authorized disposal site

Regulations related to the transport of radioactive material in Brazil

International Nuclear Information System (INIS)

Sahyun, Adelia; Sordi, Gian-Maria A.A.; Sanches, Matias P.

2001-01-01

The transport of radioactive material has raised great interest on the part of national regulatory authorities, thus resulting in a safety measures improvement for all kinds of transportation. The transport of radioactive material is regulated by safety criteria much more than those applied to conventional hazardous material. All radioactive material transportation run in Brazilian territory must be in accordance with what is established by the CNEN-NE 5.01 - Transport of Radioactive Material. There are other national and international regulations for radioactive material transportation, which have to be accomplished with and adopted during the operation of radioactive material transportation. The aim of this paper is to verify the criteria set up in the existing regulations and propose a consensus for all the intervening organizations in the regulation process for land, air or sea transportation. This kind of transportation can not depend on the efforts of only one person, a group of workers or even any governmental body, but must be instead a shared responsibility among workers, transport firms and all regulative transportation organizations. (author)

Regulations related to the transport of radioactive material in Brazil

Energy Technology Data Exchange (ETDEWEB)

Sahyun, Adelia; Sordi, Gian-Maria A.A. [ATOMO Radioprotecao e Seguranca Nuclear, Sao Paulo, SP (Brazil)]. E-mail: atomo@atomo.com.br; Sanches, Matias P. [Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil)]. E-mail: msanches@net.ipen.br

2001-07-01

The transport of radioactive material has raised great interest on the part of national regulatory authorities, thus resulting in a safety measures improvement for all kinds of transportation. The transport of radioactive material is regulated by safety criteria much more than those applied to conventional hazardous material. All radioactive material transportation run in Brazilian territory must be in accordance with what is established by the CNEN-NE 5.01 - Transport of Radioactive Material. There are other national and international regulations for radioactive material transportation, which have to be accomplished with and adopted during the operation of radioactive material transportation. The aim of this paper is to verify the criteria set up in the existing regulations and propose a consensus for all the intervening organizations in the regulation process for land, air or sea transportation. This kind of transportation can not depend on the efforts of only one person, a group of workers or even any governmental body, but must be instead a shared responsibility among workers, transport firms and all regulative transportation organizations. (author)

Assessment of LANL solid low-level mixed waste documentation

International Nuclear Information System (INIS)

Jennrich, E.A.; Lund, D.M.; Davis, K.D.; Hoevemeyer, S.S.

1991-04-01

DOE Order 5820.2A requires that a system performance assessment be conducted to assure efficient and compliant management of all radioactive waste. The objective of this report is to determine the present status of the Radioactive Waste Operations Section and the Chemical Waste Operations Section capabilities regarding preparation and maintenance of appropriate criteria, plans, and procedures. Additionally, a comparison is made which identifies areas where these documents are not presently in existence or being fully implemented. The documents being assessed in this report are: Solid Low-Level Mixed Waste Acceptance Criteria, Solid Low-Level Mixed Waste Characterization Plan, Solid Low-Level Mixed waste Certification Plan, Solid Low-Level Mixed Waste Acceptance Procedures, Solid Low-Level Mixed Waste characterization Procedures, Solid Low-Level Mixed Waste Certification Procedures, Solid Low-Level Mixed Waste Training Procedures, and Solid Low-Level Mixed Waste Recordkeeping Requirements. This report compares the current status of preparation and implementation, by the Radioactive Waste Operations Section and the Chemical Waste Operations Section, of these documents to the requirements of DOE 5820.2A,. 40 CFR 260 to 270, and to recommended practice. Chapters 2 through 9 of the report presents the results of the comparison in tabular form for each of the documents being assessed, followed by narrative discussion of all areas which are perceived to be unsatisfactory or out of compliance with respect to the availability and content of the documents. The final subpart of each of the following chapters provides recommendations where documentation practices may be improved to achieve compliance or to follow the recommended practice

Improvement of uncertainty relations for mixed states

International Nuclear Information System (INIS)

Park, Yong Moon

2005-01-01

We study a possible improvement of uncertainty relations. The Heisenberg uncertainty relation employs commutator of a pair of conjugate observables to set the limit of quantum measurement of the observables. The Schroedinger uncertainty relation improves the Heisenberg uncertainty relation by adding the correlation in terms of anti-commutator. However both relations are insensitive whether the state used is pure or mixed. We improve the uncertainty relations by introducing additional terms which measure the mixtureness of the state. For the momentum and position operators as conjugate observables and for the thermal state of quantum harmonic oscillator, it turns out that the equalities in the improved uncertainty relations hold

Radioactive waste management solutions

International Nuclear Information System (INIS)

Siemann, Michael

2015-01-01

One of the more frequent questions that arise when discussing nuclear energy's potential contribution to mitigating climate change concerns that of how to manage radioactive waste. Radioactive waste is produced through nuclear power generation, but also - although to a significantly lesser extent - in a variety of other sectors including medicine, agriculture, research, industry and education. The amount, type and physical form of radioactive waste varies considerably. Some forms of radioactive waste, for example, need only be stored for a relatively short period while their radioactivity naturally decays to safe levels. Others remain radioactive for hundreds or even hundreds of thousands of years. Public concerns surrounding radioactive waste are largely related to long-lived high-level radioactive waste. Countries around the world with existing nuclear programmes are developing longer-term plans for final disposal of such waste, with an international consensus developing that the geological disposal of high-level waste (HLW) is the most technically feasible and safe solution. This article provides a brief overview of the different forms of radioactive waste, examines storage and disposal solutions, and briefly explores fuel recycling and stakeholder involvement in radioactive waste management decision making

Relation between local landform and radioactive geopollution. Part 2

International Nuclear Information System (INIS)

Kimura, Kazuya; Nirei, Hisashi; Nakadai, Hiroki; Hiyama, Tomoyo; Yoshida, Takeshi

2013-01-01

A lot of radioactive materials were emitted by the Fukushima Daiichi nuclear disaster in March, 2011. Those of them; Cs-134 and Cs-137 have comparatively long half-life have cause the radioactivity geo pollution in the east Japan. In fact, it is not explained completely how to spread, move and absorb cesium. However, it seems that there is a certain law of nature. That is to say, we should measure radioactive materials according to the law of generation (decay), movement, deposition and take necessary actions under the Katori-Narita-Itako Declaration of IUGS GEM (IUGS-GEM, 2011). We followed this declaration and have continued measurement by use of RT-30 (made by GEORADIS). And it becomes clear that radioactivity geo pollution is strongly subject to the influence of land form, in the result carrying out diffusion and movement. In addition to the new data, this paper shows detail examples. (author)

Radioactive waste management in West Germany

Energy Technology Data Exchange (ETDEWEB)

Krause, H [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.)

1978-01-01

The technologies developed in West Germany for radioactive waste management are widely reviewed. The first topic in this review paper is the disposal of low- and middle-level radioactive liquid wastes. Almost all these liquid wastes are evaporated, and the typical decontamination factor attained is 10/sup 4/ -- 10/sup 6/. The second topic is the solidification of residuals. Short explanation is given to bituminization and some new processes. The third topic is high-level liquid wastes. Degradation of glass quality due to various radiation is discussed. Embedding of small glass particles containing radioactive wastes into metal is also explained. Disposals of low-level solid wastes and the special wastes produced from reprocessing and mixed oxide fuel fabrication are explained. Final disposal of radioactive wastes in halite is discussed as the last topic. Many photographs are used to illustrate the industrial or experimental use of those management methods.

Plastic solidification method for radioactive waste

International Nuclear Information System (INIS)

Tomita, Toshihide; Inakuma, Masahiko.

1992-01-01

Condensed liquid wastes in radioactive wastes are formed by mixing and condensing several kinds of liquid wastes such as liquid wastes upon regeneration of ion exchange resins, floor draining liquid wastes and equipment draining liquid wastes. Accordingly, various materials are contained, and it is found that polymerization reaction of plastics is inhibited especially when reductive material, such as sodium nitrite is present. Then, in the present invention, upon mixing thermosetting resins to radioactive wastes containing reducing materials, an alkaline material is admixed to an unstaturated polyester resin. This can inactivate the terminal groups of unsaturated polyester chain, to prevent the dissociation of the reducing agent such as sodium nitrite. Further, if an unsaturated polyester resin of low acid value and a polymerization initiator for high temperature are used in addition to the alkaline material, the effect is further enhanced, thereby enabling to obtain a strong plastic solidification products. (T.M.)

Relative entropy, mixed gauge-gravitational anomaly and causality

Energy Technology Data Exchange (ETDEWEB)

Bhattacharyya, Arpan [Department of Physics and Center for Field Theory and Particle Physics, Fudan University,220 Handan Road, 200433 Shanghai (China); Centre For High Energy Phsyics, Indian Institute of Science,560012 Bangalore (India); Cheng, Long [Department of Physics and Center for Field Theory and Particle Physics, Fudan University,220 Handan Road, 200433 Shanghai (China); Hung, Ling-Yan [Department of Physics and Center for Field Theory and Particle Physics, Fudan University,220 Handan Road, 200433 Shanghai (China); Collaborative Innovation Center of Advanced Microstructures, Fudan University,220 Handan Road, 200433 Shanghai (China)

2016-07-25

In this note we explored the holographic relative entropy in the presence of the 5d Chern-Simons term, which introduces a mixed gauge-gravity anomaly to the dual CFT. The theory trivially satisfies an entanglement first law. However, to quadratic order in perturbations of the stress tensor T and current density J, there is a mixed contribution to the relative entropy bi-linear in T and J, signalling a potential violation of the positivity of the relative entropy. Miraculously, the term vanishes up to linear order in a derivative expansion. This prompted a closer inspection on a different consistency check, that involves time-delay of a graviton propagating in a charged background, scattered via a coupling supplied by the Chern-Simons term. The analysis suggests that the time-delay can take either sign, potentially violating causality for any finite value of the CS coupling.

Biological treatment of concentrated hazardous, toxic, andradionuclide mixed wastes without dilution

Energy Technology Data Exchange (ETDEWEB)

Stringfellow, William T.; Komada, Tatsuyuki; Chang, Li-Yang

2004-06-15

Approximately 10 percent of all radioactive wastes produced in the U. S. are mixed with hazardous or toxic chemicals and therefore can not be placed in secure land disposal facilities. Mixed wastes containing hazardous organic chemicals are often incinerated, but volatile radioactive elements are released directly into the biosphere. Some mixed wastes do not currently have any identified disposal option and are stored locally awaiting new developments. Biological treatment has been proposed as a potentially safer alternative to incineration for the treatment of hazardous organic mixed wastes, since biological treatment would not release volatile radioisotopes and the residual low-level radioactive waste would no longer be restricted from land disposal. Prior studies have shown that toxicity associated with acetonitrile is a significant limiting factor for the application of biotreatment to mixed wastes and excessive dilution was required to avoid inhibition of biological treatment. In this study, we demonstrate that a novel reactor configuration, where the concentrated toxic waste is drip-fed into a complete-mix bioreactor containing a pre-concentrated active microbial population, can be used to treat a surrogate acetonitrile mixed waste stream without excessive dilution. Using a drip-feed bioreactor, we were able to treat a 90,000 mg/L acetonitrile solution to less than 0.1 mg/L final concentration using a dilution factor of only 3.4. It was determined that the acetonitrile degradation reaction was inhibited at a pH above 7.2 and that the reactor could be modeled using conventional kinetic and mass balance approaches. Using a drip-feed reactor configuration addresses a major limiting factor (toxic inhibition) for the biological treatment of toxic, hazardous, or radioactive mixed wastes and suggests that drip-feed bioreactors could be used to treat other concentrated toxic waste streams, such as chemical warfare materiel.

Processing method of radiation concrete waste and manufacturing method for radioactive waste solidifying filling mortar

International Nuclear Information System (INIS)

Sukekiyo, Mitsuaki; Okamoto, Masamichi

1998-01-01

Radioactive concrete wastes are crushed and pulverized. Fine solid granular materials caused by the pulverization are classified and the grain size is controlled so that the maximum grain size is 2.5mm, with the grains having a grain size of up to 0.15mm being up to 30% by weight to form fine aggregates. Separated and recovered fine concrete powders are classified and the size of the powder is controlled within a range of from 3,000 to 15,000cm 2 /g which is smaller than cement particles to form fine powders having a stable quality suitable as a mixing agent. The fine aggregates and the mixing agent are mixed to form a filling mortar (filler) for solidifying radioactive wastes. The filling mortar is filled together with other radioactive wastes in a drum to form a waste body in a drum. With such a constitution, crushed radioactive concrete wastes can be reutilized completely. (I.N.)

Summary of BNL studies regarding commercial mixed waste

International Nuclear Information System (INIS)

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

1986-09-01

Based on BNL's study it was concluded that there are low-level radioactive wastes (LLWs) which contain chemically hazardous components. Scintillation liquids may be considered an EPA listed hazardous waste and are, therefore, potential mixed wastes. Since November 1985, no operating LLW disposal site will accept these wastes for disposal. Unless such wastes contain de minimis quantities of radionuclides, they cannot be disposed of at an EPA permitted site. Currently generators of liquid scintillation wastes can ship de minimis wastes to be burned at commercial facilities. Oil wastes may also eventually be an EPA listed waste and thus will have to be considered a potential radioactive mixed waste unless NRC establishes de minimis levels of radionuclides below which oils can be managed as hazardous wastes. Regarding wastes containing lead metal there is some question as to the extent of the hazard posed by lead disposed in a LLW burial trench. Chromium-containing wastes would have to be tested to determine whether they are potential mixed wastes. There may be other wastes that are mixed wastes; the responsibility for determining this rests with the waste generator. While management options for handling potential mixed wastes are available, there is limited regulatory guidance for generators. BNL has identified and evaluated a variety of treatment options for the management of potential radioactive mixed wastes. The findings of that study showed that application of a management option with the purpose of addressing EPA concerns can, at the same time, address stabilization and volume reduction concerns of NRC. 6 refs., 1 tab

Mixed and Low-Level Treatment Facility Project. Appendix B, Waste stream engineering files, Part 1, Mixed waste streams

Energy Technology Data Exchange (ETDEWEB)

1992-04-01

This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided.

Plasma Hearth Process vitrification of DOE low-level mixed waste

International Nuclear Information System (INIS)

Gillins, R.L.; Geimer, R.M.

1995-01-01

The Plasma Hearth Process (PHP) demonstration project is one of the key technology projects in the Department of Energy (DOE) Office of Technology Development Mixed Waste Focus Area. The PHP is recognized as one of the more promising solutions to DOE's mixed waste treatment needs, with potential application in the treatment of a wide variety of DOE mixed wastes. The PHP is a high temperature vitrification process using a plasma arc torch in a stationary, refractory lined chamber that destroys organics and stabilizes the residuals in a nonleaching, vitrified waste form. This technology will be equally applicable to low-level mixed wastes generated by nuclear utilities. The final waste form will be volume reduced to the maximum extent practical, because all organics will have been destroyed and the inorganics will be in a high-density, low void-space form and little or no volume-increasing glass makers will have been added. Low volume and high integrity waste forms result in low disposal costs. This project is structured to ensure that the plasma technology can be successfully employed in radioactive service. The PHP technology will be developed into a production system through a sequence of tests on several test units, both non-radioactive and radioactive. As the final step, a prototype PHP system will be constructed for full-scale radioactive waste treatment demonstration

Lessons learned from radioactive/mixed waste analyses at EG ampersand G Idaho, Inc

International Nuclear Information System (INIS)

Murphy, R.J.; Sailer, S.J.; Bennett, J.T.; Arvizu, J.S.

1990-01-01

For the past 30 years extensive chemical characterizations of environmental and waste samples have been performed by numerous academic, commercial, and government analytical chemistry laboratories for the purposes of research, monitoring, and compliance with regulations. The vast majority of these analyses, however, has been conducted on samples containing natural concentrations of radioactive constituents. It is only within the last decade that a small number of laboratories have been conducting extensive chemical characterizations of highly radioactive samples and consequently have begun to identify many special requirements for the safe and accurate conduct of such analyses. Experience gained from chemical analyses of radioactively contaminated samples has indicated special requirements and actions needed in the following three general areas: Sample collection and preservation; chemical analysis protocols; disposal of waste from chemical analyses. In this paper we will summarize the experience and findings acquired from four years of radioactive sample analyses by the Environmental Chemistry Unit, an analytical chemistry laboratory of EG ampersand G Idaho, Inc. at the Idaho National Engineering Laboratory. 6 tabs

System for disposing of radioactive waste

International Nuclear Information System (INIS)

Gablin, K.A.; Hansen, L.J.

1980-01-01

A system is disclosed for disposing of radioactive mixed liquid and particulate waste material from nuclear reactors by solidifying the liquid components into a free standing hardened mass with a syrup of partially polymerized particles of urea formaldehyde in water and a liquid curing agent

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

Science.gov (United States)

2013-02-11

... NUCLEAR REGULATORY COMMISSION Request To Amend A License To Import; Radioactive Waste Pursuant to... Country from application no.; docket no. Diversified Scientific Class A radioactive Up to 378,000 Volume reduction...... Canada Services, Inc.; January 10, mixed waste kilograms. Amend to: (1) add four 2013...

Method of treating radioactive waste waters from uranium industry

International Nuclear Information System (INIS)

Priban, V.; Novak, L.; Zubcek, L.; Hinterholzinger, O.

1987-01-01

radioactive mine waters with suspended solid particles and acid salinated solutions from the process of underground leaching of radioactive ores with sulfuric acid, are discharged in a specified ratio to a common sump. The acid salinated solutions are used as a coagulation agent for the treatment of radioactive mine waters. Both solutions are mixed at simultaneous addition of lime milk suspension. In a sedimentation tank, the precipitate thus produced is sedimented and the clarified water is carried from the tank to a public water flow. The advantages of the method include the treatment of an over-balance 3 m 3 /min of acid salinated solutions from the process of underground leaching of radioactive ores with sulfuric acid, and reduction in the cost of radioactive mine water treatment. (E.S.)

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

International Nuclear Information System (INIS)

1993-06-01

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

Treatment of radioactive sludge

International Nuclear Information System (INIS)

Allison, W.; Payne, B.J.; Pegler, G.E.

1979-01-01

Radioactive sludge e.g. that which may accumulate in irradiated nuclear fuel element storage ponds, is treated by pumping it from a settling tank to a particle separator, conveniently a hydrocyclone and a sloping plate separator, the liquid being returned to the settling tank and the solids being metered into a drum pre-lined with dry cement. The drums are in a containment box in which they are transferred to a mixing station where the particles and cement are mixed and thence to a curing station. After curing the drums are embedded in cement in outer containers for transport to a long-term storage site. (author)

Natural radioactivity of Loire river sediments: relations with the lithology

International Nuclear Information System (INIS)

Patryl, L.

2000-01-01

This study has been carried out on request of the Loire-Bretagne water agency by the Laboratory of geology of Tours univ. (EA2100 GeEAC) in collaboration with CEA-Le Ripault. The main objective was the study of the nature and distribution of natural radioactivity in the Loire river alluvial deposits, its origin in the rocks of the surrounding basins and its links with the alluvial petrography. The radioactive flux linked with the sediments of the bottom of the river has been also determined. The Loire river and its main affluents have been the object of radiological and petrographic analyses (grain size, sands and clays mineralogy, organic matter content). The average radioactivities of 40 K, 238 U and 228 Ac in the alluvial deposits are 934.3 ± 164.7 Bq.kg -1 , 50.6 ± 30.8 Bq.kg -1 and 28.8 ± 18.1 Bq.kg -1 , respectively. The average radioactivity of 238 U, 228 Ac and their daughter products is statistically higher in Loire superieure (Massif Central mounts) than in Loire moyenne (Paris basin). The activities of 238 U and 228 Ac are mainly influenced by the grain size of the alluvial deposits and by the mineralogical composition of the sand fraction. The alluvial deposits are mainly sandy and the coarse fraction is the most abundant. The primary radioactivity is carried by the few zircons of the sediments. The activity of the uranium and thorium families increase with the feldspars content. The fixation of radioactivity seems to be linked with the presence of clay minerals inside the weathered feldspar grains which are abundant in the sands. The radioactivity of the Loire river alluvial deposits shows no important changes with respect to the substratums because of a smoothing due to the predominance of longitudinal fluxes with respect to the lateral ones. The impact of an old uranium mine on the alluvial deposits of the Besbre river is detectable along about a tenth of km s downstream only. Because of the strong variations of radioactivity with granularity, a

Mixed and Low-Level Treatment Facility Project

Energy Technology Data Exchange (ETDEWEB)

1992-04-01

This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided.

Mixed and Low-Level Treatment Facility Project

International Nuclear Information System (INIS)

1992-04-01

This appendix contains the mixed and low-level waste engineering design files (EDFS) documenting each low-level and mixed waste stream investigated during preengineering studies for Mixed and Low-Level Waste Treatment Facility Project. The EDFs provide background information on mixed and low-level waste generated at the Idaho National Engineering Laboratory. They identify, characterize, and provide treatment strategies for the waste streams. Mixed waste is waste containing both radioactive and hazardous components as defined by the Atomic Energy Act and the Resource Conservation and Recovery Act, respectively. Low-level waste is waste that contains radioactivity and is not classified as high-level waste, transuranic waste, spent nuclear fuel, or 11e(2) byproduct material as defined by DOE 5820.2A. Test specimens of fissionable material irradiated for research and development only, and not for the production of power or plutonium, may be classified as low-level waste, provided the concentration of transuranic is less than 100 nCi/g. This appendix is a tool that clarifies presentation format for the EDFS. The EDFs contain waste stream characterization data and potential treatment strategies that will facilitate system tradeoff studies and conceptual design development. A total of 43 mixed waste and 55 low-level waste EDFs are provided

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

International Nuclear Information System (INIS)

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

1999-01-01

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

Environmental assessment: Solid waste retrieval complex, enhanced radioactive and mixed waste storage facility, infrastructure upgrades, and central waste support complex, Hanford Site, Richland, Washington

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The U.S. Department of Energy (DOE) needs to take action to: retrieve transuranic (TRU) waste because interim storage waste containers have exceeded their 20-year design life and could fail causing a radioactive release to the environment provide storage capacity for retrieved and newly generated TRU, Greater-than-Category 3 (GTC3), and mixed waste before treatment and/or shipment to the Waste Isolation Pilot Project (WIPP); and upgrade the infrastructure network in the 200 West Area to enhance operational efficiencies and reduce the cost of operating the Solid Waste Operations Complex. This proposed action would initiate the retrieval activities (Retrieval) from Trench 4C-T04 in the 200 West Area including the construction of support facilities necessary to carry out the retrieval operations. In addition, the proposed action includes the construction and operation of a facility (Enhanced Radioactive Mixed Waste Storage Facility) in the 200 West Area to store newly generated and the retrieved waste while it awaits shipment to a final disposal site. Also, Infrastructure Upgrades and a Central Waste Support Complex are necessary to support the Hanford Site`s centralized waste management area in the 200 West Area. The proposed action also includes mitigation for the loss of priority shrub-steppe habitat resulting from construction. The estimated total cost of the proposed action is $66 million.

Environmental assessment: Solid waste retrieval complex, enhanced radioactive and mixed waste storage facility, infrastructure upgrades, and central waste support complex, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1995-09-01

The U.S. Department of Energy (DOE) needs to take action to: retrieve transuranic (TRU) waste because interim storage waste containers have exceeded their 20-year design life and could fail causing a radioactive release to the environment provide storage capacity for retrieved and newly generated TRU, Greater-than-Category 3 (GTC3), and mixed waste before treatment and/or shipment to the Waste Isolation Pilot Project (WIPP); and upgrade the infrastructure network in the 200 West Area to enhance operational efficiencies and reduce the cost of operating the Solid Waste Operations Complex. This proposed action would initiate the retrieval activities (Retrieval) from Trench 4C-T04 in the 200 West Area including the construction of support facilities necessary to carry out the retrieval operations. In addition, the proposed action includes the construction and operation of a facility (Enhanced Radioactive Mixed Waste Storage Facility) in the 200 West Area to store newly generated and the retrieved waste while it awaits shipment to a final disposal site. Also, Infrastructure Upgrades and a Central Waste Support Complex are necessary to support the Hanford Site's centralized waste management area in the 200 West Area. The proposed action also includes mitigation for the loss of priority shrub-steppe habitat resulting from construction. The estimated total cost of the proposed action is $66 million

OSMOTIC COEFFICIENTS, SOLUBILITIES, AND DELIQUESCENCE RELATIONS IN MIXED AQUEOUS SALT SOLUTIONS AT ELEVATED TEMPERATURE

International Nuclear Information System (INIS)

M.S. Gruszkiewicz; D.A. Palmer

2006-01-01

While thermodynamic properties of pure aqueous electrolytes are relatively well known at ambient temperature, there are far fewer data for binary systems extending to elevated temperatures and high concentrations. There is no general theoretically sound basis for prediction of the temperature dependence of ionic activities, and consequently temperature extrapolations based on ambient temperature data and empirical equations are uncertain and require empirical verification. Thermodynamic properties of mixed brines in a wide range of concentrations would enhance the understanding and precise modeling of the effects of deliquescence of initially dry solids in humid air in geological environments and in modeling the composition of waters during heating, cooling, evaporation or condensation processes. These conditions are of interest in the analysis of waters on metal surfaces at the proposed radioactive waste repository at Yucca Mountain, Nevada. The results obtained in this project will be useful for modeling the long-term evolution of the chemical environment, and this in turn is useful for the analysis of the corrosion of waste packages. In particular, there are few reliable experimental data available on the relationship between relative humidity and composition that reveals the eutonic points of the mixtures and the mixture deliquescence RH. The deliquescence RH for multicomponent mixtures is lower than that of pure component or binary solutions, but is not easy to predict quantitatively since the solutions are highly nonideal. In this work we used the ORNL low-temperature and high-temperature isopiestic facilities, capable of precise measurements of vapor pressure between ambient temperature and 250 C for determination of not only osmotic coefficients, but also solubilities and deliquescence points of aqueous mixed solutions in a range of temperatures. In addition to standard solutions of CaCl 2 , LiCl, and NaCl used as references, precise direct

Molten salt destruction process for mixed wastes

International Nuclear Information System (INIS)

Upadhye, R.S.; Wilder, J.G.; Karlsen, C.E.

1993-04-01

We are developing an advanced two-stage process for the treatment of mixed wastes, which contain both hazardous and radioactive components. The wastes, together with an oxidant gas, such as air, are injected into a bed of molten salt comprising a mixture of sodium-, potassium-, and lithium-carbonates, with a melting point of about 580 degree C. The organic constituents of the mixed waste are destroyed through the combined effect of pyrolysis and oxidation. Heteroatoms. such as chlorine, in the mixed waste form stable salts, such as sodium chloride, and are retained in the melt. The radioactive actinides in the mixed waste are also retained in the melt because of the combined action of wetting and partial dissolution. The original process, consists of a one-stage unit, operated at 900--1000 degree C. The advanced two-stage process has two stages, one for pyrolysis and one for oxidation. The pyrolysis stage is designed to operate at 700 degree C. The oxidation stage can be operated at a higher temperature, if necessary

Radioactivity in the environment

International Nuclear Information System (INIS)

2011-01-01

Illustrated by drawings, this publication briefly describes radioactive exposure modalities (external or internal irradiation), the ways they are measured and assessed (doses, units), the different natural radioactivity origins, the different radioactivity origins related to human activity, the share of each origin in population exposures

Radioactivity of tobacco

International Nuclear Information System (INIS)

Nashawati, A.; Al-Dalal, Z.; Al-Akel, B.; Al-Masri, M. S.

2002-04-01

This report shows the results of studies related to radioactivity in tobacco and its pathways to human being. Tobacco contains high concentrations of natural radioactive materials especially polonium 210 and lead 210, which may reach a value of 27 mBq/g. The amount of polonium 210 in tobacco is related to the concentration of radon (the main source of polonium 210 in the agricultural areas) in addition to the over use of phosphate fertilizers for tobacco plantation. Radioactive materials present in tobacco enter the human body through smoking where 210 Po concentrates in the Alveolar lung; this may cause health risks including lung cancer. In addition, radiation doses due to smoking have been reported and some results of the studies carried out for radioactivity in tobacco at the Syrian Atomic Energy Commission. (author)

VAC*TRAX - thermal desorption for mixed wastes

Energy Technology Data Exchange (ETDEWEB)

McElwee, M.J.; Palmer, C.R. [RUST-Clemson Technical Center, Anderson, SC (United States)

1995-10-01

The patented VAC*TRAX process was designed in response to the need to remove organic constituents from mixed waste, waste that contains both a hazardous (RCRA or TSCA regulated) component and a radioactive component. Separation of the mixed waste into its hazardous and radioactive components allows for ultimate disposal of the material at existing, permitted facilities. The VAC*TRAX technology consists of a jacketed vacuum dryer followed by a condensing train. Solids are placed in the dryer and indirectly heated to temperatures as high as 2600{degrees}C, while a strong vacuum (down to 50 mm Hg absolute pressure) is applied to the system and the dryer is purged with a nitrogen carrier gas. The organic contaminants in the solids are thermally desorbed, swept up in the carrier gas and into the condensing train where they are cooled and recovered. The dryer is fitted with a filtration system that keeps the radioactive constituents from migrating to the condensate. As such, the waste is separated into hazardous liquid and radioactive solid components, allowing for disposal of these streams at a permitted incinerator or a radioactive materials landfill, respectively. The VAC*TRAX system is designed to be highly mobile, while minimizing the operational costs with a simple, robust process. These factors allow for treatment of small waste streams at a reasonable cost.

Integrated Data Base for 1992: US spent fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1992-10-01

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1991. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal

Sodalite-type radioactive waste solidification product and method of synthesizing the same

International Nuclear Information System (INIS)

Koyama, Masashi; Yoshida, Takumasa.

1995-01-01

Radioactive waste solidification products formed by solidifying radioactive wastes comprising halides such as chlorides of alkali metal elements, alkaline earth metal elements, rare earth elements, noble metal elements generated upon dry-type reprocessing of nuclear fuels and separation of dry-type high level liquid wastes, are solidified to stable products by incorporating radioactive wastes in the form of halides into a cavity of sodalite condensation cage of aluminosilicates having three dimensional skeleton structure. Alternatively, NaOH, Al 2 O 3 , SiO 2 are mixed and heated to 600 to 900degC to form an intermediate reaction products, and then the reaction products are mixed with the halides and heated to form sodalite-type radioactive water solidification products. Thus, the halides in fission products can be held by the three dimensional skeleton structure similar with that of sodalite which is a sort of natural minerals containing chlorides, thereby enabling to solidify them stably. (N.H.)

VAC*TRAX - Thermal desorption for mixed wastes

International Nuclear Information System (INIS)

McElwee, M.J.; Palmer, C.R.

1995-01-01

The patented VAC*TRAX process was designed in response to the need to remove organic constituents from mixed waste, waste that contains both a hazardous (RCRA or TSCA regulated) component and a radioactive component. Separation of the mixed waste into its hazardous and radioactive components allows for ultimate disposal of the material at existing, permitted facilities. The VAC*TRAX technology consists of a jacketed vacuum dryer followed by a condensing train. Solids are placed in the dryer and indirectly heated to temperatures as high as 260 degrees C, while a strong vacuum (down to 50 mm Hg absolute pressure) is applied to the system and the dryer is purged with a nitrogen carrier gas. The organic contaminants in the solids are thermally desorbed, swept up in the carrier gas and into the condensing train where they are cooled and recovered. The dryer is fitted with a filtration system that keeps the radioactive constituents from migrating to the condensate. As such, the waste is separated into hazardous liquid and radioactive solid components, allowing for disposal of these streams at a permitted incinerator or a radioactive materials landfill, respectively. The VAC*TRAX system is designed to be highly mobile, while minimizing the operational costs with a simple, robust process. These factors allow for treatment of small waste streams at a reasonable cost. This paper describes the VAC*TRAX thermal desorption process, as well as results from the pilot testing program. Also, the design and application of the full-scale treatment system is presented. Materials tested to date include spiked soil and debris, power plant trash and sludge contaminated with solvents, PCB contaminated soil, solvent-contaminated uranium mill-tailings, and solvent and PCB-contaminated sludge and trash. Over 70 test runs have been performed using the pilot VAC*TRAX system, with more than 80% of the tests using mixed waste as the feed material

Mathematical modelling of transport phenomena in radioactive waste-cement-bentonite matrix

International Nuclear Information System (INIS)

Plecas, Ilija; Dimovic, Slavko

2010-01-01

the volume of the waste (e.g. by incineration or compaction); solidifying non-solid wastes to make them physically stable, and packaging the waste to isolate it from the environment. Ion exchange resins may be used most successfully for the removal of radioactive and stable ions from dilute solutions. Ion exchange resins are polymers with cross-linking (connections between long carbon chains in a polymer). The resin has active groups in the form of electrically charged sites. At these sites ions of opposite charge are attracted but may be replaced by other ions depending on their relative concentrations and affinities for the sites. Spent mix bead exchange resins containing 60 Co and 137 Cs, represent a major portion of the solid radioactive waste in nuclear technology. Cement is used as a solidification material for the storage of intermediate-level radioactive waste. However, the retention of cesium, in the cement matrix is negligible. The sorption of cesium on cement is low and diffusivity of cesium in the hydrated cement is high. Only when the cement is mixed with a material having a significant sorption capacity, normally bead or powdered ion exchange resins, is the leachability of cesium and cobalt from the cement matrix low enough to be acceptable. Although cement has several unfavorable characteristics as a solidifying material, i.e. low volume reduction and relatively high leachability, it possesses many practical advantages: good mechanical characteristics, low cost, easy operation and radiation and thermal stability. It is generally assumed that the cement leachability of 137 Cs and other radionuclides can be reduced by adding minerals like bentonite, vermiculite and zeolite. At the 'Vinca' Institute of Nuclear Sciences, a promising composite for the solidification of radioactive wastes has been developed. Leaching of 137 Cs from this material was studied using the method recommended by the IAEA. (authors)

System for disposing of radioactive waste

International Nuclear Information System (INIS)

Gablin, K.A.; Hansen, L.J.

1979-01-01

A system is described for disposing of radioactive waste material from nuclear reactors by solidifying the liquid components to produce an encapsulated mass adapted for disposal by burial. The method contemplates mixing of radioactive waste materials, with or without contained solids, with a setting agent capable of solidifying the waste liquids into a free standing hardened mass, placing the resulting liquid mixture in a container with a proportionate amount of a curing agent to effect solidification under controlled conditions, and thereafter burying the container and contained solidified mixture. The setting agent is a water-extendable polymer consisting of a suspension of partially polymerized particles of urea formaldehyde in water, and the curing agent is sodium bisulfate. Methods are disclosed for dewatering slurry-like mixtures of liquid and particulate radioactive waste materials, such as spent ion exchange resin beads, and for effecting desired distribution of non-liquid radioactive materials in the central area of the container prior to solidification, so that the surrounding mass of lower specific radioactivity acts as a partial shield against higher radioactivity of the non-liquid radioactive materials. The methods also provide for addition of non-radioactive filler materials to dilute the mixture and lower the overall radioactivity of the hardened mixture to desired Lowest Specific Activity counts. An inhibiting agent is added to the liquid mixture to adjust the solidification time, and provision is made for adding additional amounts of setting agent and curing agent to take up any free water and further encapsulate the hardened material within the container. 30 claims

System for disposing of radioactive waste

International Nuclear Information System (INIS)

Gablin, K.A.; Hansen, L.J.

1977-01-01

A system is described for disposing of radioactive waste material from nuclear reactors by solidifying the liquid components to produce an encapsulated mass adapted for disposal by burial. The method contemplates mixing of radioactive waste materials, with or without contained solids, with a setting agent capable of solidifying the waste liquids into a free standing hardened mass, placing the resulting liquid mixture in a container with a proportionate amount of a curing agent to effect solidification under controlled conditions, and thereafter burying the container and contained solidified mixture. The setting agent is a water-extendable polymer consisting of a suspension of partially polymerized particles of urea formaldehyde in water, and the curing agent is sodium bisulfate. Methods are disclosed for dewatering slurry-like mixtures of liquid and particulate radioactive waste materials, such as spent ion exchange resin beads, and for effecting desired distribution of non-liquid radioactive materials in the central area of the container prior to solidification, so that the surrounding mass of lower specific radioactivity acts as a partial shield against higher radioactivity of the non-liquid radioactive materials. The methods also provide for addition of non-radioactive filler materials to dilute the mixture and lower the overall radioactivity of the hardened mixture to desired Lowest Specific Activity counts. An inhibiting agent is added to the liquid mixture to adjust the solidification time, and provision is made for adding additional amounts of setting agent and curing agent to take up any free water and further encapsulate the hardened material within the container

Biological treatment of concentrated hazardous, toxic, and radionuclide mixed wastes without dilution

International Nuclear Information System (INIS)

Stringfellow, William T.; Komada, Tatsuyuki; Chang, Li-Yang

2004-01-01

Approximately 10 percent of all radioactive wastes produced in the U. S. are mixed with hazardous or toxic chemicals and therefore can not be placed in secure land disposal facilities. Mixed wastes containing hazardous organic chemicals are often incinerated, but volatile radioactive elements are released directly into the biosphere. Some mixed wastes do not currently have any identified disposal option and are stored locally awaiting new developments. Biological treatment has been proposed as a potentially safer alternative to incineration for the treatment of hazardous organic mixed wastes, since biological treatment would not release volatile radioisotopes and the residual low-level radioactive waste would no longer be restricted from land disposal. Prior studies have shown that toxicity associated with acetonitrile is a significant limiting factor for the application of biotreatment to mixed wastes and excessive dilution was required to avoid inhibition of biological treatment. In this study, we demonstrate that a novel reactor configuration, where the concentrated toxic waste is drip-fed into a complete-mix bioreactor containing a pre-concentrated active microbial population, can be used to treat a surrogate acetonitrile mixed waste stream without excessive dilution. Using a drip-feed bioreactor, we were able to treat a 90,000 mg/L acetonitrile solution to less than 0.1 mg/L final concentration using a dilution factor of only 3.4. It was determined that the acetonitrile degradation reaction was inhibited at a pH above 7.2 and that the reactor could be modeled using conventional kinetic and mass balance approaches. Using a drip-feed reactor configuration addresses a major limiting factor (toxic inhibition) for the biological treatment of toxic, hazardous, or radioactive mixed wastes and suggests that drip-feed bioreactors could be used to treat other concentrated toxic waste streams, such as chemical warfare materiel

The NEA research and environmental surveillance programme related to sea disposal of low-level radioactive waste

Science.gov (United States)

Rugger, B.; Templeton, W. L.; Gurbutt, P.

1983-05-01

Sea dumping operations of certain types of packaged low and medium level radioactive wastes have been carried out since 1967 in the North-East Atlantic under the auspices of the OECD Nuclear Energy Agency. On the occasion of the 1980 review of the continued suitability of the North-East Atlantic site used for the disposal of radioactive waste, it was recommended that an effort should be made to increase the scientific data base relating to the oceanographic and biological characteristics of the dumping area. In particular, it was suggested that a site specific model of the transfer of radionuclides in the marine environment be developed, which would permit a better assessment of the potential radiation doses to man from the dumping of radioactive waste. To fulfill these objectives a research and environmental surveillance program related to sea disposal of radioactive waste was set up in 1981 with the participation of thirteen Member countries and the International Laboratory for Marine Radioactivity of the IAEA in Monaco. The research program is focused on five research areas which are directly relevant to the preparation of more site specific assessments in the future. They are: model development; physical oceanography; geochemistry; biology; and radiological surveillance. Promising results have already been obtained and more are anticipated in the not too distant future. An interim description of the NEA dumping site has been prepared which provides an excellent data base for this area.

Majorization uncertainty relations for mixed quantum states

Science.gov (United States)

Puchała, Zbigniew; Rudnicki, Łukasz; Krawiec, Aleksandra; Życzkowski, Karol

2018-04-01

Majorization uncertainty relations are generalized for an arbitrary mixed quantum state ρ of a finite size N. In particular, a lower bound for the sum of two entropies characterizing the probability distributions corresponding to measurements with respect to two arbitrary orthogonal bases is derived in terms of the spectrum of ρ and the entries of a unitary matrix U relating both bases. The results obtained can also be formulated for two measurements performed on a single subsystem of a bipartite system described by a pure state, and consequently expressed as an uncertainty relation for the sum of conditional entropies.

System for measuring radioactivity of labelled biopolymers

International Nuclear Information System (INIS)

Gross, V.

1980-01-01

A system is described for measuring radioactivity of labelled biopolymers, comprising: a set of containers adapted for receiving aqueous solutions of biological samples containing biopolymers which are subsequently precipitated in said containers on particles of diatomite in the presence of a coprecipitator, then filtered, dissolved, and mixed with a scintillator; radioactivity measuring means including a detection chamber to which is fed the mixture produced in said set of containers; an electric drive for moving said set of containers in a stepwise manner; means for proportional feeding of said coprecipitator and a suspension of diatomite in an acid solution to said containers which contain the biological sample for forming an acid precipitation of biopolymers; means for the removal of precipitated samples from said containers; precipitated biopolymer filtering means for successively filtering the precipitate, suspending the precipitate, dissolving the biopolymers mixed with said scintillator for feeding of the mixture to said detection chamber; a system of pipelines interconnecting said above-recited means; and said means for measuring radioactivity of labelled biopolymers including, a measuring cell arranged in a detection chamber and communicating with said means for filtering precipitated biopolymers through one pipeline of said system of pipelines; a program unit electrically connected to said electric drive, said means for acid precipatation of biopolymers, said means for the removal of precipitated samples from said containers, said filtering means, and said radioactivity measuring device; said program unit adapted to periodically switch on and off the above-recited means and check the sequence of the radioactivity measuring operations; and a control unit for controlling the initiation of the system and for selecting programs

Land Disposal Restrictions Treatment Standards: Compliance Strategies for Four Types of Mixed Wastes

International Nuclear Information System (INIS)

Fortune, W.B.; Ranek, N.L.

2006-01-01

This paper describes the unique challenges involved in achieving compliance with the Resource Conservation and Recovery Act (Public Law 94-580) Land Disposal Restrictions (LDR) treatment standards for four types of mixed wastes generated throughout the U.S. Department of Energy (DOE) complex: (1) radioactively contaminated lead acid batteries; (2) radioactively contaminated cadmium-, mercury-, and silver-containing batteries; (3) mercury-bearing mixed wastes; and (4) radioactive lead solids. For each of these mixed waste types, the paper identifies the strategy pursued by DOE's Office of Pollution Prevention and Resource Conservation Policy and Guidance (EH-43) in coordination with other DOE elements and the U.S. Environmental Protection Agency (EPA) to meet the compliance challenge. Specifically, a regulatory interpretation was obtained from EPA agreeing that the LDR treatment standard for wastes in the D008 'Radioactive Lead Solids' sub-category applies to radioactively contaminated lead acid batteries. For cadmium-, mercury-, and silver-containing batteries, generically applicable treatability variances were obtained from EPA approving macro-encapsulation as the alternative LDR treatment standard for all three battery types. Joint DOE/EPA technology demonstrations were pursued for mercury-bearing mixed wastes in an effort to justify revising the LDR treatment standards, which focus on thermal recovery of mercury for reuse. Because the demonstrations failed to produce enough supporting data for a rulemaking, however, EPA has recommended site-specific treatability variances for particular mercury-bearing mixed waste streams. Finally, DOE has filed an application for a determination of equivalent treatment requesting approval of container-based macro-encapsulation technologies as an alternative LDR treatment standard for radioactive lead solids. Information is provided concerning the length of time required to implement each of these strategies, and suggestions for

Safety guidebook relative to the disposal of radioactive wastes in deep geologic formation

International Nuclear Information System (INIS)

2008-01-01

The French nuclear safety authority (ASN) initiated in 2003 a revision process of the objectives to be considered during the research and work steps of the implementation of a radioactive waste storage facility in deep geologic formations. The purpose of this document is to define the safety objectives that have to be retained at each step of this implementation, from the site characterization to the closure of the facility. This update takes into account the works carried out by the ANDRA (French national agency of radioactive wastes) in the framework of the law from December 30, 1991, and the advices of the permanent experts group about these works. It takes also into consideration the international research works in this domain and the choices defined in the program law no 2006-739 from June 28, 2006 relative to the sustainable management of radioactive materials and wastes. The main modifications concern: the notion of reversibility, the definition of the safety functions of disposal components, the safety goals and the design principles assigned to waste packages, the control of nuclear materials and the monitoring objectives of the facility. The documents treats of the following points: 1 - the objectives of public health and environment protection; 2 - the safety principles and the safety-related design bases of the facility; and 3 - the method used for demonstrating the disposal safety. (J.S.)

Overview of mixed waste issues

International Nuclear Information System (INIS)

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

1986-01-01

Based on BNL's study it was concluded that there are LLWs which contain chemically hazardous components. Scintillation liquids may be considered an EPA listed hazardous waste and are, therefore, potential mixed wastes. Since November, 1985 no operating LLW disposal site will accept these wastes for disposal. Unless such wastes contain de minimis quantities of radionuclides, they cannot be disposed of at an EPA an EPA permitted site. Currently generators of LSC wastes can ship de minimis wastes to be burned at commercial facilities. Oil wastes will also eventually be an EPA listed waste and thus will have to be considered a potential radioactive mixed wasted unless NRC establishes de minimis levels of radionuclides below which oils can be managed as hazardous wastes. Regarding wastes containing lead metal there is some question as to the extent of the hazard posed by lead disposed in a LLW burial trench. Chromium-containing wastes would have to be tested to determine whether they are potential mixed wastes. There may be other wastes that are mixed wastes; the responsibility for determining this rests with the waste generator. It is believed that there are management options for handling potential mixed wastes but there is no regulatory guidance. BNL has identified and evaluated a variety of treatment options for the management of potential radioactive mixed wastes. The findings of that study showed that application of a management option with the purpose of addressing EPA concern can, at the same time, address stabilization and volume reduction concerns of NRC

Co-ordinated research and environmental surveillance programme related to sea disposal of radioactive waste

International Nuclear Information System (INIS)

1984-01-01

Sea disposal operations of packaged low-level radioactive waste are carried out under the provisions of the Convention on the Prevention of Marine Pollution by Dumping of Wastes and Other Matter, also referred to as the London Dumping Convention. The environmental impact of this disposal method is continuously kept under review, in particular within the IAEA which has provided the ''Definition of High-Level Radioactive Waste or Other High-Level Radioactive Matter Unsuitable for Dumping at Sea'' for the purpose of the Convention and within the OECD-NEA in the framework of its Multilateral Consultation and Surveillance Mechanism for Sea Dumping of Radioactive Waste. The NEA Co-Ordinated Research and Environmental Surveillance Programme (CRESP) is focussed on the actual North-East Atlantic dump site. Its objective is to increase the available scientific data base related to the oceanographic and biological characteristics of the dump site and elaborate a site specific model of the transfers of radionuclides to human populations. Future site suitability reviews, as periodically requested under the terms of the Multilateral Consultation and Surveillance Mechanism, will therefore be based on a more accurate and comprehensive scientific basis

Mixed and chelated waste test programs with bitumen solidification

International Nuclear Information System (INIS)

Simpson, S.I.; Morris, M.; Vidal, H.

1988-01-01

This paper presents the results of bitumen solidification tests on mixed wastes and chelated wastes. The French Atomic Energy Commission (CEA) performed demonstration tests on radioactive wastes contaminated with chelating agents for Associated Technologies, Inc. (ATI). The chelated wastes were produced and concentrated by Commonwealth Edison Co. as a result of reactor decontamination at Dresden Nuclear Station, Unit 1. Law Engineering in Charlotte, N. C. produced samples and performed tests on simulated heavy metal laden radioactive waste (mixed) to demonstrate the quality of the bituminous product. The simulation is intended to represent waste produced at Oak Ridge National Labs operated by Martin-Marietta

A lower bound on the relative error of mixed-state cloning and related operations

International Nuclear Information System (INIS)

Rastegin, A E

2003-01-01

We extend the concept of the relative error to mixed-state cloning and related physical operations, in which the ancilla contains some information a priori about the input state. The lower bound on the relative error is obtained. It is shown that this result provides further support for a stronger no-cloning theorem

A thermal analysis study on proprietary quick-setting mixed binder system

International Nuclear Information System (INIS)

Deneanu, N.; Dulama, M.; Diaconescu, C.

2013-01-01

The present paper presents a study, by thermal analysis, of the hydration of a mixed binder system consist of Portland composite cement type CEM II/A-M(S-LL) 32,5 R and calcium aluminate cement type GORKAL 70, patented by the authors for embedding spent radioactive solvents. Cement hydration reactions are often affected by the presence of a spent radioactive solvent, usually retarded. This process can be monitored by thermal analysis and often quantified. The data are being used as a reference to compare the changes in the cement blend hydration during the solidification caused by the presence of the spent radioactive solvents itself or by emulsifier additives which are being availed. Detailed analysis of DTG (derivative thermo gravimetric) decomposition profiles of portlandite and carbonate enabled the evaluation of admixture-related parameters concerning portlandite formation and also indicated the behaviour of specific carbonates during the hydration process. (authors)

Recommendations for continuous emissions monitoring of mixed waste incinerators

International Nuclear Information System (INIS)

Quigley, G.P.

1992-01-01

Considerable quantities of incinerable mixed waste are being stored in and generated by the DOE complex. Mixed waste is defined as containing a hazardous component and a radioactive component. At the present time, there is only one incinerator in the complex which has the proper TSCA and RCRA permits to handle mixed waste. This report describes monitoring techniques needed for the incinerator

Research requirements related to radioactivity in the environment

International Nuclear Information System (INIS)

Fry, F.A.; Hill, M.D.; Wilkins, B.; Cooper, J.R.

1988-05-01

A set of papers identifying perceived national research requirements to 1989 had been prepared by various organisations for the Radioactivity, Research and Environmental Monitoring Committee. The Committee had also received a set of papers describing the research to be carried out or commissioned by Government Departments, advisory bodies and the nuclear industry in 1987-9. The purpose of the present report in the general area of radioactivity in the environment is to consider those papers and identify any gaps or overlaps in the national research effort to 1989. Five gaps are identified and their significance is commented upon. (author)

National Institutes of Health: Mixed waste minimization and treatment

International Nuclear Information System (INIS)

1995-08-01

The Appalachian States Low-Level Radioactive Waste Commission requested the US Department of Energy's National Low-Level Waste Management Program (NLLWMP) to assist the biomedical community in becoming more knowledgeable about its mixed waste streams, to help minimize the mixed waste stream generated by the biomedical community, and to identify applicable treatment technologies for these mixed waste streams. As the first step in the waste minimization process, liquid low-level radioactive mixed waste (LLMW) streams generated at the National Institutes of Health (NIH) were characterized and combined into similar process categories. This report identifies possible waste minimization and treatment approaches for the LLMW generated by the biomedical community identified in DOE/LLW-208. In development of the report, on site meetings were conducted with NIH personnel responsible for generating each category of waste identified as lacking disposal options. Based on the meetings and general waste minimization guidelines, potential waste minimization options were identified

National Institutes of Health: Mixed waste minimization and treatment

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-08-01

The Appalachian States Low-Level Radioactive Waste Commission requested the US Department of Energy`s National Low-Level Waste Management Program (NLLWMP) to assist the biomedical community in becoming more knowledgeable about its mixed waste streams, to help minimize the mixed waste stream generated by the biomedical community, and to identify applicable treatment technologies for these mixed waste streams. As the first step in the waste minimization process, liquid low-level radioactive mixed waste (LLMW) streams generated at the National Institutes of Health (NIH) were characterized and combined into similar process categories. This report identifies possible waste minimization and treatment approaches for the LLMW generated by the biomedical community identified in DOE/LLW-208. In development of the report, on site meetings were conducted with NIH personnel responsible for generating each category of waste identified as lacking disposal options. Based on the meetings and general waste minimization guidelines, potential waste minimization options were identified.

An evaluation of three representative multimedia models used to support cleanup decision-making at hazardous, mixed, and radioactive waste sites

International Nuclear Information System (INIS)

Moskowitz, P.D.; Pardi, R.; Fthenakis, V.M.; Holtzman, S.

1996-01-01

The decision process involved in cleaning sites contaminated with hazardous, mixed, and radioactive materials is supported often by results obtained from computer models. These results provide limits within which a decision-maker can judge the importance of individual transport and fate processes, and the likely outcome of alternative cleanup strategies. The transport of hazardous materials may occur predominately through one particular pathway but, more often, actual or potential transport must be evaluated across several pathways and media. Multimedia models are designed to simulate the transport of contaminants from a source to a receptor through more than one environmental pathway. Three such multimedia models are reviewed here: MEPAS, MMSOILS, and PRESTO-EPA-CPG. The reviews are based on documentation provided with the software, on published reviews, on personal interviews with the model developers, and on model summaries extracted from computer databases and expert systems. The three models are reviewed within the context of specific media components: air, surface water, ground water, and food chain. Additional sections evaluate the way that these three models calculate human exposure and dose and how they report uncertainty. Special emphasis is placed on how each model handles radionuclide transport within specific media. For the purpose of simulating the transport, fate and effects of radioactive contaminants through more than one pathway, both MEPAS and PRESTO-EPA-CPG are adequate for screening studies; MMSOILS only handles nonradioactive substances and must be modified before it can be used in these same applications. Of the three models, MEPAS is the most versatile, especially if the user needs to model the transport, fate, and effects of hazardous and radioactive contaminants. 44 refs., 2 tabs

NEA Research and Environmental Surveillance Programme related to sea disposal of low-level radioactive waste

International Nuclear Information System (INIS)

Ruegger, B.; Templeton, W.L.; Gurbutt, P.

1983-05-01

Sea dumping operations of certain types of packaged low and medium-level radioactive wastes have been carried out since 1967 in the North-East Atlantic under the auspices of the OECD Nuclear Energy Agency. On the occasion of the 1980 review of the continued suitability of the North-East Atlantic site used for the disposal of radioactive waste, it was recommended that an effort should be made to increase the scientific data base relating to the oceanographic and biological characteristics of the dumping area. In particular, it was suggested that a site specific model of the transfer of radionuclides in the marine environment be developed, which would permit a better assessment of the potential radiation doses to man from the dumping of radioactive waste. To fulfill these objectives a research and environmental surveillance programme related to sea disposal of radioactive waste was set up in 1981 with the participation of thirteen Member countries and the International Laboratory for Marine Radioactivity of the IAEA in Monaco. The research program is focused on five research areas which are directly relevant to the preparation of more site-specific assessments in the future. They are: model development; physical oceanography; geochemistry; biology; and radiological surveillance. Promising results have already been obtained and more are anticipated in the not too distant future. An interim description of the NEA dumping site has been prepared which provides an excellent data base for this area (NEA 1983).It includes data in bathymetry, isopycnal topography, local and larger scale currents, sediment distribution and sedimentary processes, hydrochemistry, deep ocean biology and results of radiochemical analyses of sea water, sediments and biological materials. The modelling work is also well advanced allowing comparison of results obtained from different codes. After integration of the models, sensitivity analyses will provide indications for future research needs

Measuring relative humidity in the radioactive environment of the IRRAD proton facility

CERN Document Server

Paerg, Marten

2017-01-01

The aim of the project was to obtain information on relative humidity conditions at different locations in the IRRAD proton facility. Due to high radiation levels inside the facility, different sensors had to be qualified and dedicated electronics had to be built to transfer the data of the sensors over long wires to a less radioactive area, where it could be collected.

Task 1.6 - mixed waste. Topical report, April 1, 1994--September 30, 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-31

For fifty years, the United States was involved in a nuclear arms race of immense proportions. During the majority of this period, the push was always to design new weapons, produce more weapons, and increase the size of the arsenal, maintaining an advantage over the opposition in order to protect U.S. interests. Now that the {open_quotes}Cold War{close_quotes} is over, we are faced with the imposing tasks of dismantling, cleaning up, and remediating the wide variety of problems created by this arms race. An overview of the current status of the total remediation effort within the DOE is presented in the DOE publication {open_quotes}ENVIRONMENTAL MANAGEMENT 1995{close_quotes} (EM 1995). Not all radioactive waste is the same though; therefore, a system was devised to categorize the different types of radioactive waste. These categories are as follows: spent fuel; high-level waste; transuranic waste; low-level waste; mixed waste; and uranium-mill tailings. Mixed waste is defined to be material contaminated with any of these categories of radioactive material plus an organic or heavy metal component. However, for this discussion, {open_quotes}mixed waste{close_quote} will pertain only to low-level mixed waste which consists of low-level radioactive waste mixed with organic solvents and or heavy metals. The area of {open_quotes}mixed-waste characterization, treatment, and disposal{close_quotes} is listed on page 6 of the EM 1995 publication as one of five focus areas for technological development, and while no more important than the others, it has become an area of critical concern for DOE. Lacking adequate technologies for treatment and disposal, the DOE stockpiled large quantities of mixed waste during the 1970s and 1980s. Legislative changes and the need for regulatory compliance have now made it expedient to develop methods of achieving final disposition for this stockpiled mixed waste.

Mixed Waste Focus Area - Waste form initiative

International Nuclear Information System (INIS)

Nakaoka, R.; Waters, R.; Pohl, P.; Roach, J.

1998-01-01

The mission of the US Department of Energy's (DOE) Mixed Waste Focus Area (MWFA) is to provide acceptable technologies that enable implementation of mixed waste treatment systems which are developed in partnership with end-users, stakeholders, tribal governments, and regulators. To accomplish this mission, a technical baseline was established in 1996 and revised in 1997. The technical baseline forms the basis for determining which technology development activities will be supported by the MWFA. The primary attribute of the technical baseline is a set of prioritized technical deficiencies or roadblocks related to implementation of mixed waste treatment systems. The Waste Form Initiative (WFI) was established to address an identified technical deficiency related to waste form performance. The primary goal of the WFI was to ensure that the mixed low-level waste (MLLW) treatment technologies being developed, currently used, or planned for use by DOE would produce final waste forms that meet the waste acceptance criteria (WAC) of the existing and/or planned MLLW disposal facilities. The WFI was limited to an evaluation of the disposal requirements for the radioactive component of MLLW. Disposal requirements for the hazardous component are dictated by the Resource Conservation and Recovery Act (RCRA), and were not addressed. This paper summarizes the technical basis, strategy, and results of the activities performed as part of the WFI

Characterization and remediation of a mixed waste-contaminated site at Kirtland Air Force Base, New Mexico

International Nuclear Information System (INIS)

Johnston, J.W.; Thacker, M.S.; DeWitt, C.B.

1997-01-01

In the area of environmental restoration, one of the most challenging problems is the task of remediating mixed waste-contaminated sites. This paper discusses a successful Interim Corrective Measure (ICM) performed at a mixed waste-contaminated site on Kirtland Air Force Base (AFB) in Albuquerque, New Mexico. The site, known as RW-68, Cratering Area and Radium Dump/Slag Piles, was used during the late 1940s and early 1950s for the destruction and incineration of captured World War II aircraft. It contained 19 slag piles totaling approximately 150 tons of slag, ash, refractory brick, and metal debris. The piles were contaminated with radium-226 and RCRA-characteristic levels of heavy metals. Therefore, the piles were considered mixed waste. To eliminate the threat to human health and the environment, an ICM of removal, segregation, stabilization, and disposal was conducted from October through December 1996. Approximately 120 cubic yards (cu yds) of mixed waste, 188 cu yds of low-level radioactive-contaminated soil, 1 cu yd of low-level radioactive-contaminated debris, 5 cu yds of RCRA-characteristic hazardous waste, and 45 tons of nonhazardous debris were stabilized and disposed of during the ICM. To render the RCRA metals and radionuclides insoluble, stabilization was performed on the mixed and RCRA-characteristic waste streams. All stabilized material was subjected to TCLP analysis to verify it no longer exhibited RCRA-characteristic properties. Radiological and geophysical surveys were conducted concurrently with site remediation activities. These surveys provided real-time documentation of site conditions during each phase of the ICM and confirmed successful cleanup of the site. The three radioactive waste streams, stabilized mixed waste, low-level radioactive-contaminated soil, and low-level radioactive-contaminated debris, were disposed of at the Envirocare low-level radioactive disposal facility

Lactoperoxidase catalyzed radioiodination of cell surface immunoglobulin: incorporated radioactivity may not reflect relative cell surface Ig density

International Nuclear Information System (INIS)

Wilder, R.L.; Yuen, C.C.; Mage, R.G.

1979-01-01

Rabbit and mouse splenic lymphocytes were radioiodinated by the lactoperoxidase technique, extracted with non-ionic detergent, immunoprecipitated with high titered rabbit anti-kappa antisera, and compared by SDS-PAGE. Mouse sIg peaks were reproducibly larger in size than rabbit sIg peaks (often greater than 10 times). Neither differences in incorporation of label into the rabbit cell surface, nor differences in average sIg density explain this result. Total TCA-precipitable radioactivity was similar in each species. Estimation of the relative amounts of sIg in the mouse and rabbit showed similar average sIg densities. Differences in detergent solubility, proteolytic lability, or antisera used also do not adequately account for this difference. Thus, these data indicate that radioactivity incorporated after lactoperoxidase catalyzed cell surface radioiodination may not reflect cell surface Ig density. Conclusions about cell surface density based upon relative incorporation of radioactivity should be confirmed by other approaches

Method of solidifying radioactive laundry wastes

International Nuclear Information System (INIS)

Yasumura, Keijiro

1984-01-01

Purpose: To enable to solidify radioactive laundry wastes containing non-ionic liquid detergents less solidifiable by plastic solidification process in liquid laundry wastes for cloths or the likes discharged from a nuclear power plant. Method: Radioactive laundry wastes are solidified by using plastic solidifying agent comprising, as a main ingredient, unsaturated polyester resins and methylmethacrylate monomers. The plastic solidifying agents usable herein include, for example, unsaturated polyester resins prepared by condensating maleic anhydride and phthalic anhydride with propylene glycol and incorporated with methylmethacrylate monomers. The mixing ratio of the methylmethacrylate monomers is preferably 30 % by weight based on the unsaturated polyester resins. (Aizawa, K.)

Dispersal of radioactivity by wildlife from contaminated sites in a forested landscape

International Nuclear Information System (INIS)

Garten, C.T. Jr.

1992-01-01

Oak Ridge National Laboratory (ORNL) is located within the Ridge and Valley physiographic province of eastern Tennessee (USA). This area is characterized by deciduous forests dominated by hardwood and mixed mesophytic tree species. Wildlife populations have access to some radioactively contaminated sites at ORNL, and contaminated animals or animal nests within the Laboratory's boundaries have been found to contain on the order of 10 -12 to 10 -6 Ci/g of 90 Sr or 137 Cs, and trace amounts of other radionuclides (including transuranic elements). Theoretical calculations indicate that nanocurie levels of 90 Sr in bone can arise from relatively small amounts (1%) of contaminated browse vegetation in a deer's diet. Measures that have been undertaken at ORNL to curtail the dispersal of radioactivity by animals are briefly reviewed

Electromagnetic mixed waste processing system for asbestos decontamination

Energy Technology Data Exchange (ETDEWEB)

Kasevich, R.S. [KAI Technologies, Inc., Portsmouth, NH (United States); Vaux, W.G. [Westinghouse Electric Corp., Pittsburgh, PA (United States); Nocito, T. [Ohio DSI Corp., New York (United States)

1995-10-01

DOE sites contain a broad spectrum of asbestos materials (cloth, pipe lagging, sprayed insulation and other substances) which are contaminated with a combination of hazardous and radioactive wastes due to its use during the development of the U.S. nuclear weapons complex. These wastes consist of cutting oils, lubricants, solvents, PCB`s, heavy metals and radioactive contaminants. The radioactive contaminants are the activation, decay and fission products of DOE operations. The asbestos must be converted by removing and separating the hazardous and radioactive materials to prevent the formation of mixed wastes and to allow for both sanitary disposal and effective decontamination. Currently, no technology exists that can meet these sanitary and other objectives.

Electromagnetic mixed waste processing system for asbestos decontamination

International Nuclear Information System (INIS)

Kasevich, R.S.; Vaux, W.G.; Nocito, T.

1995-01-01

DOE sites contain a broad spectrum of asbestos materials (cloth, pipe lagging, sprayed insulation and other substances) which are contaminated with a combination of hazardous and radioactive wastes due to its use during the development of the U.S. nuclear weapons complex. These wastes consist of cutting oils, lubricants, solvents, PCB's, heavy metals and radioactive contaminants. The radioactive contaminants are the activation, decay and fission products of DOE operations. The asbestos must be converted by removing and separating the hazardous and radioactive materials to prevent the formation of mixed wastes and to allow for both sanitary disposal and effective decontamination. Currently, no technology exists that can meet these sanitary and other objectives

Commercial treatability study capabilities for application to the US Department of Energy's anticipated mixed waste streams

International Nuclear Information System (INIS)

1996-07-01

The U.S. Department of Energy (DOE) has established the Mixed Waste Focus Area (MWFA), which represents a national effort to develop and coordinate treatment solutions for mixed waste among all DOE facilities. The hazardous waste component of mixed waste is regulated under the Resource Conservation and Recovery Act (RCRA), while the radioactive component is regulated under the Atomic Energy Act, as implemented by the DOE, making mixed waste one of the most complex types of waste for the DOE to manage. The MWFA has the mission to support technologies that meet the needs of the DOE's waste management efforts to characterize, treat, and dispose of mixed waste being generated and stored throughout the DOE complex. The technologies to be supported must meet all regulatory requirements, provide cost and risk improvements over available technologies, and be acceptable to the public. The most notable features of the DOE's mixed-waste streams are the wide diversity of waste matrices, volumes, radioactivity levels, and RCRA-regulated hazardous contaminants. Table 1-1 is constructed from data from the proposed site treatment plans developed by each DOE site and submitted to DOE Headquarters. The table shows the number of mixed-waste streams and their corresponding volumes. This table illustrates that the DOE has a relatively small number of large-volume mixed-waste streams and a large number of small-volume mixed-waste streams. There are 1,033 mixed-waste streams with volumes less than 1 cubic meter; 1,112 mixed-waste streams with volumes between 1 and 1,000 cubic meters; and only 61 mixed-waste streams with volumes exceeding 1,000 cubic meters

Estimation of global inventories of radioactive waste and other radioactive materials

International Nuclear Information System (INIS)

2008-06-01

A variety of nuclear activities have been carried out in the second part of the twentieth century for different purposes. Initially the emphasis was on military applications, but with the passage of time the main focus of nuclear activities has shifted to peaceful uses of nuclear energy and to the use of radioactive material in industry, medicine and research. Regardless of the objectives, the nuclear activities generate radioactive waste. It was considered worthwhile to produce a set of worldwide data that could be assessed to evaluate the legacy of the nuclear activities performed up to the transition between the twentieth and the twenty first century. The assessment tries to cover the inventory of all the human produced radioactive material that can be considered to result from both military and civilian applications. This has caused remarkable difficulties since much of the data, particularly relating to military programmes, are not readily available. Consequently the data on the inventory of radioactive material should be considered as order-of-magnitude approximations. This report as a whole should be considered as a first iteration in a continuing process of updating and upgrading. The accumulations of radioactive materials can be considered a burden for human society, both at present and in the future, since they require continuing monitoring and control. Knowing the amounts and types of such radioactive inventories can help in the assessment of the relative burdens. Knowledge of the national or regional radioactive waste inventory is necessary for planning management operations, including the sizing and design of conditioning, storage and disposal facilities. A global inventory, either of radioactive waste or of other environmental accumulations of radioactive material, could be used to provide a perspective on the requirements and burdens associated with their management, by means of comparisons with the burdens caused by other types of waste or other

Mixed Waste Salt Encapsulation Using Polysiloxane - Final Report

International Nuclear Information System (INIS)

Miller, C.M.; Loomis, G.G.; Prewett, S.W.

1997-01-01

A proof-of-concept experimental study was performed to investigate the use of Orbit Technologies polysiloxane grouting material for encapsulation of U.S. Department of Energy mixed waste salts leading to a final waste form for disposal. Evaporator pond salt residues and other salt-like material contaminated with both radioactive isotopes and hazardous components are ubiquitous in the DOE complex and may exceed 250,000,000 kg of material. Current treatment involves mixing low waste percentages (less than 10% by mass salt) with cement or costly thermal treatment followed by cementation to the ash residue. The proposed technology involves simple mixing of the granular salt material (with relatively high waste loadings-greater than 50%) in a polysiloxane-based system that polymerizes to form a silicon-based polymer material. This study involved a mixing study to determine optimum waste loadings and compressive strengths of the resultant monoliths. Following the mixing study, durability testing was performed on promising waste forms. Leaching studies including the accelerated leach test and the toxicity characteristic leaching procedure were also performed on a high nitrate salt waste form. In addition to this testing, the waste form was examined by scanning electron microscope. Preliminary cost estimates for applying this technology to the DOE complex mixed waste salt problem is also given

A survey of the environmental radioactivity in the east sea related to the Russian ocean dumping of the radioactive waste

International Nuclear Information System (INIS)

Kim, Kyehoon; Kim, Changkyu; Lee, Mosung

1994-01-01

From October 24 - December 30, 1993 a joint survey by the Office of Fisheries, Korea Institute of Nuclear Safety, Korea Ocean Research and Development Institute, and several other governmental institutes which was supervised by Ministry of Science and Technology was carried out to investigate present marine environmental radioactivity of the East Sea where former USSR and Russia had dumped radioactive waste since 1957. Exposure rate was measured and the radioactivity of seawater, both surface and deep water, bottom sediment, fish, and planktonic organisms from the areas around the dumping sites and the East Sae were analyzed. Results showed that the radioactivities of Cs-137 in the sea water from dumping sites were less than 0.0038 Bq/L, which was similar to the background level of the East Sea. The radioactivity level of fish and bottom sediment from dumping sites also did not increased. A detailed Ocean Environmental Monitoring Plan, however, should be established and the monitoring must be carried out continuously to protect people from potential radioactive hazards

Management of radioactive waste

International Nuclear Information System (INIS)

Neerdael, B.; Marivoet, J.; Put, M.; Van Iseghem, P.; Volckaert, G.; Wacquier, W.

1998-09-01

The document gives an overview of of different aspects of radioactive waste management in Belgium. The document discusses the radioactive waste inventory in Belgium, the treatment and conditioning of radioactive waste as well as activities related to the characterisation of different waste forms. A separate chapter is dedicated to research and development regarding deep geological disposal of radioactive waste. In the Belgian waste management programme, particular emphasis is on studies for disposal in clay. Main results of these studies are highlighted and discussed

Method to determine the radioactivity of radioactive waste packages. Basic procedure of the method used to determine the radioactivity of low-level radioactive waste packages generated at nuclear power plants: 2007

International Nuclear Information System (INIS)

2008-03-01

This document describes the procedures adopted in order to determine the radioactivity of low-level radioactive waste packages generated at nuclear power plants in Japan. The standards applied have been approved by the Atomic Energy Society of Japan after deliberations by the Subcommittee on the Radioactivity Verification Method for Waste Packages, the Nuclear Cycle Technical Committee, and the Standards Committee. The method for determining the radioactivity of the low-level radioactive waste packages was based on procedures approved by the Nuclear Safety Commission in 1992. The scaling factor method and other methods of determining radioactivity were then developed on the basis of various investigations conducted, drawing on extensive accumulated knowledge. Moreover, the international standards applied as common guidelines for the scaling factor method were developed by Technical Committee ISO/TC 85, Nuclear Energy, Subcommittee SC 5, Nuclear Fuel Technology. Since the application of accumulated knowledge to future radioactive waste disposal is considered to be rational and justified, such body of knowledge has been documented in a standardized form. The background to this standardization effort, the reasoning behind the determination method as applied to the measurement of radioactivity, as well as other related information, are given in the Annexes hereto. This document includes the following Annexes. Annex 1: (reference) Recorded items related to the determination of the scaling factor. Annex 2 (reference): Principles applied to the determining the radioactivity of waste packages. (author)

Radioactive tank waste remediation focus area

International Nuclear Information System (INIS)

1996-08-01

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

Radioactive tank waste remediation focus area

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-08-01

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

Development of treatment technologies of the processing of U.S. Department of Energy mixed waste

International Nuclear Information System (INIS)

Backus, P.M.; Berry, J.B.; Coyle, G.J. Jr.; Lurk, P.; Wolf, S.M.

1994-01-01

Waste contaminated with chemically hazardous and radioactive species is defined as mixed waste. Significant technology development has been conducted for separate treatment of hazardous and radioactive waste, but technology development addressing mixed-waste treatment has been limited. In response to the need for a comprehensive and consistent approach to mixed-waste technology development, the Office of Technology Development of the US Department of Energy (DOE) has established the Mixed Waste Integrated Program. The program is identifying and evaluating treatment technologies to treat present and estimated future mixed wastes at DOE sites. The status of the technical initiatives in chemical/physical treatment, waste destruction/stabilization technology, off-gas treatment, and final waste form production/assessment is described in this paper

Integrated data base for 1993: US spent fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

Klein, J.A.; Storch, S.N.; Ashline, R.C.

1994-03-01

The Integrated Data Base (IDB) Program has compiled historic data on inventories and characteristics of both commercial and DOE spent fuel; also, commercial and U.S. government-owned radioactive wastes through December 31, 1992. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest U.S. Department of Energy/Energy Information Administration (DOE/EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste (HLW), transuranic (TRU), waste, low-level waste (LLW), commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) LLW. For most of these categories, current and projected inventories are given through the calendar-year (CY) 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal

Integrated Data Base for 1992: US spent fuel and radioactive waste inventories, projections, and characteristics. Revision 8

Energy Technology Data Exchange (ETDEWEB)

Payton, M. L.; Williams, J. T.; Tolbert-Smith, M.; Klein, J. A.

1992-10-01

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1991. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal.

Solidification of radioactive waste effluents

International Nuclear Information System (INIS)

Mergan, L.M.; Cordier, J.-P.

1981-01-01

A process and apparatus for solidifying radioactive waste liquid containing dissolved and/or suspended solids is disclosed. The process includes chemically treating for pH adjustment and precipitation of solids, concentrating solids with a thin-film evaporator to provide liquid concentrate containing about 50% solids, and drying the concentrate with a heated mixing apparatus. The heated mixing apparatus includes a heated wall and working means for shearing dried concentrate from internal surfaces and subdividing dry concentrate into dry, powdery particles. The working means includes a rotor and helical means for positively advancing the concentrate and resulting dry particles from inlet to outlet of the mixing apparatus. The dry particles may also be encapsulated in a matrix material. Entrained particles in the vapor stream from the evaporator and mixer are removed in an integral particle separator and the vapor is subsequently condensed and may be recycled upstream of the thin-film evaporator. A section of the mixer may be used for mixing dry particles with the matrix material in a continuous drying and mixing sequence. A section of the mixer also may be used for mixing the treating chemical with the waste liquid

The Treatment of Mixed Waste with GeoMelt In-Container Vitrification

International Nuclear Information System (INIS)

Finucane, K.G.; Campbell, B.E.

2006-01-01

AMEC's GeoMelt R In-Container Vitrification (ICV) TM has been used to treat diverse types of mixed low-level radioactive waste. ICV is effective in the treatment of mixed wastes containing polychlorinated biphenyls (PCBs) and other semi-volatile organic compounds, volatile organic compounds (VOCs) and heavy metals. The GeoMelt vitrification process destroys organic compounds and immobilizes metals and radionuclides in an extremely durable glass waste form. The process is flexible allowing for treatment of aqueous, oily, and solid mixed waste, including contaminated soil. In 2004, ICV was used to treat mixed radioactive waste sludge containing PCBs generated from a commercial cleanup project regulated by the Toxic Substances Control Act (TSCA), and to treat contaminated soil from Rocky Flats Environmental Technology Site. The Rocky Flats soil contained cadmium, PCBs, and depleted uranium. In 2005, AMEC completed a treatability demonstration of the ICV technology on Mock High Explosive from Sandia National Laboratories. This paper summarizes results from these mixed waste treatment projects. (authors)

Method of solidifying radioactive wastes

International Nuclear Information System (INIS)

Tomita, Toshihide; Minami, Yuji; Matsuura, Hiroyuki

1984-01-01

Purpose: To enable complete curing even when radioactive wastes contain those materials hindering the curing reaction, for example, copper hydroxide. Method: After admixing an alkaline substance to radioactive concentrated liquid wastes containing copper hydroxide or other amphoteric substances, they are dried, powderized and then cured with thermosetting resins. The thermosetting resins usable herein include, for example, those prepared by mixing an unsaturated polyester with a monomer such as styrene. When a polymerization initiator such as methyl ethyl ketone peroxide and a polymerization promotor are added to the mixture, it takes places curing reaction at normal temperature. Suitable alkaline substances usable herein are those which are insoluble to the liquid wastes and do not change the chemical form under heating and drying. (Yoshihara, H.)

Radioactive waste shredding: Preliminary evaluation

International Nuclear Information System (INIS)

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

1994-07-01

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

Thermal processing systems for TRU mixed waste

International Nuclear Information System (INIS)

Eddy, T.L.; Raivo, B.D.; Anderson, G.L.

1992-01-01

This paper presents preliminary ex situ thermal processing system concepts and related processing considerations for remediation of transuranic (TRU)-contaminated wastes (TRUW) buried at the Radioactive Waste Management Complex (RWMC) of the Idaho National Engineering Laboratory (INEL). Anticipated waste stream components and problems are considered. Thermal processing conditions required to obtain a high-integrity, low-leachability glass/ceramic final waste form are considered. Five practical thermal process system designs are compared. Thermal processing of mixed waste and soils with essentially no presorting and using incineration followed by high temperature melting is recommended. Applied research and development necessary for demonstration is also recommended

Radioactivity and food

International Nuclear Information System (INIS)

Olszyna-Marzys, A.E.

1990-01-01

Two topics relating to radioactivity and food are discussed: food irradiation for preservation purposes, and food contamination from radioactive substances. Food irradiation involves the use of electromagnetic energy (x and gamma rays) emitted by radioactive substances or produced by machine in order to destroy the insects and microorganisms present and prevent germination. The sanitary and economic advantages of treating food in this way are discussed. Numerous studies have confirmed that under strictly controlled conditions no undesirable changes take place in food that has been irradiated nor is radioactivity induced. Reference is made to the accident at the Chernobyl nuclear power station, which aroused public concern about irradiated food. The events surrounding the accident are reviewed, and its consequences with regard to contamination of different foods with radioactive substances, particularly iodine-131 and cesium-137, are described. Also discussed are the steps that have been taken by different international organizations to set limits on acceptable radioactivity in food.15 references

Destructive and non-destructive tests for radioactive waste packages Task 3 Characterization of radioactive waste forms. A series of final reports (1985-89) No 43

International Nuclear Information System (INIS)

Odoj, R.

1991-01-01

On the basis of preliminary waste acceptance requirements quality control of radioactive waste has to be performed prior to interim storage or final disposal. The quality control can either be achieved by random tests on conditioned radioactive waste packages or by process qualification of the conditioning processes. One of the most important criteria is the activity of the radioactive waste product or packages. To get some first information on the waste package γ-spectrometric measurement is performed as non-destructive test. Besides the γ-emitting nuclides the α and β-emitting nuclides can be estimated by calculation if the waste was generated in nuclear power plants and the nuclide relations are known. If the non-destructive determination of nuclides is not sufficient or the non-radioactive content of the waste packages has to be identified sampling from the waste packages has to be performed. This can best be done by core drilling. To avoid the need of water for cooling the drill head, air cooled core drilling is investigated. As mixed wastes is not allowed for final disposal the determination of possible organic toxic materials like PCB, dioxin and furane-compounds in cemented wastes is conducted by GC-MS-investigations. For getting more knowledge in the field of process qualification concerning super compaction, instrumentation of the super compaction process is investigated and tested

Public relations work in the field of disposal of radioactive wastes in the Federal Republic of Germany

International Nuclear Information System (INIS)

Schmitt, R.

1996-01-01

Many institutions have participated in public relations work concerning the final disposal of radioactive wastes in Germany since preliminary research work in this field was started in the early 1960's. The large number of institutions involved necessitates a uniform phraseology, kept up to date by permanent exchanges of information. The Press and Public Information Section of the Bundesamt fur Strahlenschutz (BfS) is responsible for co-ordination, with the aim of presenting both the general disposal concept of the Federal Government, and the work done within the scope of individual projects in the field of final waste disposal. Public relations activities are supported by the Deutsche Gesellschaft zum Bau and Betrieb von Endlagern fur Abfallstoffe mbH (DBE) which conducts public relations work at site level. Since the early sixties radioactive waste disposal policy in Germany has been based on the decision that all kinds of radioactive wastes should be disposed of in deep geological formations. One operating repository and two different disposal projects are currently under was in Germany. The paper discusses these three sites and their public relations efforts. A lot of work has been done in the public relations field in Germany, for more than 15 years now. Open, comprehensive information and reporting are essential for transparent and credible representations of the activities necessary for the disposal of radioactive waste, as well as to create a climate of confidence in order to fashion a position identity for such large-scale projects. In addition to personal contacts, target-group oriented information meetings and scientifically understandable information material are important means to achieved this end. The permanent presence of contact persons at the sites supports this objective, especially with regard to information directed towards the general public. (author)

Method of solidifying liquid radioactive wastes

International Nuclear Information System (INIS)

Pekar, A.; Petrovic, J.; Timulak, J.

1987-01-01

Liquid radioactive waste containing boric acid salts is mixed with zeolite tuff and neutralized by lime. Power plant fly ash containing single-component or mixed Portland cement is then added to the mixture. Prior to packaging, anion-active bitumen emulsion or an aqueous emulsion of fatty acid salts and of free fatty acids insoluble in water can be added. Examples are given listing accurate proportions of the individual components. The advantage of the said solidification method is the use of easily available raw materials and improved values of extractability of the resulting product radionuclides. (E.S.)

Comparison of modified sulfur cement and hydraulic cement for encapsulation of radioactive and mixed wastes

International Nuclear Information System (INIS)

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

1990-01-01

The majority of solidification/stabilization systems for low-level radioactive waste (LLW) and mixed waste, both in the commercial sector and at Department of Energy (DOE) facilities, utilize hydraulic cement (such as portland cement) to encapsulate waste materials and yield a monolithic solid waste form for disposal. Because hydraulic cement requires a chemical hydration reaction for setting and hardening, it is subject to potential interactions between elements in the waste and binder that can retard or prevent solidification. A new and innovative process utilizing modified sulfur cement developed by the US Bureau of Mines has been applied at Brookhaven National Laboratory (BNL) for the encapsulation of many of these problem wastes. Modified sulfur cement is a thermoplastic material, and as such, it can be heated above its melting point, combined with dry waste products to form a homogeneous mixture, and cooled to form a monolithic solid product. Under sponsorship of the DOE, research and development efforts at BNL have successfully applied the modified sulfur cement process for treatment of a range of LLWs including sodium sulfate salts, boric acid salts, and incinerator bottom ash and for mixed waste contaminated incinerator fly ash. Process development studies were conducted to determine optimal waste loadings for each waste type. Property evaluation studies were conducted to test waste form behavior under disposal conditions by applying relevant performance testing criteria established by the Nuclear Regulatory Commission (for LLW) and the Environmental Protection Agency (for hazardous wastes). Based on both processing and performance considerations, significantly greater waste loadings were achieved using modified sulfur cement when compared with hydraulic cement. Technology demonstration of the modified sulfur cement encapsulation system using production-scale equipment is scheduled for FY 1991

The view of the geotechnical engineering on the radioactive waste disposal

International Nuclear Information System (INIS)

Komada, Hiroya

2004-01-01

The state of radioactive waste disposal produced by the nuclear fuel cycle facilities and the future problems of geotechnical engineering are stated. Concept of classification of radioactive waste and their disposal, the present state of operating waste and TRU waste in the low level radioactive waste and the high level radioactive waste are explained. On the future problems, evaluation of ground water flow, long period estimation of natural phenomena, mixed earth with bentonite as a buffer and cement materials are discussed. The geological disposal of radioactive waste, which kept them at more than 200 m underground, has two important different points from the general geotechnical engineering such as a system covered inhomogeneous large space of natural geological features and very long time (some million year) considered. (S.Y.)

Radioactivity and its measurement

CERN Document Server

Mann, W B; Garfinkel, S B

1980-01-01

Begins with a description of the discovery of radioactivity and the historic research of such pioneers as the Curies and Rutherford. After a discussion of the interactions of &agr;, &bgr; and &ggr; rays with matter, the energetics of the different modes of nuclear disintegration are considered in relation to the Einstein mass-energy relationship as applied to radioactive transformations. Radiation detectors and radioactivity measurements are also discussed

Commercial treatability study capabilities for application to the US Department of Energy`s anticipated mixed waste streams

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

The U.S. Department of Energy (DOE) has established the Mixed Waste Focus Area (MWFA), which represents a national effort to develop and coordinate treatment solutions for mixed waste among all DOE facilities. The hazardous waste component of mixed waste is regulated under the Resource Conservation and Recovery Act (RCRA), while the radioactive component is regulated under the Atomic Energy Act, as implemented by the DOE, making mixed waste one of the most complex types of waste for the DOE to manage. The MWFA has the mission to support technologies that meet the needs of the DOE`s waste management efforts to characterize, treat, and dispose of mixed waste being generated and stored throughout the DOE complex. The technologies to be supported must meet all regulatory requirements, provide cost and risk improvements over available technologies, and be acceptable to the public. The most notable features of the DOE`s mixed-waste streams are the wide diversity of waste matrices, volumes, radioactivity levels, and RCRA-regulated hazardous contaminants. Table 1-1 is constructed from data from the proposed site treatment plans developed by each DOE site and submitted to DOE Headquarters. The table shows the number of mixed-waste streams and their corresponding volumes. This table illustrates that the DOE has a relatively small number of large-volume mixed-waste streams and a large number of small-volume mixed-waste streams. There are 1,033 mixed-waste streams with volumes less than 1 cubic meter; 1,112 mixed-waste streams with volumes between 1 and 1,000 cubic meters; and only 61 mixed-waste streams with volumes exceeding 1,000 cubic meters.

US Department of Energy, Office of Technology Development, mixed-waste treatment research, development, demonstration, testing, and evaluation

International Nuclear Information System (INIS)

Berry, J.B.; Backus, P.M.; Conley, T.B.; Coyle, G.J.; Lurk, P.W.; Wolf, S.M.

1993-01-01

Department of Energy (DOE) mixed waste is contaminated with both chemically hazardous and radioactive species. The DOE is responsible for regulating radioactive species while the Environmental Protection Agency (EPA) is responsible for regulating hazardous species. Dual regulations establish treatment standards and therefore affect the treatment technologies used to process mixed waste. This duality is reflected in technology development initiatives. Significant technology development has been conducted for either radioactive or hazardous waste, but limited technology development, specifically addressing mixed waste treatment issues, has been completed. Technology has not been designed, developed, demonstrated, or tested to produce a low-risk final waste form that increases the probability that the final waste form will be disposed

DOE acceptance of commercial mixed waste -- Studies are under way

Energy Technology Data Exchange (ETDEWEB)

Plummer, T.L. [Dept. of Energy, Washington, DC (United States). Technical Support Program; Owens, C.M. [Idaho National Engineering Lab., Idaho Falls, ID (United States). National Low-Level Waste Management Program

1993-03-01

The topic of the Department of Energy acceptance of commercial mixed waste at DOE facilities has been proposed by host States and compact regions that are developing low-level radioactive waste disposal facilities. States support the idea of DOE accepting commercial mixed waste because (a) very little commercial mixed waste is generated compared to generation by DOE facilities (Department of Energy--26,300 cubic meters annually vs. commercial--3400 cubic meters annually); (b) estimated costs for commercial disposal are estimated to be $15,000 to $40,000 per cubic foot; (c) once treatment capability becomes available, 70% of the current levels of commercial mixed waste will be eliminated, (d) some State laws prohibit the development of mixed waste disposal facilities in their States; (e) DOE is developing a nationwide strategy that will include treatment and disposal capacity for its own mixed waste and the incremental burden on the DOE facilities would be minuscule, and (6) no States are developing mixed waste disposal facilities. DOE senior management has repeatedly expressed willingness to consider investigating the feasibility of DOE accepting commercial mixed waste. In January 1991, Leo Duffy of the Department of energy met with members of the Low-Level Radioactive Waste Forum, which led to an agreement to explore such an arrangement. He stated that this seems like a cost-effective way to solve commercial mixed waste management problems.

On-line radioactivity detector for HPLC

International Nuclear Information System (INIS)

Kessler, M.J.

1986-01-01

Over the last ten years the technique of high performance liquid chromotography (HPLC) has become extensively employed for the separation and quantitation of various biological, organic, and inorganic substances. The use of HPLC for the separation of various metabolic compounds has become routine. The major problem of analyzing the metabolism process is that the quantitation is accomplished by the use of radioactive substrates. Until recently the only method to quantitate these radioactive compounds eluting from the HPLC was by collecting fractions at preset times, removing aliquots and quantitating in a liquid scintillation counter. Once the radioactivity present in each fraction was determined, the results were plotted on a graph and the area of each of the radioactive peaks was determined. This entire process required from 3-20 hours. The introduction of the flow through radioactivity detector enable the investigator to directly quantitate the radioactive peaks as they elute from the HPLC in real time and at about one-tenth the original cost of the previous methods. The detection limits of this technique are dependent on the residence time of the sample in the flow cell and the type of flow cell used for the analysis. Using a 2.5 ml liquid flow cell, (mixing with liquid scintillation solution), base line resolution can be obtained for peaks 1.5 minutes apart, and a sensitivity of 70 dpm for tritium and 30 dpm for carbon-14 can be achieved

Catabolism of lysine by mixed rumen bacteria

International Nuclear Information System (INIS)

Onodera, Ryoji; Kandatsu, Makoto.

1975-01-01

Metabolites arising from the catabolism of lysine by the mixed rumen bacteria were chromatographically examined by using radioactive lysine. After 6 hr incubation, 241 nmole/ml of lysine was decomposed to give ether-soluble substances and CO 2 by the bacteria and 90 nmole/ml of lysine was incorporated unchanged into the bacteria. delta-Aminovalerate, cadaverine or pipecolate did not seem to be produced from lysine even after incubation of the bacteria with addition of those three amino compounds to trap besides lysine and radioactive lysine. Most of the ether-soluble substances produced from radioactive lysine was volatile fatty acids (VFAs). Fractionation of VFAs revealed that the peaks of butyric and acetic acids coincided with the strong radioactive peaks. Small amounts of radioactivities were detected in propionic acid peak and a peak assumed to be caproic acid. The rumen bacteria appeared to decompose much larger amounts of lysine than the rumen ciliate protozoa did. (auth.)

Environmental radioactivity in the Netherlands. Results in 2005

NARCIS (Netherlands)

Knetsch GJ; RIZA; RIKZ; VWA; RIKILT; LSO; IMD

2007-01-01

From 2005 onwards the national monitoring program "Radioactivity and radiation in the environment" is extended with measurements in milk and in mixed diet. With that the monitoring program complies for the first time with the recommendations of the European Union of 2000. These recommendations

Transportable Vitrification System Demonstration on Mixed Waste

International Nuclear Information System (INIS)

Zamecnik, J.R.; Whitehouse, J.C.; Wilson, C.N.; Van Ryn, F.R.

1998-01-01

This paper describes preliminary results from the first demonstration of the Transportable Vitrification System (TVS) on actual mixed waste. The TVS is a fully integrated, transportable system for the treatment of mixed and low-level radioactive wastes. The demonstration was conducted at Oak Ridge's East Tennessee Technology Park (ETTP), formerly known as the K-25 site. The purpose of the demonstration was to show that mixed wastes could be vitrified safely on a 'field' scale using joule-heated melter technology and obtain information on system performance, waste form durability, air emissions, and costs

Integrated Data Base for 1989: Spent fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1989-11-01

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1988. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected defense-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, remedial action waste, commercial reactor and fuel cycle facility decommissioning waste, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous, highly radioactive materials that may require geologic disposal. 45 figs., 119 tabs

Monitoring device for radioactive leakage from steam system in nuclear power plant

International Nuclear Information System (INIS)

Ogawa, Tateo; Sato, Kohei

1988-01-01

Purpose: To improve the reliability for the monitor of radio-active leakage by accumulating small quantity of radioactivities each lower than the detectable level and increasing their dose rate. Constitution: Even if the steam system radiation monitor in the nuclear power plant is disposed for the detection of in-leak radioactivity, radioactive leakage can be monitored at high reliability by increasing the small quantity of radioactivities in the drains to a detectable sensitivity range of the monitor upon detection. In view of the above, in the present invention, radioactive material catching medium is incorporated to a radio-activity monitor spool piece for accumulating small quantity of radioactivities. Specifically as the catching medium, an ion exchange resin is used for the leakage of ionic radioactive material, while an ion exchange resin increased with the mixing ratio of a cationic resin or hollow thread membrane filter is used for crud-like radioactive material leakage. These catching media are incorporated into the spool piece, thereby enabling to catch even small quantity of radioactive leakage lower than the detectable sensitivity of the radiation monitor, if should occur, in the spool piece and enabling radioactive detection for the accumulated dose rate. (Horiuchi, T.)

Argonne-West facility requirements for a radioactive waste treatment demonstration

International Nuclear Information System (INIS)

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

1995-01-01

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

Design of a mixing system for simulated high-level nuclear waste melter feed slurries

International Nuclear Information System (INIS)

Peterson, M.E.; McCarthy, D.; Muhlstein, K.D.

1986-03-01

The Nuclear Waste Treatment Program development program consists of coordinated nonradioactive and radioactive testing combined with numerical modeling of the process to provide a complete basis for design and operation of a vitrification facility. The radioactive demonstration tests of equipment and processes are conducted before incorporation in radioactive pilot-scale melter systems for final demonstration. The mixing system evaluation described in this report was conducted as part of the nonradioactive testing. The format of this report follows the sequence in which the design of a large-scale mixing system is determined. The initial program activity was concerned with gaining an understanding of the theoretical foundation of non-Newtonian mixing systems. Section 3 of this report describes the classical rheological models that are used to describe non-Newtonian mixing systems. Since the results obtained here are only valid for the slurries utilized, Section 4, Preparation of Simulated Hanford and West Valley Slurries, describes how the slurries were prepared. The laboratory-scale viscometric and physical property information is summarized in Section 5, Laboratory Rheological Evaluations. The bench-scale mixing evaluations conducted to define the effects of the independent variables described above on the degree of mixing achieved with each slurry are described in Section 6. Bench-scale results are scaled-up to establish engineering design requirements for the full-scale mixing system in Section 7. 24 refs., 37 figs., 44 tabs

Always more radioactive matters to manage

International Nuclear Information System (INIS)

Chevallier, J.

2009-01-01

The national agency for radioactive waste management published at the end of June (2009)its new three-yearly inventory of radioactive matters and wastes. for this edition, the numbers are stopped at the 31. december 2007. The volume of conditioned wastes represents 1.15 millions of cubic meters. 62% of these wastes come from nuclear industry. The sectors of research and defence each produce 17% of the whole. The remaining 4% come from others industries and medical sector. currently, 824 609 cubic meters are stored. The most being low and intermediate activity at short life (68%) and very low activity (20%). with 2293 cubic meters the high level activity wastes represent 0.2% of the total volume but constitute 94.98% of the total radioactivity. They come from the reprocessing of spent fuels of electronuclear industry and content fission products and minor actinides. They are not still stored but mixed to a glass matrix melt in stainless steel container. (N.C.)

Perspectives concerning radioactive waste management

International Nuclear Information System (INIS)

Noynaert, L.

2013-01-01

The article presents a general overview of the principles of radioactive waste management as established by the International Atomic Energy Agency. Subsequently, research and development related to radioactive waste management at the Belgian Nuclear Research Center SCK·CEN is discussed. Different topical areas are treated including radioactive waste characterisation, decontamination and the long-term management of radioactive waste. The decommissioning of the BR3 reactor and the construction and the exploitation of the underground research laboratory HADES are cited as examples of the pioneering role that SCK·CEN has played in radioactive waste management.

Radiation safety and health effects related to low-level radioactive wastes

International Nuclear Information System (INIS)

King, W.C.

1979-01-01

The hazards associated with low-level radioactive waste, one of the nation's greatest concerns, are discussed from a health physicist's perspective. Potential biological hazards, four stages of the low-level radioactive waste disposal process, and suggested methods of reducing the risks of handling and disposal, based on previous studies, are defined. Also discussed are potential pathways of human exposure and two scenarios designed to demonstrate the complexity of modeling exposure pathways. The risks of developing a fatal cancer from exposure to the radioactive material, should it occur, is compared to other more commonly accepted risks

U.S. Geological Survey research in radioactive waste disposal - Fiscal years 1986-1990

Science.gov (United States)

Trask, N.J.; Stevens, P.R.

1991-01-01

The report summarizes progress on geologic and hydrologic research related to the disposal of radioactive wastes. The research efforts are categorized according to whether they are related most directly to: (1) high-level wastes, (2) transuranic wastes, (3) low-level and mixed low-level and hazardous wastes, or (4) uranium mill tailings. Included is research applicable to the identification and geohydrologic characterization of waste-disposal sites, to investigations of specific sites where wastes have been stored, to development of techniques and methods for characterizing disposal sites, and to studies of geologic and hydrologic processes related to the transport and/or retention of waste radionuclides.

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

International Nuclear Information System (INIS)

1997-12-01

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

Radioactive waste (disposal)

International Nuclear Information System (INIS)

Jenkin, P.

1985-01-01

The disposal of low- and intermediate-level radioactive wastes was discussed. The following aspects were covered: public consultation on the principles for assessing disposal facilities; procedures for dealing with the possible sites which the Nuclear Industry Radioactive Waste Executive (NIREX) had originally identified; geological investigations to be carried out by NIREX to search for alternative sites; announcement that proposal for a site at Billingham is not to proceed further; NIREX membership; storage of radioactive wastes; public inquiries; social and environmental aspects; safety aspects; interest groups; public relations; government policies. (U.K.)

Three multimedia models used at hazardous and radioactive waste sites

International Nuclear Information System (INIS)

Moskowitz, P.D.; Pardi, R.; Fthenakis, V.M.; Holtzman, S.; Sun, L.C.; Rambaugh, J.O.; Potter, S.

1996-02-01

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

Marine environmental monitoring related to sea disposal of radioactive waste in the NE Atlantic Ocean

International Nuclear Information System (INIS)

Bettencourt, A.O.; Elias, M.D.T.; Ferrador, G.C.

1988-01-01

Reference is made to the sea disposal of packaged radioactive waste in the NE Atlantic and to the role of the OCDE Nuclear Energy Agency (NEA) since 1967, in the dumping operations. The objectives of marine environmental monitoring in relation to sea disposal of radioactive wastes are described as well as the coordinated research and environmental surveillance programme (CRESP) developed within NEA frame. The Portuguese on-going programme in this field is presented and the results concerning measurements of 239+240 Pu, 238 Pu, 241 Am and 137 Cs in samples of water, sediments and fish collected at Madeira and Continental Portuguese coasts, are discussed. It was observed that these radionuclides concentrations are lower for deep-sea fishes than for the shallow-water ones. The obtained results are compared with those found in the literature. From the observation of the large spectrum of results available, it can be concluded that no generalized contamination of the marine environment due to the sea dumping of radioactive wastes if observed at present. On the other hand, there is an interest in pursuing analyses of deep-sea fish with the aim of early detection of any possible modifications in the actual levels of radioactivity in the marine environment. (author) [pt

Commercial mixed waste treatment and disposal

International Nuclear Information System (INIS)

Vance, J.K.

1994-01-01

At the South Clive, Utah, site, Envirocare of Utah, Inc., (Envirocare), currently operates a commercial low-activity, low-level radioactive waste facility, a mixed waste RCRA Part B storage and disposal facility, and an 11e.(2) disposal facility. Envirocare is also in the process of constructing a Mixed Waste Treatment Facility. As the nation's first and only commercial treatment and disposal facility for such waste, the information presented in this segment will provide insight into their current and prospective operations

Deep geologic disposal of mixed waste in bedded salt: The Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

Rempe, N.T.

1993-01-01

Mixed waste (i.e., waste that contains both chemically hazardous and radioactive components) poses a moral, political, and technical challenge to present and future generations. But an international consensus is emerging that harmful byproducts and residues can be permanently isolated from the biosphere in a safe and environmentally responsible manner by deep geologic disposal. To investigate and demonstrate such disposal for transuranic mixed waste, derived from defense-related activities, the US Department of Energy has prepared the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. This research and development facility was excavated approximately at the center of a 600 m thick sequence of salt (halite) beds, 655 m below the surface. Proof of the long-term tectonic and hydrological stability of the region is supplied by the fact that these salt beds have remained essentially undisturbed since they were deposited during the Late Permian age, approximately 225 million years ago. Plutonium-239, the main radioactive component of transuranic mixed waste, has a half-life of 24,500 years. Even ten half-lives of this isotope - amounting to about a quarter million years, the time during which its activity will decline to background level represent only 0.11 percent of the history of the repository medium. Therefore, deep geologic disposal of transuranic mixed waste in Permian bedded salt appears eminently feasible

Calibration method based on direct radioactivity measurement for radioactive gas monitoring instruments

International Nuclear Information System (INIS)

Yoshida, Makoto; Ohi, Yoshihiro; Chida, Tohru; Wu, Youyang.

1993-01-01

A calibration method for radioactive gas monitoring instruments was studied. In the method, gaseous radioactivity standards were provided on the basis of the direct radioactivity measurement by the diffusion-in long proportional counter method (DLPC method). The radioactivity concentration of the gas mixture through a monitoring instrument was determined by sampling the known volume of the gas mixture into the proportional counter used for the DLPC method. Since oxygen in the gas mixture decreased the counting efficiency in a proportional counter, the influence on calibration was experimentally estimated. It was not serious and able to be easily corrected. By the present method, the relation between radioactivity concentration and ionization current was determined for a gas-flow ionization chamber with 1.5 l effective volume. It showed good agreement with the results in other works. (author)

Handling of radioactive waste

International Nuclear Information System (INIS)

Sanhueza Mir, Azucena

1998-01-01

Based on characteristics and quantities of different types of radioactive waste produced in the country, achievements in infrastructure and the way to solve problems related with radioactive waste handling and management, are presented in this paper. Objectives of maintaining facilities and capacities for controlling, processing and storing radioactive waste in a conditioned form, are attained, within a great range of legal framework, so defined to contribute with safety to people and environment (au)

The Assessment of Radioactive Liquid Waste Treatment Generated From The Fuel Reprocessing Plant Using Chemical Coagulation Method

International Nuclear Information System (INIS)

Kuncoro Arief, H; M Birmano, Dj

1998-01-01

Reprocessing of nuclear spent fuel produced 8 lot of radioactive liquid waste still bearing uranium and transuranium. The assessment of the radioactive liquid waste treatment with FeCI 3 as coagulant has been done. Decontamination factor and separation efficiency can be calculated from known activities of initial and post-treatment wastes. It can be concluded that some factors i.e. pH of treatment process, quantity of coagulant, mixing rate, and mixing time have influenced the treatment product

1995 Report on Hanford site land disposal restrictions for mixed waste

International Nuclear Information System (INIS)

Black, D.G.

1995-04-01

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order Milestone M-26-01E. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of land disposal restricted mixed waste at the Hanford Site. The U.S. Department of Energy, its predecessors, and contractors at the Hanford Site were involved in the production and purification of nuclear defense materials from the early 1940s to the late 1980s. These production activities have generated large quantities of liquid and solid radioactive mixed waste. This waste is subject to regulation under authority of both the Resource Conservation and Recovery Act of 1976 and Atomic Energy Act of 1954. This report covers mixed waste only. The Washington State Department of Ecology, U.S. Environmental Protection Agency, and U.S. Department of Energy have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tri-Party Agreement) to bring the Hanford Site operations into compliance with dangerous waste regulations. The Tri-Party Agreement required development of the original land disposal restrictions (LDRs) plan and its annual updates to comply with LDR requirements for radioactive mixed waste. This report is the fifth update of the plan first issued in 1990. Tri-Party Agreement negotiations completed in 1993 and approved in January 1994 changed and added many new milestones. Most of the changes were related to the Tank Waste Remediation System and these changes are incorporated into this report

1995 Report on Hanford site land disposal restrictions for mixed waste

Energy Technology Data Exchange (ETDEWEB)

Black, D.G.

1995-04-01

This report was submitted to meet the requirements of Hanford Federal Facility Agreement and Consent Order Milestone M-26-01E. This milestone requires the preparation of an annual report that covers characterization, treatment, storage, minimization, and other aspects of land disposal restricted mixed waste at the Hanford Site. The U.S. Department of Energy, its predecessors, and contractors at the Hanford Site were involved in the production and purification of nuclear defense materials from the early 1940s to the late 1980s. These production activities have generated large quantities of liquid and solid radioactive mixed waste. This waste is subject to regulation under authority of both the Resource Conservation and Recovery Act of 1976 and Atomic Energy Act of 1954. This report covers mixed waste only. The Washington State Department of Ecology, U.S. Environmental Protection Agency, and U.S. Department of Energy have entered into an agreement, the Hanford Federal Facility Agreement and Consent Order (commonly referred to as the Tri-Party Agreement) to bring the Hanford Site operations into compliance with dangerous waste regulations. The Tri-Party Agreement required development of the original land disposal restrictions (LDRs) plan and its annual updates to comply with LDR requirements for radioactive mixed waste. This report is the fifth update of the plan first issued in 1990. Tri-Party Agreement negotiations completed in 1993 and approved in January 1994 changed and added many new milestones. Most of the changes were related to the Tank Waste Remediation System and these changes are incorporated into this report.

Options open to a small country, like Slovenia, in relation to radioactive waste disposal

International Nuclear Information System (INIS)

Kontic, B.

1996-01-01

When a society of two million people, who live on scarcely 20500 km 2 , needs to plan, and afterwards to implement, a strategy for radioactive waste management, the first step in the process is to look round and ask its bigger, stronger and more experienced neighbours (neighbouring countries), how they performed that task. Unfortunately, it is usually found that only few of the numerous answers to these questions and sub-questions are suitable for questioner. So what is to be done when the society is a Mediterranean, Central European, relatively highly populated country, where the Gross Domestic Product (GDP) per capita in 1994 exceeded 7000 US dollars, where the territory is mainly intended for residence, tourism and agricultural purposes, and where there is only one nuclear power plant (NPP) and one uranium mill which are responsible for the greatest part of the highly undesired radioactive waste ? The producers of radioactive wastes, and the economy of the country as a whole, cannot afford the costs of seeking a unique way of disposing of those wastes, but nevertheless, answers to the two primary questions concerning radioactive waste management should be given in any case. First: What should be done with the radioactive wastes produced in one NPP (PWR, 632 MWe) during 35 years of operation (up to 8000 m 3 of low - and intermediate - level waste, about 600 tons of spent fuel), and a uranium mill closed after only six years of ore-processing operation (670000 tons of ore-processing wastes)? Second: Where should it be done? Both questions pose the problem of siting, environmental assessment and the appropriateness of (all kinds of) criteria. In this paper the situation in Slovenia is presented with emphasis on the possibility and feasibility of radioactive waste disposal. Methodology and criteria for site evaluation and site selection for low- and intermediate- level radioactive waste (LILW) disposal is described. Fifty-five criteria are included in a decision

Radioactivity in waters in SR Slovenia

International Nuclear Information System (INIS)

Kobal, I.; Mihailovic, M.; Shkofljanec, M.; Zhlebnik, L.; Drobne, F.

1977-12-01

The radioactivity of samples of rivers Brebovscica and Sava with its contributaries was monitored. The Brebovscica was found to have an enchanced radioactivity due to the geological and mining excavations in the uranium mine Zirovski vrh. This radioactivity is lowered by a dillution in the Poljanska Sora where the radioactive contamination has been hardly detected. The radioactivity in the Sava is relatively low though a few places with enchanced values were found may be due to radioactive pollutants from conventional industries. But this ought to be confirmed in the future

Radioactive waste management in Mexico

International Nuclear Information System (INIS)

Paredes, L.; Reyes L, J.; Jimenez D, J.

2000-01-01

This paper describes the radioactive waste management in Mexico, particularly the activities that the National Institute of Nuclear Research (NINR) is undertaking in this field. Classification and annual generation of radioactive waste, together with practices and facilities relating to the management of radioactive waste are addressed. The respective national legal framework and policy are outlined. (author)

Counting statistics in radioactivity measurements

International Nuclear Information System (INIS)

Martin, J.

1975-01-01

The application of statistical methods to radioactivity measurement problems is analyzed in several chapters devoted successively to: the statistical nature of radioactivity counts; the application to radioactive counting of two theoretical probability distributions, Poisson's distribution law and the Laplace-Gauss law; true counting laws; corrections related to the nature of the apparatus; statistical techniques in gamma spectrometry [fr

Methodology to remediate a mixed waste site

International Nuclear Information System (INIS)

Berry, J.B.

1994-08-01

In response to the need for a comprehensive and consistent approach to the complex issue of mixed waste management, a generalized methodology for remediation of a mixed waste site has been developed. The methodology is based on requirements set forth in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and the Resource Conservation and Recovery Act (RCRA) and incorporates ''lessons learned'' from process design, remediation methodologies, and remediation projects. The methodology is applied to the treatment of 32,000 drums of mixed waste sludge at the Oak Ridge K-25 Site. Process technology options are developed and evaluated, first with regard to meeting system requirements and then with regard to CERCLA performance criteria. The following process technology options are investigated: (1) no action, (2) separation of hazardous and radioactive species, (3) dewatering, (4) drying, and (5) solidification/stabilization. The first two options were eliminated from detailed consideration because they did not meet the system requirements. A quantitative evaluation clearly showed that, based on system constraints and project objectives, either dewatering or drying the mixed waste sludge was superior to the solidification/stabilization process option. The ultimate choice between the drying and the dewatering options will be made on the basis of a technical evaluation of the relative merits of proposals submitted by potential subcontractors

Methodology to remediate a mixed waste site

Energy Technology Data Exchange (ETDEWEB)

Berry, J.B.

1994-08-01

In response to the need for a comprehensive and consistent approach to the complex issue of mixed waste management, a generalized methodology for remediation of a mixed waste site has been developed. The methodology is based on requirements set forth in the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and the Resource Conservation and Recovery Act (RCRA) and incorporates ``lessons learned`` from process design, remediation methodologies, and remediation projects. The methodology is applied to the treatment of 32,000 drums of mixed waste sludge at the Oak Ridge K-25 Site. Process technology options are developed and evaluated, first with regard to meeting system requirements and then with regard to CERCLA performance criteria. The following process technology options are investigated: (1) no action, (2) separation of hazardous and radioactive species, (3) dewatering, (4) drying, and (5) solidification/stabilization. The first two options were eliminated from detailed consideration because they did not meet the system requirements. A quantitative evaluation clearly showed that, based on system constraints and project objectives, either dewatering or drying the mixed waste sludge was superior to the solidification/stabilization process option. The ultimate choice between the drying and the dewatering options will be made on the basis of a technical evaluation of the relative merits of proposals submitted by potential subcontractors.

Method of processing solidification product of radioactive waste

International Nuclear Information System (INIS)

Daime, Fumiyoshi.

1988-01-01

Purpose: To improve the long-time stability of solidification products by providing solidification products with liquid tightness, gas tightness, abrasion resistance, etc., of the products in the course of the solidification for the treatment of radioactive wastes. Method: The surface of solidification products prepared by mixing solidifying agents with powder or pellets is entirely covered with high molecular polymer such as epoxy resin. The epoxy resin has excellent properties such as radiation-resistance, heat resistance, water proofness and chemical resistance, as well as have satisfactory mechanical properties. This can completely isolate the solidification products of radioactive wastes from the surrounding atmosphere. (Yoshino, Y.)

Transport of radioactive materials

International Nuclear Information System (INIS)

1991-07-01

The purpose of this Norm is to establish, relating to the TRANSPORT OF RADIOACTIVE MATERIALS, safety and radiological protection requirements to ensure an adequate control level of the eventual exposure of persons, properties and environment to the ionizing radiation comprising: specifications on radioactive materials for transport; package type selection; specification of the package design and acceptance test requirements; arrangements relating to the transport itself; administrative requirements and responsibilities. (author)

The Mixed Waste Management Facility. Preliminary design review

International Nuclear Information System (INIS)

1995-01-01

This document presents information about the Mixed Waste Management Facility. Topics discussed include: cost and schedule baseline for the completion of the project; evaluation of alternative options; transportation of radioactive wastes to the facility; capital risk associated with incineration; radioactive waste processing; scaling of the pilot-scale system; waste streams to be processed; molten salt oxidation; feed preparation; initial operation to demonstrate selected technologies; floorplans; baseline revisions; preliminary design baseline; cost reduction; and project mission and milestones

Integrated data base for 1990: US spent fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1990-10-01

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1989. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 22 refs., 48 figs., 109 tabs

Integrated Data Base for 1991: US spent fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1991-10-01

The Integrated Data Base (IDB) Program has compiled current data on inventories and characteristics of commercial spent fuel and both commercial and US government-owned radioactive wastes through December 31, 1990. These data are based on the most reliable information available form government sources, the open literature, technical reports, and direct contacts. The current projections of future waste and spent fuel to be generated generally through the year 2020 and characteristics of these materials are also presented. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration (DOE/EIA) projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered are spent fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the year 2020, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 160 refs., 61 figs., 142 tabs

Upfront Delisting of F006 Mixed Waste

International Nuclear Information System (INIS)

Poulos, D.G.; Pickett, J.B.; Jantzen, C.M.

1995-01-01

The US DOE at the Savannah River Site will petition the US EPA to upfront delist treatment residues generated from the vitrification of approximately 650,000 gallons of a regulated mixed (hazardous and radioactive) waste. The upfront petition, based on bench-scale treatability studies and pilot-scale system data, will exclude the vitrified wasteform from hazardous waste management regulations. The EPA encourages the use of the upfront delisting method as it allows applicants prior knowledge of waste specific treatment standards, which when met will render the waste non-hazardous, before generating the final wasteform. To meet the EPA performance based treatment standards, the waste must be stabilized to control the leaching of hazardous and radioactive constituents from the final wasteform. SRS has contracted a vendor to stabilize the mixed waste in a temporary Vitrification Treatment Facility (VTF). The EPA has declared vitrification as the Best Demonstrated Available Technology for high level radioactive wastes and the DOE Office of Technology Development has taken the position that mixed waste needs to be stabilized to the highest degree possible to ensure that the resulting wasteform meets both current and future regulatory specifications. Treatability studies conducted on a VTF pilot-scale system unit indicates that the mixed waste can be converted into a highly durable glass form, which exceeds the projected EPA performance based criteria. Upfront petitions can be processed by the EPA concurrently during facility construction or permitting activities; therefore, the SRS VTF will be capable of producing wastes which are considered non-hazardous sooner than otherwise expected. At the same time, EPA imposed conditional testing requirements to verify that the delisting levels are achieved by the fully operational VTF, ensures that only non-hazardous wastes are removed from hazardous waste management regulations. Vitrification of the (Abstract Truncated)

Rapid screening of radioactivity in food for emergency response.

Science.gov (United States)

Bari, A; Khan, A J; Semkow, T M; Syed, U-F; Roselan, A; Haines, D K; Roth, G; West, L; Arndt, M

2011-06-01

This paper describes the development of methods for the rapid screening of gross alpha (GA) and gross beta (GB) radioactivity in liquid foods, specifically, Tang drink mix, apple juice, and milk, as well as screening of GA, GB, and gamma radioactivity from surface deposition on apples. Detailed procedures were developed for spiking of matrices with (241)Am (alpha radioactivity), (90)Sr/(90)Y (beta radioactivity), and (60)Co, (137)Cs, and (241)Am (gamma radioactivity). Matrix stability studies were performed for 43 days after spiking. The method for liquid foods is based upon rapid digestion, evaporation, and flaming, followed by gas proportional (GP) counting. For the apple matrix, surface radioactivity was acid-leached, followed by GP counting and/or gamma spectrometry. The average leaching recoveries from four different apple brands were between 63% and 96%, and have been interpreted on the basis of ion transport through the apple cuticle. The minimum detectable concentrations (MDCs) were calculated from either the background or method-blank (MB) measurements. They were found to satisfy the required U.S. FDA's Derived Intervention Levels (DILs) in all but one case. The newly developed methods can perform radioactivity screening in foods within a few hours and have the potential to capacity with further automation. They are especially applicable to emergency response following accidental or intentional contamination of food with radioactivity. Published by Elsevier Ltd.

Rapid screening of radioactivity in food for emergency response

International Nuclear Information System (INIS)

Bari, A.; Khan, A.J.; Semkow, T.M.; Syed, U.-F.; Roselan, A.; Haines, D.K.; Roth, G.; West, L.; Arndt, M.

2011-01-01

This paper describes the development of methods for the rapid screening of gross alpha (GA) and gross beta (GB) radioactivity in liquid foods, specifically, Tang drink mix, apple juice, and milk, as well as screening of GA, GB, and gamma radioactivity from surface deposition on apples. Detailed procedures were developed for spiking of matrices with 241 Am (alpha radioactivity), 90 Sr/ 90 Y (beta radioactivity), and 60 Co, 137 Cs, and 241 Am (gamma radioactivity). Matrix stability studies were performed for 43 days after spiking. The method for liquid foods is based upon rapid digestion, evaporation, and flaming, followed by gas proportional (GP) counting. For the apple matrix, surface radioactivity was acid-leached, followed by GP counting and/or gamma spectrometry. The average leaching recoveries from four different apple brands were between 63% and 96%, and have been interpreted on the basis of ion transport through the apple cuticle. The minimum detectable concentrations (MDCs) were calculated from either the background or method-blank (MB) measurements. They were found to satisfy the required U.S. FDA's Derived Intervention Levels (DILs) in all but one case. The newly developed methods can perform radioactivity screening in foods within a few hours and have the potential to capacity with further automation. They are especially applicable to emergency response following accidental or intentional contamination of food with radioactivity.

Transport of radioactive materials

International Nuclear Information System (INIS)

1988-07-01

The norm which establishes the requirements of radiation protection and safety related to the transport of radioactive materials, aiming to keep a suitable control level of eventual exposure of personnels, materials and environment of ionizing radiation, including: specifications on radioactive materials for transport, selection of package type; specification of requirements of the design and assays of acceptance of packages; disposal related to the transport; and liability and administrative requirements, are presented. This norm is applied to: truckage, water carriage and air service; design, fabrication, assays and mantenaince of packages; preparation, despatching, handling, loading storage in transition and reception in the ultimate storage of packages; and transport of void packages which have been contained radioactive materials. (M.C.K.) [pt

Integrated data base for 1993: US spent fuel and radioactive waste inventories, projections, and characteristics. Revision 9

Energy Technology Data Exchange (ETDEWEB)

Klein, J.A.; Storch, S.N.; Ashline, R.C. [and others

1994-03-01

The Integrated Data Base (IDB) Program has compiled historic data on inventories and characteristics of both commercial and DOE spent fuel; also, commercial and U.S. government-owned radioactive wastes through December 31, 1992. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest U.S. Department of Energy/Energy Information Administration (DOE/EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional (I/I) activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste (HLW), transuranic (TRU), waste, low-level waste (LLW), commercial uranium mill tailings, environmental restoration wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) LLW. For most of these categories, current and projected inventories are given through the calendar-year (CY) 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal.

Application of a glass furnace system to low-level radioactive and mixed waste disposal

International Nuclear Information System (INIS)

Klinger, L.; Armstrong, K.

1986-01-01

In 1981 Mound began a study to determine the feasibility of using an electrically heated glass furnace for the treatment of low-level radioactive wastes generated at commercial nuclear power facilities. Experiments were designed to determine: Whether the technology offered solutions to industry waste disposal problems, and if so; whether is could meet what were thought to be critical requirements for radioactive thermal waste processing. These requirements include: high quality combustion of organic constituents, capture and immobilization of radioactivity, integrity of final waste form, and cost effectiveness. To address these questions a variety of wastes typical of the types generated by nuclear power facilities, including not only standard trash but also wastes of high aqueous and/or inorganic content, were spiked with waste radioisotopes predominant in plant wastes and processed in the glass furnace. The results of this study indicate that the unit is capable of fully meeting the addressed needs of the nuclear industry for power plant waste processing

324 Radiochemical engineering cells and high level vault tanks mixed waste compliance status

International Nuclear Information System (INIS)

1994-01-01

The 324 Building in the Hanford 300 Area contains Radiochemical Engineering Cells and High Level Vault tanks (the open-quotes REC/HLVclose quotes) for research and development activities involving radioactive materials. Radioactive mixed waste within this research installation, found primarily in B-Cell and three of the high level vault tanks, is subject to RCRA/DWR (open-quotes RCRAclose quotes) regulations for storage. This white paper provides a baseline RCRA compliance summary of MW management in the REC/HLV, based on best available knowledge. The REC/HLV compliance project, of which this paper is a part, is intended to achieve the highest degree of compliance practicable given the special technical difficulties of managing high activity radioactive materials, and to assure protection of human health and safety and the environment. The REC/HLV was constructed in 1965 to strict standards for the safe management of highly radioactive materials. Mixed waste in the REC/HLV consists of discarded tools and equipment, dried feed stock from nuclear waste melting experiments, contaminated particulate matter, and liquid feed stock from various experimental programs in the vault tanks. B-Cell contains most of these materials. Total radiological inventory in B-Cell is estimated at 3 MCi, about half of which is potentially open-quotes dispersibleclose quotes, that is, it is in small pieces or mobile particles. Most of the mixed waste currently in the REC/HLV was generated or introduced before mixed wastes were subjected to RCRA in 1987

Mixed waste management options

International Nuclear Information System (INIS)

Owens, C.B.; Kirner, N.P.

1992-01-01

Currently, limited storage and treatment capacity exists for commercial mixed waste streams. No commercial mixed waste disposal is available, and it has been estimated that if and when commercial mixed waste disposal becomes available, the costs will be high. If high disposal fees are imposed, generators may be willing to apply extraordinary treatment or regulatory approaches to properly dispose of their mixed waste. This paper explores the feasibility of several waste management scenarios and management options. Existing data on commercially generated mixed waste streams are used to identify the realm of mixed waste known to be generated. Each waste stream is evaluated from both a regulatory and technical perspective in order to convert the waste into a strictly low-level radioactive or a hazardous waste. Alternative regulatory approaches evaluated in this paper include a delisting petition) no migration petition) and a treatability variance. For each waste stream, potentially available treatment options are identified that could lead to these variances. Waste minimization methodology and storage for decay are also considered. Economic feasibility of each option is discussed broadly. Another option for mixed waste management that is being explored is the feasibility of Department of Energy (DOE) accepting commercial mixed waste for treatment, storage, and disposal. A study has been completed that analyzes DOE treatment capacity in comparison with commercial mixed waste streams. (author)

Compatibility of packaging components with simulant mixed waste

International Nuclear Information System (INIS)

Nigrey, P.J.; Dickens, T.G.

1996-01-01

The purpose of hazardous and radioactive materials packaging is to enable these materials to be transported without posing a threat to the health or property of the general public. To achieve this aim, regulations in the US have been written establishing general design requirements for such packagings. While no regulations have been written specifically for mixed waste packaging, regulations for the constituents of mixed wastes, i.e., hazardous and radioactive substances, have been codified by the US Department of Transportation (US DOT, 49 CFR 173) and the US Nuclear Regulatory Commission (NRC, 10 CFR 71). Based on these national requirements, a Chemical Compatibility Testing Program was developed in the Transportation Systems Department at Sandia National Laboratories (SNL). The program provides a basis to assure any regulatory body that the issue of packaging material compatibility towards hazardous and radioactive materials has been addressed. In this paper, the authors present the results of the second phase of this testing program. The first phase screened five liner materials and six seal materials towards four simulant mixed wastes. This phase involved the comprehensive testing of five candidate liner materials to an aqueous Hanford Tank simulant mixed waste. The comprehensive testing protocol involved exposing the respective materials a matrix of four gamma radiation doses (∼ 1, 3, 6, and 40 kGy), three temperatures (18, 50, and 60 C), and four exposure times (7, 14, 28, and 180 days). Following their exposure to these combinations of conditions, the materials were evaluated by measuring five material properties. These properties were specific gravity, dimensional changes, hardness, stress cracking, and mechanical properties

Early-stage bioassay for monitoring radioactive contamination in living livestock.

Science.gov (United States)

Yamaguchi, Toshiro; Sawano, Kaita; Kishimoto, Miori; Furuhama, Kazuhisa; Yamada, Kazutaka

2012-12-01

Soil samples from the ground surface and feces and blood from a mixed-breed male pig were collected on April 10, 2011 at a farm within 20 km of the Fukushima Daiichi nuclear power plant. The radioactivity of each sample was measured using a Ge semiconductor detector. Despite the fact that the pig had been fed non-contaminated imported feed, (131)I, (134)Cs and (137)Cs were detected in the feces, and (134)Cs and (137)Cs were detected in the blood clots. Because it is considerably difficult to measure radioactive contamination in the edible muscle of living livestock, bioassays are an option for the screening of radioactive contamination in living livestock to ensure food safety.

Use of fixation techniques in processing radioactive wastes from nuclear power plants in Czechoslovakia

International Nuclear Information System (INIS)

Seliga, M.

1977-01-01

The current state of radioactive waste disposal from the Bohunice nuclear power plant is described. The method of vacuum cementation was chosen for solidifying liquid radioactive wastes. This method makes it possible to obtain a product whose properties, namely strength, leachability, and radiation stability allow for the production of blocks without packing material. Also solved was the fixation of liquid radioactive waste using bituminization based on mixing liquid radioactive waste with aqueous bitumen emulsion in a film evaporator in which the mixture of liquid radioactive wastes and bitumen emulsion evaporate producing solid bitumen. The parameters are given of the cementation and bituminization lines which are designed for use in nuclear power plants with WWER type reactors. (J.B.)

Conceptual Design Report: Nevada Test Site Mixed Waste Disposal Facility Project

International Nuclear Information System (INIS)

2009-01-01

Environmental cleanup of contaminated nuclear weapons manufacturing and test sites generates radioactive waste that must be disposed. Site cleanup activities throughout the U.S. Department of Energy (DOE) complex are projected to continue through 2050. Some of this waste is mixed waste (MW), containing both hazardous and radioactive components. In addition, there is a need for MW disposal from other mission activities. The Waste Management Programmatic Environmental Impact Statement Record of Decision designates the Nevada Test Site (NTS) as a regional MW disposal site. The NTS has a facility that is permitted to dispose of onsite- and offsite-generated MW until November 30, 2010. There is not a DOE waste management facility that is currently permitted to dispose of offsite-generated MW after 2010, jeopardizing the DOE environmental cleanup mission and other MW-generating mission-related activities. A mission needs document (CD-0) has been prepared for a newly permitted MW disposal facility at the NTS that would provide the needed capability to support DOE's environmental cleanup mission and other MW-generating mission-related activities. This report presents a conceptual engineering design for a MW facility that is fully compliant with Resource Conservation and Recovery Act (RCRA) and DOE O 435.1, 'Radioactive Waste Management'. The facility, which will be located within the Area 5 Radioactive Waste Management Site (RWMS) at the NTS, will provide an approximately 20,000-cubic yard waste disposal capacity. The facility will be licensed by the Nevada Division of Environmental Protection (NDEP)

Modeling approach to various time and spatial scale environmental issues in Fukushima. Related to radioactive cesium migration in aquatic systems

International Nuclear Information System (INIS)

Kurikami, Hiroshi; Kitamura, Akihiro; Yamada, Susumu; Machida, Masahiko

2015-01-01

Several numerical models have been prepared to deal with various time- and spatial-scale issues related to radioactive cesium migration in environment in Fukushima area. The SACT (Soil and Cesium Transport) model developed by the Japan Atomic Energy Agency (JAEA) predicts middle- to long-term evolution of radioactive cesium distribution due to soil erosion, subsequent sediment transport and deposition, and radioactive cesium migration based on the Universal Soil Loss Equation (USLE). The TODAM (Time-dependent One-dimensional Degradation and Migration) model, iRIC/Nays2D and the FLESCOT (Flow, Energy, Salinity, Sediment, Contaminant Transport) model are one-, two- and three-dimensional river/reservoir/coastal models, respectively. Based on conservation equations of sediment and radioactive cesium, they treat advection and diffusion of suspended sediment and cesium, deposition of sediment to bed, re-suspension from bed and adsorption/desorption of radioactive cesium. These models are suitable for small and short time scale issues such as high discharges of sediment and radioactive cesium from rivers due to heavy rainfall events. This paper describes fragments of the JAEA’s approaches of modeling to deal with the issues corresponding to radioactive cesium migration in environment with some case studies. (author)

Role of disposal in developing Federal Facility Compliance Act mixed waste treatment plans

International Nuclear Information System (INIS)

Case, J.T.; Rhoderick, J.

1994-01-01

The Federal Facilities Compliance Act (FFCA) was enacted on October 6, 1992. This act amends the Solid Waste Disposal Act, which was previously amended by the Resource Conservation and Recovery Act (RCRA). The FFCA set in place a process for managing the Department of Energy's (DOE) mixed low-level radioactive wastes (MLLW), wastes that contain both hazardous and low-level radioactive constituents, with full participation of the affected states. The FFCA provides the framework for the development of treatment capacity for DOE's mixed waste. Disposal of the treatment residues is not addressed by the FFCA. DOE has initiated efforts in concert with the states in the development of a disposal strategy for the treated mixed wastes. This paper outlines DOE efforts in development of a mixed waste disposal strategy which is integrated with the FFCA Site Treatment Planning process

Treatment of radioactive silts and soils with organic materials

International Nuclear Information System (INIS)

Sobolev, I.A.; Barinov, A.S.; Dmitriev, S.A.; Lifanov, F.A.; Varlakov, A.P.; Karlin, S.V.

1997-01-01

Moscow SIA RADON is developing the ''Clinker'' method to treat radioactive silts and grounds. The ''Clinker'' method consists of radioactive silt (ground) mixed with lime and other components. This mixture is calcined at 800 to 1000 o C. The product is ground to a surface area size of 2500 to 4500 cm 2 /g, mixed with water at a water-to-cement ratio not less than 0.25, and aged to form a solid monolith. The ''Clinker'' method was compared to the traditional cementation methods. The ''Clinker'' method reduces the final volume and enhance the strength characteristics of the final product. The ''Clinker'' cement compound has higher hardening rate. Preliminary data show that it has higher cold resistance, sulfate and leaching corrosion durability in comparison to one prepared by the traditional cementation method. The range of applicability of the ''Clinker'' method is increased by the possibility of treating materials containing up to 80% (mass) of organic materials, such as turf, flora and fauna decomposition products, and manmade material, including natural materials, such as petroleum products and polymers. In addition, the ''Clinker'' method does not require expensive waste binders, i.e., cement. The ''Clinker'' cement can be used for cementation of other radioactive waste. (author)

Treatment of mixed radioactive liquid wastes at Argonne National Laboratory

International Nuclear Information System (INIS)

Vandegrift, G.F.; Chamberlain, D.B.; Conner, C.

1994-01-01

Aqueous mixed waste at Argonne National Laboratory (ANL) is traditionally generated in small volumes with a wide variety of compositions. A cooperative effort at ANL between Waste Management (WM) and the Chemical Technology Division (CMT) was established, to develop, install, and implement a robust treatment operation to handle the majority of such wastes. For this treatment, toxic metals in mixed-waste solutions are precipitated in a semiautomated system using Ca(OH) 2 and, for some metals, Na 2 S additions. This step is followed by filtration to remove the precipitated solids. A filtration skid was built that contains several filter types which can be used, as appropriate, for a variety of suspended solids. When supernatant liquid is separated from the toxic-metal solids by decantation and filtration, it will be a low-level waste (LLW) rather than a mixed waste. After passing a Toxicity Characteristic Leaching Procedure (TCLP) test, the solids may also be treated as LLW

Method of handling radioactive alkali metal waste

Science.gov (United States)

Wolson, R.D.; McPheeters, C.C.

Radioactive alkali metal is mixed with particulate silica in a rotary drum reactor in which the alkali metal is converted to the monoxide during rotation of the reactor to produce particulate silica coated with the alkali metal monoxide suitable as a feed material to make a glass for storing radioactive material. Silica particles, the majority of which pass through a 95 mesh screen or preferably through a 200 mesh screen, are employed in this process, and the preferred weight ratio of silica to alkali metal is 7 to 1 in order to produce a feed material for the final glass product having a silica to alkali metal monoxide ratio of about 5 to 1.

Method of handling radioactive alkali metal waste

International Nuclear Information System (INIS)

Mcpheeters, C.C.; Wolson, R.D.

1980-01-01

Radioactive alkali metal is mixed with particulate silica in a rotary drum reactor in which the alkali metal is converted to the monoxide during rotation of the reactor to produce particulate silica coated with the alkali metal monoxide suitable as a feed material to make a glass for storing radioactive material. Silica particles, the majority of which pass through a 95 mesh screen or preferably through a 200 mesh screen, are employed in this process, and the preferred weight ratio of silica to alkali metal is 7 to 1 in order to produce a feed material for the final glass product having a silica to alkali metal monoxide ratio of about 5 to 1

Hazardous chemical and radioactive wastes at Hanford

International Nuclear Information System (INIS)

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

1991-07-01

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

Hazardous chemical and radioactive wastes at Hanford

International Nuclear Information System (INIS)

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

1993-01-01

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 were built at Hanford for plutonium production. Generally, Hanford's 100 Area was dedicated to reactor operation; the 200 Areas 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 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 chemicals as well as radioactive constituents. This paper focuses 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

K. Radioactive waste management

International Nuclear Information System (INIS)

1976-01-01

Radioactive waste management is a controversial and emotive subject. This report discusses radioactivity hazards which arise from each stage of the fuel cycle and then relates these hazards to the New Zealand situation. There are three appendices, two of which are detailed considerations of a paper by Dr. B.L.Cohen

[Nationwide survey on radioactive waste management related to positron emission tomography in Japan].

Science.gov (United States)

Nagaoka, Hiroaki; Watanabe, Hiroshi; Yamaguchi, Ichiro; Fujibuchi, Toshioh; Kida, Tetsuo; Tanaka, Shinji

2009-12-20

A clearance system for medical radioactive solid waste has not yet been implemented in Japan. Since 2004 new regulations have allowed institutions using positron emission tomography(PET)to handle totally decayed radioactive waste as non-radioactive waste after decay-in-storage. It was expected that this new regulation would mediate the installation of clearance systems in Japan. In order to assess the current situation of radiation safety management in PET institutions, we conducted a nationwide survey. The study design was a cross-sectional descriptive study conducted by questionnaire. The subjects of this survey were all the PET institutions in Japan. Among 224 institutes, 128 institutes are equipped with cyclotrons and 96 institutes are not. The number of returned questionnaires was 138. Among institutes that are using delivered radiopharmaceuticals, 80% treat their waste as non-radioactive according to the new regulation. The impact of new regulations for reducing radioactive waste in PET institutes without a cyclotron was estimated at about $400 thousand per year. The main concern of medical institutes was assessment of the contamination caused by by-products of radioactive nuclides generated in target water during the operation of a cyclotron. It was thought that a rational rule based on scientific risk management should be established because these by-products of radioactive nuclides are negligible for radiation safety. New regulation has had a good influence on medical PET institutes, and it is expected that a clearance system for medical radioactive waste will be introduced in the near future, following these recent experiences in PET institutes.

Development of a mixed waste management facility at the Nevada Test Site

International Nuclear Information System (INIS)

Dolenc, M.R.; Kendall, E.W.

1989-01-01

The US Department of Energy (DOE) produces some radioactive low-level wastes (LLW) which contain hazardous components. By definition, the management of those mixed wastes (MW) at the Nevada Test Site (NTS) requires compliance with US Environmental Protection Agency (EPA) and state of Nevada regulations for hazardous wastes, and DOE regulations for LLW. Preparations for operation of a separate Mixed Waste Management Unit (MWMU) in the 1990s are underway. The 167-acre MWMU will be a part of the 732-acre Area 5 Radioactive Waste Management Site (RWMS). The MWMU is being developed in response to a DOE Office of Defense Waste and Transporation Management need to provide enhanced capabilities and facilities for safe, secure, and efficient disposal of defense-related MW in accordance with DOE, EPA, and state of Nevada requirements. Planned activities relating to the development of the MWMU include completing National Environmental Policy Act (NEPA) requirements; responding to any notices of deficiencies (NODs) on the NTS Part B Permit application; conducting generator audits as part of the NTS MW certification program; optimizing the design and operation of the vadose zone monitoring system; developing protocols for the sampling and analysis of MW, and facility construction. This paper describes the permitting and regulatory environment, the specific application of the permit process to the NTS, and the phased development of an MWMU at the NTS

Immobilization of hazardous and radioactive waste into glass structures

International Nuclear Information System (INIS)

Wicks, G.G.

1997-01-01

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. In addition to immobilization of HLW glass matrices are also being considered for isolation of many other types of hazardous materials, both radioactive as well as nonradioactive. This includes vitrification of various actinides resulting from clean-up operations and the legacy of the cold war, as well as possible immobilization of weapons grade plutonium resulting from disarmament activities. Other types of wastes being considered for immobilization into glasses include transuranic wastes, mixed wastes, contaminated

Hazardous and mixed waste transportation program

International Nuclear Information System (INIS)

Hohnstreiter, G.F.; Glass, R.E.; McAllaster, M.E.; Nigrey, P.J.; Trennel, A.J.; Yoshimura, H.R.

1993-01-01

Sandia National Laboratories (SNL) has developed a program to address the packaging needs associated with the transport of hazardous and mixed waste during the United States' Department of Energy (DOE) remediation efforts. The program addresses the technology needs associated with the transport of materials which have components that are radioactive and chemically hazardous. The mixed waste transportation activities focus on on-site specific applications of technology to the transport of hazardous and mixed wastes. These activities were identified at a series of DOE-sponsored workshops. These activities will be composed of the following: (1) packaging concepts, (2) chemical compatibility studies, and (3) systems studies. This paper will address activities in each of these areas. (J.P.N.)

Hazardous and Mixed Waste Transportation Program

International Nuclear Information System (INIS)

Hohnstreiter, G.F.; Glass, R.E.; McAllaster, M.E.; Nigrey, P.J.; Trennel, A.J.; Yoshimura, H.R.

1991-01-01

Sandia National Laboratories (SNL) has developed a program to address the packaging needs associated with the transport of hazardous and mixed waste during the United States' Department of Energy (DOE) remediation efforts. The program addresses the technology needs associated with the transport of materials which have components that are radioactive and chemically hazardous. The mixed waste transportation activities focus on on-site specific applications of technology to the transport of hazardous and mixed wastes. These activities were identified at a series of DOE-sponsored workshops. These activities will be composed of the following: (1) packaging concepts, (2) chemical compatibility studies, and (3) systems studies. This paper will address activities in each of these areas

Effects of mixed waste simulants on transportation packaging plastic components

International Nuclear Information System (INIS)

Nigrey, P.J.; Dickens, T.G.

1994-01-01

The purpose of hazardous and radioactive materials packaging is to, enable these materials to be transported without posing a threat to the health or property of the general public. To achieve this aim, regulations have been written establishing general design requirements for such packagings. While no regulations have been written specifically for mixed waste packaging, regulations for the constituents of mixed wastes, i.e., hazardous and radioactive substances, have been codified. The design requirements for both hazardous and radioactive materials packaging specify packaging compatibility, i.e., that the materials of the packaging and any contents be chemically compatible with each other. Furthermore, Type A and Type B packaging design requirements stipulate that there be no significant chemical, galvanic, or other reaction between the materials and contents of the package. Based on these requirements, a Chemical Compatibility Testing Program was developed in the Transportation Systems Department at Sandia National Laboratories (SNL). The program, supported by the US Department of Energy's (DOE) Transportation Management Division, EM-261 provides the means to assure any regulatory body that the issue of packaging material compatibility towards hazardous and radioactive materials has been addressed. In this paper, we describe the general elements of the testing program and the experimental results of the screening tests. The implications of the results of this testing are discussed in the general context of packaging development. Additionally, we present the results of the first phase of this experimental program. This phase involved the screening of five candidate liner and six seal materials against four simulant mixed wastes

Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions.

Integrated data base report - 1994: US spent nuclear fuel and radioactive waste inventories, projections, and characteristics

International Nuclear Information System (INIS)

1995-09-01

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and U.S. Department of Energy (DOE) spent nuclear fuel and commercial and U.S. government-owned radioactive wastes. Except for transuranic wastes, inventories of these materials are reported as of December 31, 1994. Transuranic waste inventories are reported as of December 31, 1993. All spent nuclear fuel and radioactive waste data reported are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest DOE/Energy Information Administration (EIA) projections of U.S. commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program contaminated environmental media, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given through the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions

Comparative analysis of DOE Order 5820.2A, NRC, and EPA radioactive and mixed waste management requirements

International Nuclear Information System (INIS)

1991-07-01

As directed by DOE-Headquarters and DOE-Idaho, the Radioactive Waste Technical Support Program (TSP) drafted an analysis of DOE Order 5820. 2A on ''Radioactive Waste Management'' to develop guidelines and criteria for revising the Order. This comparative matrix is a follow up to the earlier analysis. This matrix comparing the requirements of DOE Order 5820.2A with Nuclear Regulatory Commission (NRC) and Environmental Protection Agency (EPA) regulations was prepared at the request of EM-30. The matrix compares DOE Order 5820.2A with the following: NRC regulations in 10 CFR Part 61 on ''Licensing Requirements for Land Disposal of Radioactive Waste''; NRC regulations in 10 CFR Part 60 on ''Disposal of High-Level Radioactive Waste in Geologic Repositories''; EPA regulations in 40 CFR Part 191 on ''Environmental Radiation Protection Standards for Management and Disposal of Spent Nuclear Fuel, High-Level and Transuranic Radioactive Waste''; EPA regulations in 40 FR Part 192 on ''Health and Environmental Protection Standards for Uranium and Thorium Mill Tailing''; and EPA regulations under the Resource Conservation and Recovery Act

Remotely controlled reagent feed system for mixed waste treatment Tank Farm

International Nuclear Information System (INIS)

Dennison, D.K.; Bowers, J.S.; Reed, R.K.

1995-02-01

LLNL has developed and installed a large-scale. remotely controlled, reagent feed system for use at its existing aqueous low-level radioactive and mixed waste treatment facility (Tank Farm). LLNL's Tank Farm is used to treat aqueous low-level and mixed wastes prior to vacuum filtration and to remove the hazardous and radioactive components before it is discharged to the City of Livermore Water Reclamation Plant (LWRP) via the sanitary sewer in accordance with established limits. This reagent feed system was installed to improve operational safety and process efficiency by eliminating the need for manual handling of various reagents used in the aqueous waste treatment processes. This was done by installing a delivery system that is controlled either remotely or locally via a programmable logic controller (PLC). The system consists of a pumping station, four sets of piping to each of six 6,800-L (1,800-gal) treatment tanks, air-actuated discharge valves at each tank, a pH/temperature probe at each tank, and the PLC-based control and monitoring system. During operation, the reagents are slowly added to the tanks in a preprogrammed and controlled manner while the pH, temperature, and liquid level are continuously monitored by the PLC. This paper presents the purpose of this reagent feed system, provides background related to LLNL's low-level/mixed waste treatment processes, describes the major system components, outlines system operation, and discusses current status and plans

Regulatory issues related to long-term storage and disposal of radioactive wastes in Kazakhstan

International Nuclear Information System (INIS)

Kim, A.; Romanenko, O.; Tazhibayeva, I.; Zhunussova, T.

2012-01-01

Full text: Reported material is a result of activity accomplished in the framework of cooperation program between Kazakhstan and Norway within 2009-2012. This work was divided into three distinctive parts, as follows: 1. Analysis of existing threats associated with radioactive wastes in the Republic of Kazakhstan. The objective of this part of the work was to reveal the most important threats in the sphere of radioactive waste management in the Republic of Kazakhstan, which require an increased regulatory attention. Threat assessment needed to identify: main radiological threats both for people who work with radioactive wastes and for population living near the radioactive waste storage places now and in the long term which require an increased regulatory attention; problems that need urgent and detailed analysis; and main problems in the realization of regulatory process in Kazakhstan including weakness in the regulatory and legal framework. Threat assessment analysis showed that in order to reduce the level of threats it was necessary to begin developing a national policy and strategy for radioactive waste management which need to be approved by the Government, to develop proposals for Radioactive Wastes new classification, including identification of relevant categories of Radioactive Wastes, as well as criteria for their disposal in accordance with IAEA recommendations and experience from other countries. 2. Development of new classification system for radioactive wastes in Kazakhstan. Following the results of threat assessment performed within the first stage, the objective of the second part of work was to develop a proposal to adopt a new Radioactive Wastes classification in Kazakhstan in accordance with the IAEA recommendations, including implementation of new categories, taking into account international experience and current situation in Kazakhstan. The result of this stage of work was a proposal for a new Radioactive Wastes classification and

Romanian experience in a assessment of the risk and environmental consequences due to radioactive materials transportation

International Nuclear Information System (INIS)

Vieru, Gheorghe

2006-01-01

Full text: The transport of radioactive materials (RAM) is a very important problem taking into consideration its potential risks over the environment and the radiological consequences of this activity. Romania as a Member State of the International Atomic Energy Agency has implemented national regulations for a safe transport of RAM in complying with the Agency's recommendations as well as other international specialized organizations. The paper will present the main sources of radioactive materials in Romania, and their transportation routes with a particular focus on the radioactive wastes (very low level and mixed low-level radioactive materials), radioactive isotopes and sources, and natural uranium ore. Starting from the fact that the safety in the transport of radioactive materials is dependent on packaging appropriate for the contents being shipped, rather than operational and/or administrative actions required for the package, the paper presents, very briefly, the qualification tests for the main packages used for transport and storage of RAM in Romania. There are presented also specific problems related to the identification and evaluation of the environmental risks and impacts as well as the potential radiological consequences associated with the transport of radioactive materials, for all those three possible situations: routine transport (without incidents), normal transport (with minor incidents) and during potential accidents. As a conclusion, it is stated that the evaluated annual collective dose for the population due to RAM transport is less than those received by natural radiation sources. At the same time it is concluded that Romanian made packages are safe and prevent loss of its radioactive contents into environment. (author)

Radioactive waste management policy

International Nuclear Information System (INIS)

Morrison, R.W.

1983-06-01

The speaker discusses the development of government policy regarding radioactive waste disposal in Canada, indicates overall policy objectives, and surveys the actual situation with respect to radioactive wastes in Canada. He also looks at the public perceptions of the waste management situation and how they relate to the views of governmental decision makers

Cementitious Composites for Immobilization of Radioactive Waste into Final Wasteform

International Nuclear Information System (INIS)

Varlakov, A.P.

2013-01-01

Research and development works are important on universal cementation technological processes to achieve maximal conditioning efficiency for various type wastes such as saline liquid radioactive waste (LRW), where the variants of cement composition formulations, modes of cement compounds preparation and types of equipment are minimised. This work presents the results of development of multi-component cement compositions for the complex of technological processes of different types of radioactive waste (RAW) cementation: concentrated saline LRW, concentrated boron-containing saline LRW, LRW with high surface active substances content, with residues, liquid organic radioactive waste, spent ion-exchange resins and filter-perlite powder, ash residues from solid radioactive waste (SRW) combustion, mixed closely packed and large-fragmented SRW. The research has found technological parameters of equipment and cement compositions providing reliable RAW cementation. Continuous and periodic cycle plants were developed for LRW cementation by mixing. Pouring and penetration methods were developed for SRW cementation. Based on compliance with equipment parameters, methods and cement grouts were selected for most effective technological processes of cementation. Formulations of cement compositions were developed to provide reliable preparation of cement compounds with maximal waste loading at required cement compound quality. The complex of technological processes of cementation using multi-component cement compositions allows highly efficient treatment of the wide range of RAW including problematic waste streams and wastes generated in small amounts. Rational reduction of cementation variants significantly increases economical efficiency of immobilisation. (author)

Radiological dose assessment related to management of naturally occurring radioactive materials generated by the petroleum industry

International Nuclear Information System (INIS)

Smith, K.P.; Blunt, D.L.; Williams, G.P.; Tebes, C.L.

1995-01-01

A preliminary radiological dose assessment related to equipment decontamination, subsurface disposal, landspreading, equipment smelting, and equipment burial was conducted to address concerns regarding the presence of naturally occurring radioactive materials in production waste streams. The assessment evaluated the relative dose of these activities and included a sensitivity analysis of certain input parameters. Future studies and potential policy actions are recommended

Criteria relating to the approval of consumer goods containing radioactive substances: a consultative document

International Nuclear Information System (INIS)

1980-05-01

The National Radiological Protection Board currently provides manufacturers and suppliers of consumer goods containing radioactive substances with advice on the acceptability of their products. Examples of such goods available to the public include radioluminous devices such as clocks, watches and compasses, products containing gaseous tritium light sources, ionisation chamber smoke detectors and thorium gas mantles. In the present document, detailed proposals are put forward for criteria which the Board may use when considering applications for the approval of goods containing radioactive substances to ensure that they are safe. The proposals relate to the radiation doses to consumers and others who may be exposed as a consequence of their activities, and also consider the benefits to consumers. They are concerned with doses arising during normal use, through accidents and misuse, and as a consequence of uncontrolled disposal. (U.K.)

In situ vitrification pilot-scale radioactive test

International Nuclear Information System (INIS)

Timmerman, C.L.; Oma, K.H.

1984-10-01

Pacific Northwest Laboratory (PNL) is developing in situ vitrification (ISV) as an in-place stabilization technique for selected liquid radioactive waste disposal sites. The process melts the wastes and surrounding soil to produce a durable glass and crystalline waste form. These ISV process development testing and evaluation studies are being conducted for the US Department of Energy. The results of an ISV pilot-scale test conducted in June of 1983 in which soils contaminated with actual radioactive transuranic and mixed fission product elements were vitrified are discussed. The primary objectives of the radioactive test were to: demonstrate containment and confinement of the radioactive material; verify equipment performance of the power and off-gas systems; identify losses to the off-gas system; and characterize the behavior of the radioactive material in the vitrified soil. The test successfully demonstrated the processing containment of radionuclides both within the vitrified mass and in the off-gas system. No environmental release of radioactive material was measured during testing operations. The vitrified soil had a greater than 99% retention of all radionuclides. Losses to the off-gas system varied from less than or equal to 0.03% for particulate materials (plutonium and strontium) to 0.8% for cesium which is a more volatile element. The off-gas system effectively contained both volatile and entrained radioactive materials. Analysis of the vitrified soil revealed that all radionuclides were distributed throughout the vitrified zone, some more uniformly than others. No migration of radionuclides outside the vitrification zone occurred, as indicated by analysis of soil samples from around the block. Previous waste form leaching studies indicate an acceptable durability of the ISV product. 8 references, 34 figures, 8 tables

In situ vitrification pilot-scale radioactive test

Energy Technology Data Exchange (ETDEWEB)

Timmerman, C.L.; Oma, K.H.

1984-10-01

Pacific Northwest Laboratory (PNL) is developing in situ vitrification (ISV) as an in-place stabilization technique for selected liquid radioactive waste disposal sites. The process melts the wastes and surrounding soil to produce a durable glass and crystalline waste form. These ISV process development testing and evaluation studies are being conducted for the US Department of Energy. The results of an ISV pilot-scale test conducted in June of 1983 in which soils contaminated with actual radioactive transuranic and mixed fission product elements were vitrified are discussed. The primary objectives of the radioactive test were to: demonstrate containment and confinement of the radioactive material; verify equipment performance of the power and off-gas systems; identify losses to the off-gas system; and characterize the behavior of the radioactive material in the vitrified soil. The test successfully demonstrated the processing containment of radionuclides both within the vitrified mass and in the off-gas system. No environmental release of radioactive material was measured during testing operations. The vitrified soil had a greater than 99% retention of all radionuclides. Losses to the off-gas system varied from less than or equal to 0.03% for particulate materials (plutonium and strontium) to 0.8% for cesium which is a more volatile element. The off-gas system effectively contained both volatile and entrained radioactive materials. Analysis of the vitrified soil revealed that all radionuclides were distributed throughout the vitrified zone, some more uniformly than others. No migration of radionuclides outside the vitrification zone occurred, as indicated by analysis of soil samples from around the block. Previous waste form leaching studies indicate an acceptable durability of the ISV product. 8 references, 34 figures, 8 tables.

Management of radioactive wastes produced by users of radioactive materials

International Nuclear Information System (INIS)

1985-01-01

This report is intended as a document to provide guidance for regulatory, administrative and technical authorities who are responsible for, or are involved in, planning, approving, executing and reviewing national waste management programmes related to the safe use of radioactive materials in hospitals, research laboratories, industrial and agricultural premises and the subsequent disposal of the radioactive wastes produced. It provides information and guidance for waste management including treatment techniques that may be available to establishments and individual users

Development of treatment technologies for the processing of US Department of Energy mixed waste

International Nuclear Information System (INIS)

Backus, P.M.; Berry, J.B.; Coyle, G.J.; Lurk, P.W.; Wolf, S.M.

1993-01-01

Waste contaminated with chemically hazardous and radioactive species is defined as mixed waste. Significant technology development has been conducted for separate treatment of hazardous and radioactive waste, but technology development addressing mixed-waste treatment has been limited. Management of mixed waste requires treatment which must meet the standards established by the US Environmental Protection Agency for the specific hazardous constituents while also providing adequate control of the radionuclides. Technology has not been developed, demonstrated, or tested to produce a low-risk final waste form specifically for mixed waste. Throughout the US Department of Energy (DOE) complex, mixed waste is a problem because definitive treatment standards have not been established and few disposal facilities are available. Treatment capability and capacity are also limited. Site-specific solutions to the management of mixed waste have been initiated; however, site-specific programs result in duplication of technology development between various sites. Significant progress is being made in developing technology for mixed waste under the Mixed Waste Integrated Program. The status of the technical initiatives in chemical/physical treatment, destruction/stabilization technology, off-gas treatment, and final waste form production/assessment is described in this paper

Environmental radioactivity in the Netherlands. Results in 2009

Energy Technology Data Exchange (ETDEWEB)

Knetsch, G J; Groot, M C.E. [eds.

2011-11-15

In 2009 the Netherlands fulfilled the European obligation to annually measure radioactivity in the environment and in food. According to the Euratom Treaty of 1957, all Member States of the European Union are obliged to perform these measurements each year. Euratom has provided guidelines for performing the measurements uniformly since 2000. However, Member States are not obliged to comply with these recommended guidelines. In the Netherlands, in 2009 strontium-90 was also determined (for the first time) in a mixed food package for which the above recommendations had been fulfilled. The National Institute for Public Health and the Environment (RIVM) reports on behalf of the Netherlands to the European Union about radioactivity in the environment. Moreover, this information provides background values and/or amounts of radioactivity that are present under normal circumstances. These background values can be used as reference values, for instance, during a disaster.

Synthesis and characterization of scandium oxide microspheres for their application in radioactive particle tracking experiments

International Nuclear Information System (INIS)

Goswami, Sunil; Biswal, Jayashree; Pant, H.J.; Pillai, K.T.; Bamankar, Y.R.

2012-01-01

Radioactive particle tracking (RPT) technique, proposed by Lin et al., is a noble technique for understanding mixing mechanisms of fluids and; evaluation and improvement of design of multiphase flow systems. In RPT technique the motion of a single radioactive particle is tracked in a flow system using an array of strategically mounted NaI(Tl) scintillation detectors around the system. The gamma emitting radioactive tracer particle being tracked is designed to be hydrodynamically similar to that of the phase being traced

DOE regulatory reform initiative vitrified mixed waste

International Nuclear Information System (INIS)

Carroll, S.J.; Holtzscheiter, E.W.

1997-01-01

The US Department of Energy (DOE) is charged with responsibly managing the largest volume of mixed waste in the United States. This responsibility includes managing waste in compliance with all applicable Federal and State laws and regulations, and in a cost-effective, environmentally responsible manner. Managing certain treated mixed wastes in Resource Conservation and Recovery Act (RCRA) permitted storage and disposal units (specifically those mixed wastes that pose low risks from the hazardous component) is unlikely to provide additional protection to human health and the environment beyond that afforded by managing these wastes in storage and disposal units subject to requirements for radiological control. In October, 1995, the DOE submitted a regulatory reform proposal to the Environmental Protection Agency (EPA) relating to vitrified mixed waste forms. The technical proposal supports a regulatory strategy that would allow vitrified mixed waste forms treated through a permit or other environmental compliance mechanism to be granted an exemption from RCRA hazardous waste regulation, after treatment, based upon the inherent destruction and immobilization capabilities of vitrification technology. The vitrified waste form will meet, or exceed the performance criteria of the Environmental Assessment (EA) glass that has been accepted as an international standard for immobilizing radioactive waste components and the LDR treatment standards for inorganics and metals for controlling hazardous constituents. The proposal further provides that vitrified mixed waste would be responsibly managed under the Atomic Energy Act (AEA) while reducing overall costs. Full regulatory authority by the EPA or a State would be maintained until an acceptable vitrified mixed waste form, protective of human health and the environment, is produced

Radioactive waste management in Korea

International Nuclear Information System (INIS)

Lee, Ik Hwan

1997-01-01

In order to meet the increasing energy demand in Korea, continuous promotion of nuclear power program will be inevitable in the future. However, the use of nuclear energy eventually requires effective and reliable radioactive waste management. For the safe and economical management of radioactive waste, first of all, volume reduction is essentially required and hence the development of related technologies continuously be pursued. A site for overall radioactive waste management has to be secured in Korea. KEPCO-NETEC will improve public understanding by reinforcing PA and will maintain transparency of radioactive waste management. (author). 1 fig

U.S. Department of Energy, Office of Technology Development, mixed-waste treatment research, development, demonstration, testing, and evaluation

International Nuclear Information System (INIS)

Berry, J.B.

1993-01-01

Both chemically hazardous and radioactive species contaminate mixed waste. Historically, technology has been developed to treat either hazardous or radioactive waste. Technology specifically designed to produce a low-risk final waste form for mixed low-level waste has not been developed, demonstrated, or tested. Site-specific solutions to management of mixed waste have been initiated; however, site-specific programs result in duplication of technology development effort between various sites. There is a clear need for technology designed to meet the unique requirements for mixed-waste processing and a system-wide integrated strategy for developing technology and managing mixed waste. This paper discusses the US Department of Energy (DOE) approach to addressing these unique requirements through a national technology development effort

Devoluming method of acidic radioactive liquid waste and processing system therefor

International Nuclear Information System (INIS)

Shirai, Takamori; Honda, Tadahiro

1998-01-01

Radioactive liquid wastes such as liquid wastes discharged from chemical decontamination (containing free acids, metal salts dissolved in acids, not-dissolved iron rust and radioactive metals) are introduced to an acid recovering device using a diffusion permeation membrane and separated to a deacidified liquid and separated acid liquid. The separated acid liquid mainly comprising free acids is recovered to a tank for recovered acids, and used repeatedly for removing crud. The deacidified liquid mainly comprising salts is concentrated in a reverse osmosis membrane (RO) concentration device. RO concentrated liquid containing radioactive metals is dried, and salts are decomposed in a drying/salt-decomposing device and separated into metal oxides and a mixed gas of an acidic gas and steams. The gas is cooled in an acid absorbing device and recovered as free acids. The metal oxides containing radioactive metals are solidified. (I.N.)

Development of mixed-waste analysis capability for graphite furnace atomic absorption spectrophotometry

International Nuclear Information System (INIS)

Bass, D.A.; TenKate, L.B.; Wroblewski, A.

1995-03-01

Graphite furnace atomic absorption spectrophotometer (GFAAS) are typically configured with ventilation to capture potentially toxic and corrosive gases emitted from the vaporization of sample aliquots. When radioactive elements are present, additional concerns (such as meeting safety guidelines and ALARA principles) must be addressed. This report describes a modification to a GFAAS that provides additional containment of vaporized sample aliquots. The modification was found to increase containment by a factor of 80, given expected operating conditions. The use of the modification allows more mixed-waste samples to be analyzed, permits higher levels of radioactive samples to be analyzed, or exposes the analyst to less airborne radioactivity. The containment apparatus was attached to a Perkin-Elmer Zeeman 5000 spectrophotometer for analysis of mixed-waste samples; however, it could also be used on other systems and in other applications where greater containment of vaporized material is desired

Report on the treatability study for inerting small quantities of radioactive explosives and explosive components

International Nuclear Information System (INIS)

Loyola, V.M.; Reber, S.D.

1996-02-01

As a result of Sandia's radiation hardening testing on a variety of its explosive components, radioactive waste streams were generated and have to be disposed of as radioactive waste. Due to the combined hazards of explosives and radioactivity, Sandia's Radioactive and Mixed Waste Management organization did not have a mechanism for disposal of these waste streams. This report documents the study done to provide a method for the removal of the explosive hazard from those waste streams. The report includes the design of the equipment used, procedures followed, results from waste stream analog tests and the results from the actual explosive inerting tests on radioactive samples. As a result of the inerting treatment, the waste streams were rendered non-explosive and, thus, manageable through normal radioactive waste disposal channels

Integrated Data Base report--1993: U.S. spent nuclear fuel and radioactive waste inventories, projections, and characteristics. Revision 10

Energy Technology Data Exchange (ETDEWEB)

1994-12-01

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and DOE spent nuclear fuel; also, commercial and US government-owned radioactive wastes through December 31, 1993. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 256 refs., 38 figs., 141 tabs.

Integrated Data Base report--1993: U.S. spent nuclear fuel and radioactive waste inventories, projections, and characteristics. Revision 10

International Nuclear Information System (INIS)

1994-12-01

The Integrated Data Base Program has compiled historic data on inventories and characteristics of both commercial and DOE spent nuclear fuel; also, commercial and US government-owned radioactive wastes through December 31, 1993. These data are based on the most reliable information available from government sources, the open literature, technical reports, and direct contacts. The information forecasted is consistent with the latest US Department of Energy/Energy Information Administration projections of US commercial nuclear power growth and the expected DOE-related and private industrial and institutional activities. The radioactive materials considered, on a chapter-by-chapter basis, are spent nuclear fuel, high-level waste, transuranic waste, low-level waste, commercial uranium mill tailings, DOE Environmental Restoration Program wastes, commercial reactor and fuel-cycle facility decommissioning wastes, and mixed (hazardous and radioactive) low-level waste. For most of these categories, current and projected inventories are given the calendar-year 2030, and the radioactivity and thermal power are calculated based on reported or estimated isotopic compositions. In addition, characteristics and current inventories are reported for miscellaneous radioactive materials that may require geologic disposal. 256 refs., 38 figs., 141 tabs

Prospects for vitrification of mixed wastes at ANL-E

International Nuclear Information System (INIS)

Mazer, J.; No, Hyo.

1993-01-01

This report summarizes a study evaluating the prospects for vitrification of some of the mixed wastes at ANL-E. This project can be justified on the following basis: Some of ANL-E's mixed waste streams will be stabilized such that they can be treated as a low-level radioactive waste. The expected volume reduction that results during vitrification will significantly reduce the overall waste volume requiring disposal. Mixed-waste disposal options currently used by ANL-E may not be permissible in the near future without treatment technologies such as vitrification

The Texas approach to the management of low-level radioactive waste after 1992

International Nuclear Information System (INIS)

Jacobi, L.R.

1992-01-01

By 1993, Texas licensees will be producing 52000 ft 3 of low level radioactive waste (LLRW) containing 11000 Ci of Radioactivity. The three operating pressurized water reactors will produce 63% of the waste volume and greater than 90% of the radioactivity. While the majority of the waste is solid LLRW, some of it, such as liquid scintillation vials and bulk liquids from hospitals, universities, and research facilities, is mixed waste. Most of this waste can be shipped out of state and incinerated, but 60 ft 3 of lead contaminated waste from nuclear power plants and other industrial plants requires land disposal

Adaptation of the TCLP and SW-846 methods to radioactive mixed waste

International Nuclear Information System (INIS)

Griest, W.H.; Schenley, R.L.; Caton, J.E.; Wolfe, P.F.

1994-01-01

Modifications of conventional sample preparation and analytical methods are necessary to provide radiation protection and to meet sensitivity requirements for regulated constituents when working with radioactive samples. Adaptations of regulatory methods for determining ''total'' Toxicity Characteristic Leaching Procedure (TCLP) volatile and semivolatile organics and pesticides, and for conducting aqueous leaching are presented

Identification of permit and waste acceptance criteria provisions requiring modification for acceptance of commercial mixed waste

International Nuclear Information System (INIS)

1994-03-01

In October 1990, representatives of States and compact regions requested that the US Department of Energy (DOE) explore an agreement with host States and compact regions under which DOE would accept commercial mixed low-level radioactive waste (LLW) at DOE's own treatment and disposal facilities. A program for DOE management of commercial mixed waste is made potentially more attractive in light of the low commercial mixed waste volumes, high regulatory burdens, public opposition to new disposal sites, and relatively high cost of constructing commercial disposal facilities. Several studies were identified as essential in determining the feasibility of DOE accepting commercial mixed waste for disposal. The purpose of this report is to identify any current or proposed waste acceptance criteria (WAC) or Resource Conservation and Recovery Act (RCRA) provisions that would have to be modified for commercial mixed waste acceptance at specified DOE facilities. Following the introduction, Section 2 of this report (a) provides a background summary of existing and proposed mixed waste disposal facilities at each DOE site, and (b) summarizes the status of any RCRA Part B permit and WAC provisions relating to the disposal of mixed waste, including provisions relating to acceptance of offsite waste. Section 3 provides overall conclusions regarding the current status and permit modifications that must be implemented in order to grant DOE sites authority under their permits to accept commercial mixed waste for disposal. Section 4 contains a list of references

Radioactive wastes in nuclear fuel cycle

International Nuclear Information System (INIS)

Sakata, Sadahiro; Nagaike, Tadakatsu; Emura, Satoru; Matsumoto, Akira; Morisawa, Shinsuke.

1978-01-01

Recent topics concerning radioactive water management and disposal are widely reviewed. As the introduction, various sources of radioactivity including uranium mining, fuel fabrication, reactor operation and fuel reprocessing and their amount of wastes accumulated per 1000 MWe year operation of a LWR are presented together with the typical methods of disposal. The second section discusses the problems associated with uranium fuel fabrication and with nuclear power plants. Typical radioactive nuclides and their sources in PWRs and BWRs are discussed. The third section deals with the problems associated with reprocessing facilities and with mixed oxide fuel fabrication. Solidification of high-level wastes and the methods of the disposal of transuranic nuclides are the main topics in this section. The fourth section discusses the methods and the problems of final disposal. Various methods being proposed or studied for the final disposal of low- and high-level wastes and transuranic wastes are reviewed. The fifth section concerns with the risk analysis of waste disposal. Both deterministic and probabilistic methods are treated. As the example, the assessment of the risk due to floods is explained. The associated event tree and fault three are presented together with the estimated probability of the occurrence of each constituent failure. In the final section, the environmental problems of radioactive wastes are widely reviewed. (Aoki, K.)

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-04-01

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.

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

International Nuclear Information System (INIS)

1996-04-01

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 ampersand 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

Hanford land disposal restrictions plan for mixed wastes

International Nuclear Information System (INIS)

1990-10-01

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

Hanford land disposal restrictions plan for mixed wastes

Energy Technology Data Exchange (ETDEWEB)

1990-10-01

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

Radioactive action code

International Nuclear Information System (INIS)

Anon.

1988-01-01

A new coding system, 'Hazrad', for buildings and transportation containers for alerting emergency services personnel to the presence of radioactive materials has been developed in the United Kingdom. The hazards of materials in the buildings or transport container, together with the recommended emergency action, are represented by a number of codes which are marked on the building or container and interpreted from a chart carried as a pocket-size guide. Buildings would be marked with the familiar yellow 'radioactive' trefoil, the written information 'Radioactive materials' and a list of isotopes. Under this the 'Hazrad' code would be written - three symbols to denote the relative radioactive risk (low, medium or high), the biological risk (also low, medium or high) and the third showing the type of radiation emitted, alpha, beta or gamma. The response cards indicate appropriate measures to take, eg for a high biological risk, Bio3, the wearing of a gas-tight protection suit is advised. The code and its uses are explained. (U.K.)

Extended storage for radioactive wastes: relevant aspects related to the safety

International Nuclear Information System (INIS)

Castillo, Reinaldo G.; Peralta V, José L.P.; Estevez, Gema G. F.

2013-01-01

The safe management of radioactive waste is an issue of great relevance globally linked to the issue of the peaceful use of nuclear energy. Among the steps in the management of this waste, the safe storage is one of the most important. Given the high costs and uncertainties existing among other aspects of the variants of disposal of radioactive waste, the prolonged storage of these wastes for periods exceeding 50 years is an option that different countries more and more value. One of the fundamental problems to take into account is the safety of the stores, so in this work are evaluated different safety components associated with these facilities through a safety analysis methodology. Elements such as human intrusion, the construction site, the design of the facility, among others are identified as some of the key aspects to take into account when evaluating the safety of these types of facilities. Periods of activities planned for a long-term storage of radioactive waste exceed, in general, the useful life of existing storage facilities. This work identified new challenges to overcome in order to meet the requirements for the achievement of a safe management of radioactive waste without negative impacts on the environment and man

Database basic design for safe management radioactive waste

International Nuclear Information System (INIS)

Son, D. C.; Ahn, K. I.; Jung, D. J.; Cho, Y. B.

2003-01-01

As the amount of radioactive waste and related information to be managed are increasing, some organizations are trying or planning to computerize the management on radioactive waste. When we consider that information on safe management of radioactive waste should be used in association with national radioactive waste management project, standardization of data form and its protocol is required, Korea Institute of Nuclear Safety(KINS) will establish and operate nationwide integrated database in order to effectively manage a large amount of information on national radioactive waste. This database allows not only to trace and manage the trend of radioactive waste occurrence and in storage but also to produce reliable analysis results for the quantity accumulated. Consequently, we can provide necessary information for national radioactive waste management policy and related industry's planing. This study explains the database design which is the essential element for information management

Elastic and strength properties of Hanford concrete mixes at room and elevated temperatures

International Nuclear Information System (INIS)

Abrams, M.S.; Gillen, M.; Campbell, D.H.

1979-03-01

The effects of long-term exposure to elevated temperatures on the physical properties of concrete mixes used in Hanford radioactive waste storage tanks were determined. Temperature had a significant effect on the elastic modulus of concretes. Poisson's ratio determined by the sonic method remained relatively constant. The splitting tensile strength increased rapidly up to 190 days of age. Then strength decreased to about 350 days and either leveled off or increased from that point on. Compressive strength data were erratic

Issues Raised in Relation to Radioactive Waste Management

International Nuclear Information System (INIS)

Atherton, Elizabeth

2003-01-01

Nirex has undertaken various consultations with different stakeholders to identify their issues and concerns about radioactive waste management in general and specific aspects of Nirex's work. This paper will outline what dialogue techniques Nirex has undertaken and the issues and concerns that people have raised during the events. It will outline some of the work that Nirex is undertaking to address stakeholders' issues and concerns. Nirex has used a variety of dialogue techniques co-ordinated under the Nirex Involvement Programme to engage with stakeholders about the work we undertake. We are now trying to address the issues, concerns, scenarios and questions raised in our work programme. Key lessons that we have learned in undertaking the dialogues include: The importance of appropriate facilitation and organisation of meetings; The need for a clear purpose for meetings; Being flexible to the needs of the attendees and the issues they raise; Providing feedback to those who participate and following up issues. Through engaging with the public Nirex has learned that: Radioactive waste is not an everyday concern for people; The public can, will and want to engage with the issue of radioactive waste management. This includes engaging with the ethical debate. To facilitate this Nirex and others need to: Provide information in a neutral form outlining the pros and cons and including various people's opinions; Use proactive techniques to allow access and space for people to discuss the issues; Demonstrate how people's opinions have been taken into account. People understand the issues very differently to the way institutions understand them. There is a need for institutions to learn to understand public concerns and the ways in which the public understand issues, as well as for the public to understand the institutional positions better. We are using these insights to develop our future work in this area

Mixed incineration of RAIW and liquid scintillator waste after storage for decay

International Nuclear Information System (INIS)

Naba, K.; Nakazato, K.; Kataoka, K.

1993-01-01

Most medical radioactive waste is combustible after radioactive decay. Moreover mixed incineration of LLW with biomedical radioactive waste will lessen radiation exposure to the public. This paper describes the total system flowsheet for the processing of liquid scintillator wastes and radioimmunoassay tube wastes containing iodine 125 (after a two-year storage for decay). The process was tested with a 60 kg/hr capacity incinerator from 1987 to 1991; this has been upgraded to a 150 kg/hr incinerator which is used for nonradioactive biomedical waste incineration as well

Method of treatment of radioactive silts and soils

International Nuclear Information System (INIS)

Varlakov, A.P.; Sobolev, I.A.; Barinov, A.S.; Dmitriev, S.A.; Karlin, S.V.; Flit, V.U.

1997-01-01

To solve the problem of silts and soils that are contaminated with radioactive and toxic substances, the following method has been developed at SIA RADON. The material is mixed with limestone and other components, including up to 70% (mass) of dried residue of liquid radioactive waste. The mixture is heated at 800 to 1,000 C, shredded, and used to form cement. This cementation process may be used to treat radioactive or other chemical waste. The work demonstrated that in the case of silts, for example, the product volume is reduced by a factor of 1.5 to 3 compared to the initial silts volume. A fast hardening, durable product is obtained, the quality of which is not inferior to that obtained by using the traditional binders. For some parameters, e.g., hardening rate and macroelement leaching, the current method is significantly better than the traditional cementation process. It has also been demonstrated that, over a wide range of parameters, when dry residue of liquid radioactive waste is used in the initial mixture, the part of NO x can be reduced to nitrogen, thereby reducing NO x emissions

Non-radioactive stand-in for radioactive contamination. I. Non-radioactive tests

International Nuclear Information System (INIS)

Rohe, M.J.; Rankin, W.N.; Postles, R.L.

1985-01-01

Candidate non-radioactive materials for use as a stand-in for radioactive contamination during application of a high-pressure, hot water decontamination were identified and evaluated. A stand-in for radioactive contamination is needed to evaluate the decontaminability of replacement canyon cranes at the manufacturers location where actual radioactive contamination cannot be used. This evaluation was conducted using high-pressure, hot-water at 420 psi, 190 0 F, and 20 gal/min through a 1/8-in.-diam nozzle, the decontamination technique preferred by SRP Separations Department for this application. A non-radioactive stand-in for radioactive contamination was desired that would be removed by direct blast stream contact but would remain intact on surfaces where direct contact does not occur. This memorandum describes identification of candidate non-radioactive stand-in materials and evaluation of these materials in screening tests and tests with high-pressure, hot-water blasting. The following non-radioactive materials were tested: carpenter's line chalk; typing correction fluid; dye penetrant developer; latex paint with attapulyite added; unaltered latex paint; gold enamel; layout fluid; and black enamel. Results show that blue layout fluid and gold enamel have similar adherence that is within the range expected for actual radioactive contamination. White latex paint has less adherence than expected for actual radioactive contamination. The film was removed at a rate of 2 . Black enamel has more adherence than expected from actual radioactive contamination. In these tests ASTM No. 2B surfaces were harder to clean than either ASTM No. 1 or electropolished surfaces which had similar cleaning properties. A 90 0 blast angle was more effective than a 45 0 blast angle. In these tests there was no discernible effect of blast distance between 1 and 3 ft

Influence of natural sorbents in immobilization of radioactive waste in cement

International Nuclear Information System (INIS)

Plecas, I.; Dimovic, S.

2006-01-01

Leach characteristics of 137 Cs and 60 Co radionuclides from spent mix bead ion exchange resins and both ordinary Portland cement and cement mixed with two kind of natural sorbents, (bentonite and clinoptilolite) have been studied using International Atomic Energy's (IAEA) standard leach method. A study is undertaken to determine the waste immobilization performance of low-level wastes in cement-natural sorbents mixtures. The solidification matrix was a standard Portland cement mixed with 290-350 (kg/m 3 ) spent mix bead exchange resins, with or without 1-10 % of bentonite or/and clinoptilolite The leaching rates from the cement-bentonite matrix as 60 Co: (1.20-9.72)x10 -5 (cm/d) and for 137 Cs: (1.00-9.22)x10 -4 (cm/d), after 300 days were measured. From the leaching data the apparent diffusivity of cobalt and cesium in cement bentonite or/and clinoptilolite matrix with a waste load of 350 (kg/m 3 ) spent mix bead exchange resins was measured as 60 Co: (1.0-5.9)x10 -6 (cm 2 /d) and for 137 Cs: (0.48-2.4)x10 -4 (cm 2 /d) after 300 days. The compressive strength of these samples is determined following the ASTM standards. These results are part of a 30-year mortar and concrete testing project which will influence the design of radioactive waste management for a future Serbian radioactive waste disposal center. (author)

Radioactive waste processing device

International Nuclear Information System (INIS)

Ikeda, Takashi; Funabashi, Kiyomi; Chino, Koichi.

1992-01-01

In a waste processing device for solidifying, pellets formed by condensing radioactive liquid wastes generated from a nuclear power plant, by using a solidification agent, sodium chloride, sodium hydroxide or sodium nitrate is mixed upon solidification. In particular, since sodium sulfate in a resin regenerating liquid wastes absorbs water in the cement upon cement solidification, and increases the volume by expansion, there is a worry of breaking the cement solidification products. This reaction can be prevented by the addition of sodium chloride and the like. Accordingly, integrity of the solidification products can be maintained for a long period of time. (T.M.)

Feasibility of using biological degradation for the on-site treatment of mixed wastes

International Nuclear Information System (INIS)

Stringfellow, William T.; Komada, Tatsuyuki; Chang, Li-Yang

2004-01-01

This research was conducted to investigate the feasibility of applying microbial biodegradation as a treatment technology for wastes containing radioactive elements and organic solvents (mixed wastes). In this study, we focused our efforts on the treatment of wastes generated by biomedical research as the result of purifying tritium labeled compounds by high-performance liquid chromatography (HPLC). These wastes are typically 80 percent water with 20 percent acetonitrile or methanol or a mixture of both. The objective was to determine the potential of using biodegradation to treat the solvent component of tritiated mixed waste to a concentration below the land disposal restriction standard (1mg/L for acetonitrile). Once the standard is reached, the remaining radioactive waste is no longer classified as a mixed waste and it can then be solidified and placed in a secure landfill. This investigation focused on treating a 10 percent acetonitrile solution, which was used as a non-radioactive surrogate for HPLC waste, in a bioreactor. The results indicated that the biodegradation process could treat this solution down to less than 1 mg/L to meet the land disposal restriction standard

Technically enhanced naturally occurring radioactive materials; identification, characterization and treatment

International Nuclear Information System (INIS)

Aly, H.F.

2001-01-01

Radioactive materials (TENORM) is produced in a relatively large amount with relatively small radioactivity, however in many instances the radioactivity levels exceeds that permissible. In this presentation, the different industries where enhanced levels of natural radioactivity is identified and characterized will be given. The different approaches for treatment of this enhanced radioactivity will be addressed. Finally, our research and development activities in characterization and treatment of TENORM produced from the oil fields in Egypt will be presented. (authors)

radioactive waste disposal standards abroad

International Nuclear Information System (INIS)

Lu Yan; Xin Pingping; Wu Jian; Zhang Xue

2012-01-01

With the world focus on human health and environmental protection, the problem of radioactive waste disposal has gradually become a global issue, and the focus of attention of public. The safety of radioactive waste disposal, is not only related to human health and environmental safety, but also an important factor of affecting the sustainable development of nuclear energy. In recent years the formulation of the radioactive waste disposal standards has been generally paid attention to at home and abroad, and it has made great progress. In China, radioactive waste management standards are being improved, and there are many new standards need to be developed. The revised task of implement standards is very arduous, and there are many areas for improvement about methods and procedures of the preparation of standards. This paper studies the current situation of radioactive waste disposal standards of the International Atomic Energy Agency, USA, France, Britain, Russia, Japan, and give some corresponding recommendations of our radioactive waste disposal standards. (authors)

Permitting mixed waste treatment, storage and disposal facilities: A mixed bag

International Nuclear Information System (INIS)

Ranek, N.L.; Coalgate, J.L.

1995-01-01

The Federal Facility Compliance Act of 1992 (FFCAct) requires the U.S. Department of Energy (DOE) to make a comprehensive national inventory of its mixed wastes (i.e., wastes that contain both a hazardous component that meets the Resource Conservation and Recovery Act (RCRA) definition of hazardous waste and a radioactive component consisting of source, special nuclear, or byproduct material regulated under the Atomic Energy Act (AEA)), and of its mixed waste treatment technologies and facilities. It also requires each DOE facility that stores or generates mixed waste to develop a treatment plan that includes, in part, a schedule for constructing units to treat those wastes that can be treated using existing technologies. Inherent in constructing treatment units for mixed wastes is, of course, permitting. This paper identifies Federal regulatory program requirements that are likely to apply to new DOE mixed waste treatment units. The paper concentrates on showing how RCRA permitting requirements interrelate with the permitting or licensing requirements of such other laws as the Atomic Energy Act, the Clean Water Act, and the Clean Air Act. Documentation needed to support permit applications under these laws are compared with RCRA permit application documentation. National Environmental Policy Act (NEPA) documentation requirements are also addressed, and throughout the paper, suggestions are made for managing the permitting process

What to do with radioactive wastes?

International Nuclear Information System (INIS)

2006-01-01

This power point presentation (82 slides) gives information on what is a radioactive waste, radioactivity and historical review of radioactivity, radioactive period, natural radioactivity (with examples of data), the three main radiation types (α, β, γ), the origin of radioactive wastes (nuclear power, research, defense, other), the proportion of radioactive wastes in the total of industrial wastes in France, the classification of nuclear wastes according to their activity and period, the quantities and their storage means, the 1991 december 30 law (France) related to the radioactive waste management, the situation in other countries (Germany, Belgium, Canada, USA, Finland, Japan, Netherlands, Sweden, Switzerland), volume figures and previsions for the various waste types in 2004, 2010 and 2020, the storage perspectives, the French national debate on radioactive waste management and the objective of perpetuated solutions, the enhancement of the public information, the 15 June 2006 law on a sustainable management of radioactive materials and wastes with three main axis (deep separation and transmutation, deep storage, waste conditioning and long term surface storage), and the development of a nuclear safety and waste culture that could be extended to other types of industry

Radioactive waste management

International Nuclear Information System (INIS)

1992-01-01

This book highlights the main issues of public concern related to radioactive waste management and puts them into perspective. It provides an overview of radioactive waste management covering, among other themes, policies, implementation and public communication based on national experiences. Its purpose is to assists in increasing the understanding of radioactive waste management issues by public and national authorities, organizations involved in radioactive waste management and the nuclear industry; it may also serve as a source book for those who communicate with the public. Even in the unlikely event that nuclear power does not further develop around the world, the necessity for dealing with nuclear waste from past usages, from uranium mining and milling, decontamination and decommissioning of existing nuclear facilities and from the uses of radioactive materials in medicine, industry and research would still exist. In many countries, radioactive waste management planning involves making effective institutional arrangements in which responsibilities and liabilities are well established for the technical operation and long term surveillance of disposal systems. Financing mechanisms are part of the arrangements. Continuous quality assurance and quality control, at all levels of radioactive waste management, are essential to ensure the required integrity of the system. As with any other human activity, improvements in technology and economics may be possible and secondary problems avoided. Improvements and confirmation of the efficiency of processes and reduction of uncertainties can only be achieved by continued active research, development and demonstration, which are the goals of many national programmes. International co-operation, also in the form of reviews, can contribute to increasing confidence in the ongoing work. The problem of radioactive wastes is not a unique one; it may be compared with other problems of toxic wastes resulting from many other

Mediated electrochemical oxidation treatment for Rocky Flats combustible low-level mixed waste. Final report, FY 1993 and 1994

International Nuclear Information System (INIS)

Chiba, Z.; Lewis, P.R.; Murguia, L.C.

1994-09-01

Mediated Electrochemical Oxidation (MEO) is an aqueous process which destroys hazardous organics by oxidizing a mediator at the anode of an electrochemical cell; the mediator in turn oxidizes the organics within the bulk of the electrolyte. With this process organics can be nearly completely destroyed, that is, the carbon and hydrogen present in the hydrocarbon are almost entirely mineralized to carbon dioxide and water. The MEO process is also capable of dissolving radioactive materials, including difficult-to-dissolve compounds such as plutonium oxide. Hence, this process can treat mixed wastes, by destroying the hazardous organic components of the waste, and dissolving the radioactive components. The radioactive material can be recovered if desired, or disposed of as non-mixed radioactive waste. The process is inherently safe, since the hazardous and radioactive materials are completely contained in the aqueous phase, and the system operates at low temperatures (below 80 degree C) and at ambient pressures

Simulated Radioactivity

Science.gov (United States)

Boettler, James L.

1972-01-01

Describes the errors in the sugar-cube experiment related to radioactivity as described in Project Physics course. The discussion considers some of the steps overlooked in the experiment and generalizes the theory beyond the sugar-cube stage. (PS)

Technical summary of Groundwater Quality Protection Program at Savannah River Plant. Volume II. Radioactive waste

International Nuclear Information System (INIS)

Stone, J.A.; Christensen, E.J.

1983-12-01

This report (Volume II) presents representative monitoring data for radioactivity in groundwater at SRP. Four major groups of radioactive waste disposal sites and three minor sites are described. Much of the geohydrological and and other background information given in Volume I is applicable to these sites and is incorporated by reference. Several of the sites that contain mixed chemical and radioactive wastes are discussed in both Volumes I and II. Bulk unirradiated uranium is considered primarily a chemical waste which is addressed in Volume I, but generally not in Volume II

Experience base for Radioactive Waste Thermal Processing Systems: A preliminary survey

International Nuclear Information System (INIS)

Mayberry, J.; Geimer, R.; Gillins, R.; Steverson, E.M.; Dalton, D.; Anderson, G.L.

1992-04-01

In the process of considering thermal technologies for potential treatment of the Idaho National Engineering Laboratory mixed transuranic contaminated wastes, a preliminary survey of the experience base available from Radioactive Waste Thermal Processing Systems is reported. A list of known commercial radioactive waste facilities in the United States and some international thermal treatment facilities are provided. Survey focus is upon the US Department of Energy thermal treatment facilities. A brief facility description and a preliminary summary of facility status, and problems experienced is provided for a selected subset of the DOE facilities

Mixed Waste Working Group report

International Nuclear Information System (INIS)

1993-01-01

The treatment of mixed waste remains one of this country's most vexing environmental problems. Mixed waste is the combination of radioactive waste and hazardous waste, as defined by the Resource Conservation and Recovery Act (RCRA). The Department of Energy (DOE), as the country's largest mixed waste generator, responsible for 95 percent of the Nation's mixed waste volume, is now required to address a strict set of milestones under the Federal Facility Compliance Act of 1992. DOE's earlier failure to adequately address the storage and treatment issues associated with mixed waste has led to a significant backlog of temporarily stored waste, significant quantities of buried waste, limited permanent disposal options, and inadequate treatment solutions. Between May and November of 1993, the Mixed Waste Working Group brought together stakeholders from around the Nation. Scientists, citizens, entrepreneurs, and bureaucrats convened in a series of forums to chart a course for accelerated testing of innovative mixed waste technologies. For the first time, a wide range of stakeholders were asked to examine new technologies that, if given the chance to be tested and evaluated, offer the prospect for better, safer, cheaper, and faster solutions to the mixed waste problem. In a matter of months, the Working Group has managed to bridge a gap between science and perception, engineer and citizen, and has developed a shared program for testing new technologies

Radioactive substances in the Danish building materials

International Nuclear Information System (INIS)

Ulbak, K.

1986-01-01

Building materials as any other materials of natural occurrence contain small concentrations of natural radioactive elements. This natural radioactivity affects people inside buildings. This publiccation refers measurements of the Danish building materials, and radiation doses originating from this source affecting the Danish population are related to the other components of background radioactivity. (EG)

SAVANNAH RIVER SITE INCIPIENT SLUDGE MIXING IN RADIOACTIVE LIQUID WASTE STORAGE TANKS DURING SALT SOLUTION BLENDING

Energy Technology Data Exchange (ETDEWEB)

Leishear, R.; Poirier, M.; Lee, S.; Steeper, T.; Fowley, M.; Parkinson, K.

2011-01-12

This paper is the second in a series of four publications to document ongoing pilot scale testing and computational fluid dynamics (CFD) modeling of mixing processes in 85 foot diameter, 1.3 million gallon, radioactive liquid waste, storage tanks at Savannah River Site (SRS). Homogeneous blending of salt solutions is required in waste tanks. Settled solids (i.e., sludge) are required to remain undisturbed on the bottom of waste tanks during blending. Suspension of sludge during blending may potentially release radiolytically generated hydrogen trapped in the sludge, which is a safety concern. The first paper (Leishear, et. al. [1]) presented pilot scale blending experiments of miscible fluids to provide initial design requirements for a full scale blending pump. Scaling techniques for an 8 foot diameter pilot scale tank were also justified in that work. This second paper describes the overall reasons to perform tests, and documents pilot scale experiments performed to investigate disturbance of sludge, using non-radioactive sludge simulants. A third paper will document pilot scale CFD modeling for comparison to experimental pilot scale test results for both blending tests and sludge disturbance tests. That paper will also describe full scale CFD results. The final paper will document additional blending test results for stratified layers in salt solutions, scale up techniques, final full scale pump design recommendations, and operational recommendations. Specifically, this paper documents a series of pilot scale tests, where sludge simulant disturbance due to a blending pump or transfer pump are investigated. A principle design requirement for a blending pump is UoD, where Uo is the pump discharge nozzle velocity, and D is the nozzle diameter. Pilot scale test results showed that sludge was undisturbed below UoD = 0.47 ft{sup 2}/s, and that below UoD = 0.58 ft{sup 2}/s minimal sludge disturbance was observed. If sludge is minimally disturbed, hydrogen will not be

Decoding Environmental Processes Using Radioactive Isotopes for the Post-Radioactive Contamination Recovery Assessment

Science.gov (United States)

Yasumiishi, Misa; Nishimura, Taku; Osawa, Kazutoshi; Renschler, Chris

2017-04-01

slopes where the surface soil was scraped and litter was cleared, the scraping showed mixed results in radioactivity reduction. It is estimated that by the completion of soil decontamination in 2020, up to 22 million cubic meters of so-called 'contaminated soils' will have been scraped off in the affected areas and transferred to an underground storage. Understanding the radioactive isotope behaviors is crucial to assessing the financial and environmental consequences of such measures. As an example, a 30-year simulation of a 5-13 % hillslope under thick vegetation with GeoWEPP (the Geospatial interface for the Water Erosion Prediction Project) resulted in a very small soil loss on the hillslope. However, the results showed about five tons of soil loss through channels and as sediment discharge annually. On the hillslope, the radioactivity level in about the top 4.0 cm of the soil exceeded the 8,000 Bq/kg threshold which the Japanese government has set for surface soil removal. Referring to the case study data in Fukushima, this presentation will discuss how environmental decontamination measures (e.g. forest clearing) and monitoring methods should be considered and planned against dynamic environmental processes.

Mixed waste management at the Hanford Site

International Nuclear Information System (INIS)

Roberts, R.J.; Jasen, W.G.

1991-01-01

Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act (AEA) and the Resource Conservation and Recovery Act (RCRA) have led to the definition of a group of wastes called radioactive mixed wastes (RMW). As a result of the radioactive and hazardous properties of these wastes, special projects have been initiated for the management of RMW. This paper addresses the management of solid RMW. The management of bulk liquid RMW will not be described. 7 refs., 4 figs

Safety aspects related to the radioactively contaminated forest areas in Belarus

International Nuclear Information System (INIS)

SULLIVAN, T.; GIBBS, B.; ANDERSSON, K.G.; ROED, J.; RYMKEVICH, V.; BREKKE, D.

1998-01-01

Doses currently received in Belarus through various pathways related to the contamination of forests are evaluated through calculations. A major pathway is, as expected, generally found to be the external radiation from a contaminated forest floor. Also other pathways may in some cases be highly significant. Generally, it is found that the dose contributions to people spending time in the contaminated forest or consuming forest products are highest, whereas for instance doses received from domestic use of fire-wood are found to be negligible. Recommendations for storage of waste from combustion plants fired with radioactive forest material are also given, together with an estimate of the specific activity of the waste to be disposed of

Polyethylene macroencapsulation - mixed waste focus area. OST reference No. 30

International Nuclear Information System (INIS)

1998-02-01

The lead waste inventory throughout the US Department of Energy (DOE) complex has been estimated between 17 million and 24 million kilograms. Decontamination of at least a portion of the lead is viable but at a substantial cost. Because of various problems with decontamination and its limited applicability and the lack of a treatment and disposal method, the current practice is indefinite storage, which is costly and often unacceptable to regulators. Macroencapsulation is an approved immobilization technology used to treat radioactively contaminated lead solids and mixed waste debris. (Mixed waste is waste materials containing both radioactive and hazardous components). DOE has funded development of a polyethylene extrusion macroencapsulation process at Brookhaven National Laboratory (BNL) that produces a durable, leach-resistant waste form. This innovative macroencapsulation technology uses commercially available single-crew extruders to melt, convey, and extrude molten polyethylene into a waste container in which mixed waste lead and debris are suspended or supported. After cooling to room temperature, the polyethylene forms a low-permeability barrier between the waste and the leaching media

Radioactive facilities classification criteria

International Nuclear Information System (INIS)

Briso C, H.A.; Riesle W, J.

1992-01-01

Appropriate classification of radioactive facilities into groups of comparable risk constitutes one of the problems faced by most Regulatory Bodies. Regarding the radiological risk, the main facts to be considered are the radioactive inventory and the processes to which these radionuclides are subjected. Normally, operations are ruled by strict safety procedures. Thus, the total activity of the radionuclides existing in a given facility is the varying feature that defines its risk. In order to rely on a quantitative criterion and, considering that the Annual Limits of Intake are widely accepted references, an index based on these limits, to support decisions related to radioactive facilities, is proposed. (author)

Mixed finite element simulations in two-dimensional groundwater flow problems

International Nuclear Information System (INIS)

Kimura, Hideo

1989-01-01

A computer code of groundwater flow in two-dimensional porous media based on the mixed finite element method was developed for accurate approximations of Darcy velocities in safety evaluation of radioactive waste disposal. The mixed finite element procedure solves for both the Darcy velocities and pressure heads simultaneously in the Darcy equation and continuity equation. Numerical results of a single well pumping at a constant rate in a uniform flow field showed that the mixed finite element method gives more accurate Darcy velocities nearly 50 % on average error than standard finite element method. (author)

Mixed waste study, Lawrence Livermore National Laboratory Hazardous Waste Management facilities

International Nuclear Information System (INIS)

1990-11-01

This document addresses the generation and storage of mixed waste at Lawrence Livermore National Laboratory (LLNL) from 1984 to 1990. Additionally, an estimate of remaining storage capacity based on the current inventory of low-level mixed waste and an approximation of current generation rates is provided. Section 2 of this study presents a narrative description of Environmental Protection Agency (EPA) and Department of Energy (DOE) requirements as they apply to mixed waste in storage at LLNL's Hazardous Waste Management (HWM) facilities. Based on information collected from the HWM non-TRU radioactive waste database, Section 3 presents a data consolidation -- by year of storage, location, LLNL generator, EPA code, and DHS code -- of the quantities of low-level mixed waste in storage. Related figures provide the distribution of mixed waste according to each of these variables. A historical review follows in Section 4. The trends in type and quantity of mixed waste managed by HWM during the past five years are delineated and graphically illustrated. Section 5 provides an estimate of remaining low-level mixed waste storage capacity at HWM. The estimate of remaining mixed waste storage capacity is based on operational storage capacity of HWM facilities and the volume of all waste currently in storage. An estimate of the time remaining to reach maximum storage capacity is based on waste generation rates inferred from the HWM database and recent HWM documents. 14 refs., 18 figs., 9 tabs

Transport regulation for radioactive materials

International Nuclear Information System (INIS)

Ha Vinh Phuong.

1986-01-01

Taking into account the specific dangers associated with the transport of radioactive materials (contamination, irradiation, heat, criticality), IAEA regulations concerning technical specifications and administrative procedures to ward off these dangers are presented. The international agreements related to the land transport, maritime transport and air transport of radioactive materials are also briefly reviewed

An interpretation of schedule 1 of the Radioactive Substances Act 1993 and related issues

International Nuclear Information System (INIS)

Hill, M.; Wakerley, M.W.

2000-09-01

Schedule 1 of the UK's Radioactive Substances Act 1993 was originally Schedule 3 of the 1960 Act of the same name. It is possible that different methods are currently being employed to interpret how Schedule 1 should be used. This report provides an interpretation and guidance on this and related issues. It is primarily for technical specialists already familiar with the workings of the Act. This report covers the period 1999/2000

Final waste management programmatic environmental impact statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume IV of V

International Nuclear Information System (INIS)

1997-01-01

The Final Waste Management Programmatic Environmental Impact Statement (WM PEIS) examines the potential environmental and cost impacts of strategic management alternatives for managing five types of radioactive and hazardous wastes that have resulted and will continue to result from nuclear defense and research activities at a variety of sites around the United States. The five waste types are low-level mixed waste, low-level waste, transuranic waste, high-level waste, and hazardous waste. The WM PEIS provides information on the impacts of various siting alternatives which the Department of Energy (DOE) will use to decide at which sites to locate additional treatment, storage, and disposal capacity for each waste type.Transportation is an integral component of the alternatives being considered for each type of radioactive waste in the U.S. Department of Energy (DOE) Waste Management Programmatic Environmental Impact Statement (WM PEIS). The types of radioactive waste considered in Part I are high-level waste (HLW), low-level waste (LLW), transuranic waste (TRUW), and low-level mixed waste (LLMW). For some alternatives, radioactive waste would be shipped among the DOE sites at various stages of the treatment, storage, and disposal (TSD) process. The magnitude of the transportation-related activities varies with each alternative, ranging from minimal transportation for decentralized approaches to significant transportation for some centralized approaches. The human health risks associated with transporting various waste materials were assessed to ensure a complete appraisal of the impacts of each PEIS alternative being considered

Peran the Public Relation Mix Dalam Membangun Komunikasi Yang Efektif

OpenAIRE

Nurhayati, Afita

2012-01-01

In communication tools, the public relation mix takesimportant role in order to develop an effective communication. The role is done by developing credibility so it will increase the visibility of company or organization, and finally the positive image of the product still keep on, both goods and services in the public sight.

Issues related to the licensing of final disposal facilities for radioactive waste

International Nuclear Information System (INIS)

Medici, M.A.; Alvarez, D.E.; Lee Gonzales, H.; Piumetti, E.H.; Palacios, E.

2010-01-01

The licensing process of a final disposal facility for radioactive waste involves the design, construction, pre-operation, operation, closure and post closure stages. While design and pre-operational stages are, to a reasonable extent, similar to other kind of nuclear or radioactive facilities, construction, operation, closure and post-closure of a radioactive waste disposal facility have unique meanings. As consequence of that, the licensing process should incorporate these particularities. Considering the long timeframes involved at each stage of a waste disposal facility, it is convenient that the development of the project being implemented in and step by step process, be flexible enough as to adapt to new requirements that would arise as a consequence of technology improvements or due to variations in the socio-economical and political conditions. In Argentina, the regulatory Standard AR 0.1.1 establishes the general guideline for the 'Licensing of Class I facilities (relevant facilities)'. Nevertheless, for radioactive waste final disposal facilities a new specific guidance should be developed in addition to the Basic Standard mentioned. This paper describes the particularities of final disposal facilities indicating that a specific licensing system for this type of facilities should be foreseen. (authors) [es

A literature review of methods of analysis of organic analytes in radioactive wastes with an emphasis on sources from the United Kingdom

International Nuclear Information System (INIS)

Clauss, S.A.; Bean, R.M.

1993-09-01

This report, compiled by Pacific Northwest Laboratory (PNL), examines literature originating through the United Kingdom (UK) nuclear industry relating to the analyses of organic constituents of radioactive waste. Additionally, secondary references from the UK and other counties, including the United States, have been reviewed. The purpose of this literature review was to find analytical methods that would apply to the mixed-waste matrices found at Hanford

Computer modeling of jet mixing in INEL waste tanks

International Nuclear Information System (INIS)

Meyer, P.A.

1994-01-01

The objective of this study is to examine the feasibility of using submerged jet mixing pumps to mobilize and suspend settled sludge materials in INEL High Level Radioactive Waste Tanks. Scenarios include removing the heel (a shallow liquid and sludge layer remaining after tank emptying processes) and mobilizing and suspending solids in full or partially full tanks. The approach used was to (1) briefly review jet mixing theory, (2) review erosion literature in order to identify and estimate important sludge characterization parameters (3) perform computer modeling of submerged liquid mixing jets in INEL tank geometries, (4) develop analytical models from which pump operating conditions and mixing times can be estimated, and (5) analyze model results to determine overall feasibility of using jet mixing pumps and make design recommendations

Proceedings of the NEA Workshop on the Management of Non-Nuclear Radioactive Waste

International Nuclear Information System (INIS)

Zafiropoulos, Demetre; Dilday, Daniel; Siemann, Michael; Ciambrella, Massimo; Lazo, Edward; Sartori, Enrico; ); Dionisi, Mario; Long, Juliet; Nicholson, David; Chambers, Douglas; Garcia Alves, Joao Henrique; McMahon, Ciara; Bruno, Gerard; Fan, Zhiwen; ); Ripani, Marco; Nielsen, Mette; Solente, Nicolas; Templeton, John; Paratore, Angelo; Feinhals, Joerg; Pandolfi, Dana; Sarchiapone, Lucia; Picentino, Bruno; Simms, Helen; Beer, Hans-Frieder; Deryabin, Sergey; Ulrici, Luisa; Bergamaschi, Carlo; Nottestad, Stacy; Anagnostakis, Marios

2017-05-01

All NEA member countries, whether or not they have nuclear power plants, are faced with appropriately managing non-nuclear radioactive waste produced through industrial, research and medical activities. Sources of such waste can include national laboratory and university research activities, used and lost industrial gauges and radiography sources, hospital nuclear medicine activities and in some circumstances, naturally occurring radioactive material (NORM) activities. Although many of these wastes are not long-lived, the shear variety of sources makes it difficult to generically assess their physical (e.g. volume, chemical form, mixed waste) or radiological (e.g. activity, half-life, concentration) characteristics. Additionally, the source-specific nature of these wastes poses questions and challenges to their regulatory and practical management at a national level. This had generated interest from both the radiological protection and radioactive waste management communities, and prompted the Committee on Radiological Protection and Public Health (CRPPH) to organise, in collaboration with the Radioactive Waste Management Committee (RWMC), a workshop tackling some of the key issues of this challenging topic. The key objectives of the NEA Workshop on the Management of Non-Nuclear Radioactive Waste were to address the particularities of managing non-nuclear waste in all its sources and forms and to share and exchange national experiences. Presentations and discussions addressed both technical aspects and national frameworks. Technical aspects included: - the range of non-nuclear waste sources, activities, volumes and other relevant characteristics; - waste storage and repository capacities and life cycles; - safety considerations for mixed wastes management; - human resources and knowledge management; - legal, regulatory and financial assurance, and liability issues. Taking into account the entire non-nuclear waste life-cycle, the workshop covered planning and

Radioactive elements in Pennsylvania waters

International Nuclear Information System (INIS)

Rose, A.W.

1990-01-01

The first recognition of radioactive elements in natural waters dates back many years, but interest has accelerated in recent years with the advent of concern about the health effects of radioactivity. At the present time, extensive monitoring of public water supplies for radioactive substances is mandated by federal and state law, and monitoring near nuclear facilities is required by federal regulations, so that a great deal of information is accumulating on the amount and distribution of radioactivity in natural waters. These results reveal that small amounts of radioactive elements are universally present in natural waters, and that the concentration vary over an appreciable range as a result of natural processes and human activities. The purpose of this paper is to summarize the origin, behavior, abundance and hazard of the main radioactive species in Pennsylvania surface and ground waters. This treatment is intended to provide background to the interested reader in comprehending questions such as the hazard of radon in homes with private wells and pollution related to the nuclear power cycle

Improvements in or relating to trapping and reuse of radioactive xenon

International Nuclear Information System (INIS)

Bolmsjoe, M.S.; Persson, B.R.

1981-01-01

A method is described suitable for recovering, from a mixture of gases contaning radioactive xenon, a mixture of gases containing an increased concentration of radioactive xenon, which method comprises the steps of passing xenon-containing gas through a bed of activated charcoal to adsorb the xenon therein, thereafter heating the charcoal bed to a temperature within the range of from 200 to 400 0 C, passing a moisture-free sweep gas through the bed when heated to said temperature to desorb xenon therefrom and then collecting the xenon-containing gas thus formed. (author)

Mixed Waste Integrated Program Quality Assurance requirements plan

International Nuclear Information System (INIS)

1994-01-01

Mixed Waste Integrated Program (MWIP) is sponsored by the US Department of Energy (DOE), Office of Technology Development, Waste Management Division. The strategic objectives of MWIP are defined in the Mixed Waste Integrated Program Strategic Plan, and expanded upon in the MWIP Program Management Plan. This MWIP Quality Assurance Requirement Plan (QARP) applies to mixed waste treatment technologies involving both hazardous and radioactive constituents. As a DOE organization, MWIP is required to develop, implement, and maintain a written Quality Assurance Program in accordance with DOE Order 4700.1 Project Management System, DOE Order 5700.6C, Quality Assurance, DOE Order 5820.2A Radioactive Waste Management, ASME NQA-1 Quality Assurance Program Requirements for Nuclear Facilities and ANSI/ASQC E4-19xx Specifications and Guidelines for Quality Systems for Environmental Data Collection and Environmental Technology Programs. The purpose of the MWIP QA program is to establish controls which address the requirements in 5700.6C, with the intent to minimize risks and potential environmental impacts; and to maximize environmental protection, health, safety, reliability, and performance in all program activities. QA program controls are established to assure that each participating organization conducts its activities in a manner consistent with risks posed by those activities

Mixed Waste Integrated Program Quality Assurance requirements plan

Energy Technology Data Exchange (ETDEWEB)

1994-04-15

Mixed Waste Integrated Program (MWIP) is sponsored by the US Department of Energy (DOE), Office of Technology Development, Waste Management Division. The strategic objectives of MWIP are defined in the Mixed Waste Integrated Program Strategic Plan, and expanded upon in the MWIP Program Management Plan. This MWIP Quality Assurance Requirement Plan (QARP) applies to mixed waste treatment technologies involving both hazardous and radioactive constituents. As a DOE organization, MWIP is required to develop, implement, and maintain a written Quality Assurance Program in accordance with DOE Order 4700.1 Project Management System, DOE Order 5700.6C, Quality Assurance, DOE Order 5820.2A Radioactive Waste Management, ASME NQA-1 Quality Assurance Program Requirements for Nuclear Facilities and ANSI/ASQC E4-19xx Specifications and Guidelines for Quality Systems for Environmental Data Collection and Environmental Technology Programs. The purpose of the MWIP QA program is to establish controls which address the requirements in 5700.6C, with the intent to minimize risks and potential environmental impacts; and to maximize environmental protection, health, safety, reliability, and performance in all program activities. QA program controls are established to assure that each participating organization conducts its activities in a manner consistent with risks posed by those activities.

Method for electrolytic decontamination of radioactive contaminated metals

International Nuclear Information System (INIS)

Tanaka, Akio; Horita, Masami; Onuma, Tsutomu; Kato, Koji

1991-01-01

The invention relates to an electrolytic decontamination method for radioactive contaminated metals. The contaminated sections are eluted by electrolysis after the surface of a piece of equipment used with radioactive substances has been immersed in an electrolyte. Metal contaminated by radioactive substances acts as the anode

Mixed waste treatment capabilities at Envirocare

International Nuclear Information System (INIS)

Rafati, A.

1994-01-01

This presentation gives an overview of the business achievements and presents a corporate summary for the whole handling company Envirocare located in Clive, Utah. This company operates a permitted low-level radioactive and mixed waste facility which handles waste from the United States Department of Energy, Environmental Protection Agency, Department of Defense, and Fortune 500 companies. A description of business services and treatment capabilities is presented

Process for disposal of aqueous solutions containing radioactive isotopes

Science.gov (United States)

Colombo, Peter; Neilson, Jr., Robert M.; Becker, Walter W.

1979-01-01

A process for disposing of radioactive aqueous waste solutions whereby the waste solution is utilized as the water of hydration to hydrate densified powdered portland cement in a leakproof container; said waste solution being dispersed without mechanical inter-mixing in situ in said bulk cement, thereafter the hydrated cement body is impregnated with a mixture of a monomer and polymerization catalyst to form polymer throughout the cement body. The entire process being carried out while maintaining the temperature of the components during the process at a temperature below 99.degree. C. The container containing the solid polymer-impregnated body is thereafter stored at a radioactive waste storage dump such as an underground storage dump.

Process for disposal of aqueous solutions containing radioactive isotopes

International Nuclear Information System (INIS)

Colombo, P.; Neilson, R.M. Jr.; Becker, W.W.

1979-01-01

A process for disposing of radioactive aqueous waste solutions whereby the waste solution is utilized as the water of hydration to hydrate densified powdered portland cement in a leakproof container; said waste solution being dispersed without mechanical inter-mixing in situ in said bulk cement, thereafter the hydrated cement body is impregnated with a mixture of a monomer and polymerization catalyst to form polymer throughout the cement body. The entire process being carried out while maintaining the temperature of the components during the process at a temperature below 99 0 C. The container containing the solid polymer-impregnated body is thereafter stored at a radioactive waste storage dump such as an underground storage dump

The need for mixed waste treatment options within the US Department of Energy

International Nuclear Information System (INIS)

McCulla, W.H.; French, D.M.

1992-01-01

The United States Department of Energy (DOE) has generated and stored significant amounts of low-level mixed wastes consisting of radioactive materials mixed with hazardous chemical substances in various forms. The DOE is in the process of beginning a cleanup of these mixed wastes at many of its facilities. Many of these waste streams had been previously disposed of by methods acceptable at the time but with the passage of very stringent laws affecting migration of hazardous components, now the disposal areas constitute remediation sites. Disposal of low level radioactive waste potentially containing hazardous materials have also fallen under land disposal restrictions and currently no mixed waste is going to low level disposal facilities. The paper will address why the DOE is just now starting to comply with environmental laws, why there is a need to find more effective and less expensive means of cleaning up wastes, how the DOE is organizing to accomplish this cleanup, and several plasma technology development efforts in the DOE Complex that show promise of meeting these needs

The need for mixed waste treatment options within the US Department of Energy

Energy Technology Data Exchange (ETDEWEB)

McCulla, W.H.; French, D.M.

1992-12-31

The United States Department of Energy (DOE) has generated and stored significant amounts of low-level mixed wastes consisting of radioactive materials mixed with hazardous chemical substances in various forms. The DOE is in the process of beginning a cleanup of these mixed wastes at many of its facilities. Many of these waste streams had been previously disposed of by methods acceptable at the time but with the passage of very stringent laws affecting migration of hazardous components, now the disposal areas constitute remediation sites. Disposal of low level radioactive waste potentially containing hazardous materials have also fallen under land disposal restrictions and currently no mixed waste is going to low level disposal facilities. The paper will address why the DOE is just now starting to comply with environmental laws, why there is a need to find more effective and less expensive means of cleaning up wastes, how the DOE is organizing to accomplish this cleanup, and several plasma technology development efforts in the DOE Complex that show promise of meeting these needs.

Low sintering temperature glass waste forms for sequestering radioactive iodine

Science.gov (United States)

Nenoff, Tina M.; Krumhansl, James L.; Garino, Terry J.; Ockwig, Nathan W.

2012-09-11

Materials and methods of making low-sintering-temperature glass waste forms that sequester radioactive iodine in a strong and durable structure. First, the iodine is captured by an adsorbant, which forms an iodine-loaded material, e.g., AgI, AgI-zeolite, AgI-mordenite, Ag-silica aerogel, ZnI.sub.2, CuI, or Bi.sub.5O.sub.7I. Next, particles of the iodine-loaded material are mixed with powdered frits of low-sintering-temperature glasses (comprising various oxides of Si, B, Bi, Pb, and Zn), and then sintered at a relatively low temperature, ranging from 425.degree. C. to 550.degree. C. The sintering converts the mixed powders into a solid block of a glassy waste form, having low iodine leaching rates. The vitrified glassy waste form can contain as much as 60 wt % AgI. A preferred glass, having a sintering temperature of 500.degree. C. (below the silver iodide sublimation temperature of 500.degree. C.) was identified that contains oxides of boron, bismuth, and zinc, while containing essentially no lead or silicon.

Civil nuclear and responsibilities related to radioactive wastes. The 'cumbersome' wastes of the civil nuclear; The Parliament and the management of wastes from the civil nuclear; The Swiss legal framework related to the shutting down of nuclear power stations and to the management of radioactive wastes; Economic theory and management of radioactive wastes: to dare the conflict

International Nuclear Information System (INIS)

Rambour, Muriel; Pauvert, Bertrand; Zuber-Roy, Celine; Thireau, Veronique

2015-01-01

This publication presents the contributions to a research seminar organised by the European Centre of research on Risk, Collective Accident and Disasters Law (CERDACC) on the following theme: civil nuclear and responsibilities related to radioactive wastes. Three main thematic issues have been addressed: the French legal framework for waste processing, the comparison with the Swiss case, and the controversy about the exposure of societies to waste-induced risks. The first contribution addressed the cumbersome wastes of the civil nuclear industry: characterization and management solutions, the hypothesis of reversibility of the storage of radioactive wastes. The second one comments the commitment of the French Parliament in the management of wastes of the civil nuclear industry: role of Parliamentary Office of assessment of scientific and technological choices (OPECST) to guide law elaboration, assessment by the Parliament of the management of nuclear wastes (history and evolution of legal arrangements). The next contribution describes the Swiss legal framework for the shutting down of nuclear power stations (decision and decommissioning) and for the management of radioactive wastes (removal, financing). The last contribution discusses the risk related to nuclear waste management for citizen and comments how economists address this issue

Radioactivity of Consumer Products

Science.gov (United States)

Peterson, David; Jokisch, Derek; Fulmer, Philip

2006-11-01

A variety of consumer products and household items contain varying amounts of radioactivity. Examples of these items include: FiestaWare and similar glazed china, salt substitute, bananas, brazil nuts, lantern mantles, smoke detectors and depression glass. Many of these items contain natural sources of radioactivity such as Uranium, Thorium, Radium and Potassium. A few contain man-made sources like Americium. This presentation will detail the sources and relative radioactivity of these items (including demonstrations). Further, measurements of the isotopic ratios of Uranium-235 and Uranium-238 in several pieces of china will be compared to historical uses of natural and depleted Uranium. Finally, the presenters will discuss radiation safety as it pertains to the use of these items.

Material for radioactive protection

Science.gov (United States)

Taylor, R.S.; Boyer, N.W.

A boron containing burn resistant, low-level radiation protection material useful, for example, as a liner for radioactive waste disposal and storage, a component for neutron absorber, and a shield for a neutron source is described. The material is basically composed of borax in the range of 25 to 50%, coal tar in the range of 25 to 37.5%, with the remainder being an epoxy resin mix. A preferred composition is 50% borax, 25% coal tar and 25% epoxy resin. The material is not susceptible to burning and is about 1/5 the cost of existing radiation protection material utilized in similar applications.

Decontamination and radioactivity measurement on building surfaces related to dismantling of Japan power demonstration reactor (JPDR)

International Nuclear Information System (INIS)

Hatakeyama, Mutsuo; Tachibana, Mitsuo; Yanagihara, Satoshi

1997-12-01

In the final stage of dismantling activities for decommissioning a nuclear power plant, building structures have to be demolished to release the site for unrestricted use. Since building structures are generally made from massive reinforced concrete materials, it is not a rational way to treat all concrete materials arising from its demolition as radioactive waste. Segregation of radioactive parts from building structures is therefore indispensable. The rational procedures were studied for demolition of building structures by treating arising waste as non-radioactive materials, based on the concept established by Nuclear Safety Commission, then these were implemented in the following way by the JPDR dismantling demonstration project. Areas of the JPDR facilities are categorized into two groups : possibly contaminated areas, and possibly non-contaminated areas, based on the document of the reactor operation. Radioactivity on the building surfaces was then measured to confirm that the qualitative categorization is reasonable. After that, building surfaces were decontaminated in such a way that the contaminated layers were removed with enough margin to separate radioactive parts from non-radioactive building structures. Thought it might be possible to demolish the building structures by treating arising waste as non-radioactive materials, confirmation survey for radioactivity was conducted to show that there is no artificial radioactive nuclides produced by operation in the facility. This report describes the procedures studied on measurement of radioactivity and decontamination, and the results of its implementation in the JPDR dismantling demonstration project. (author)

Biogenesis of tritiated and carbon-14 methane from low-level radioactive waste

International Nuclear Information System (INIS)

Francis, A.J.; Dobbs, S.; Doering, R.F.

1980-01-01

Methane bacteria were detected in leachate samples collected from commercial low-level radioactive waste disposal sites. Significant amounts of tritiated and carbon-14 methane were generated by a mixed methanogenic culture from a leachate sample collected from the low-level radioactive waste disposal site, Maxey Flats, KY. Tritiated methane was produced by methane bacteria from synthetic media containing 2 mCi of tritium as tritiated water or tritiated acetate, and the level of tritium added to the medium had no effect on methanogenesis. Under anaerobic conditions the organic compounds containing 14 C and 3 H activity and tritiated water in the waste are metabolized by microorganisms and they produce radioactive gases which escape into the environment from the disposal sites. 4 figures, 3 tables

The incorporation of low and medium level radioactive wastes (solids and liquids) in cement

International Nuclear Information System (INIS)

Brown, D.J.; Capp, P.D.; Smith, D.L.

1982-08-01

Laboratory studies and mixing plant trials on simulated radioactive waste formulations are reported. Long term stability testing of various formulations including those containing blast furnace slag-ordinary Portland cement, sodium nitrate, ion exchange resins, and sodium nitrate-tributyl phosphate, are reported and some results are given. Mixing plant trials with a high shear cement mixer are reported. An outline of future work is presented. (U.K.)

Status of technologies related to radioactive waste management and disposal

International Nuclear Information System (INIS)

1979-09-01

The document discusses the status of technologies relevant to radioactive waste management and disposal, as defined by the INFCE Working Group 7 study. All fuel cycle wastes, with the exception of mill tailings, are placed in mined geologic repositories. In addition to the availability of technologies, the document discusses the: a) importance of the systems viewpoint, b) importance of modeling, c) need for site-specific investigations, d) consideration of future sub-surface human activities and e) prospects for successful isolation. In the sections on waste isolation and repository safety assessments, principal considerations are discussed. The document concludes that successful isolation of radioactive wastes from the biosphere appears technically feasible for periods of thousands of years provided that the systems view is used in repository siting and design

EPA's approach to regulation of mixed waste and status of future activities

International Nuclear Information System (INIS)

Shackleford, B.

1988-01-01

Regulation of radioactive mixed waste is a topic that has received much attention in the past several years. Much of the discussion and confusion stemmed from uncertainty about applicable regulatory authorities. On July 3, 1986, EPA clarified its position that the Resource Conservation and Recovery Act (RCRA) applied to the hazardous component of radioactive mixed waste. The Agency announced this clarification in the Federal Register and informed States that they must seek authority to regulate mixed waste in order to obtain or maintain RCRA authorization to administer and enforce a hazardous waste program in lieu of EPA. Since that time, five States have received authorization to regulate mixed waste: Colorado, South Carolina, Tennessee, Washington, and Georgia. Authorized States issue RCRA permits in lieu of EPA. Currently, 44 States have been authorized for the base RCRA program, Conversely, 12 States and Trust Territories have no RCRA authorization. In these States and territories, EPA administers that RCRA hazardous waste program. A more stringent State requirement occurs when a State allows less time for compliance than would be provided under Federal law, for example. There is a third authorization category with respect to mixed waste that I have yet to address. This category is made up of States which have EPA authorization to regulate hazardous waste but have yet to obtain mixed waste authorization. Most States fall into this category. In these States, of which there are 39, mixed wastes are not hazardous wastes and subject to Subtitle C regulations

Summary of the Law relating to Atomic Energy and Radioactive Subtances as at March 1979

International Nuclear Information System (INIS)

Sim, D.F.; Ritchie, K.J.S.

1979-01-01

This Note contains summaries of new laws and regulations on atomic energy and radioactive substances and amendments made to previous ones in the United Kingdom as at March 1979, including international regulations and agreements. New materials referred to includes the Nuclear Installations (Excepted Matter) Regulations 1978, the Medicines (Radioactive Substances) Order 1978, the Medicines (Committee on Radiation from Radioactive Medicinal Products) Order 1978 and the Medicines (Administration of Radioactive Substances) Regulations 1978. The Note also reproduces other amendments in nuclear legislation, already referred to in a previous Note dated March 1978. (NEA) [fr

Blending of Low-Level Radioactive Waste for NPP Decommissioning

International Nuclear Information System (INIS)

Kessel, David S.; Kim, Chang Lak

2016-01-01

Radioactive wastes may are generated throughout the life cycle of a nuclear power plant. These wastes can be categorized as follows: Operational wastes in the form of solids, liquids and gases. Plant components resulting from maintenance, modification or life extension work (e.g. steam generators, pumps, valves, control rods, spent filters, etc.). Materials from the structure of the plant and equipment (e.g. metals and concrete that result in large quantities of waste upon decommissioning Large quantities of materials will be generated during decommissioning and dismantling. A significant proportion of these materials will only be slightly contaminated with radioactivity. Due to economies of scale, recycling and reuse options are more likely to be cost effective for such large quantities of materials than for the relatively smaller quantities arising during operation. These materials also present opportunities to manage waste more effectively by utilizing the approaches to blending discussed in this paper. The NRC uses allows blending based on risk and performance measures for public health and safety. Performance-based regulation means that the blended waste must meet the limits on radiation exposures at the disposal facility and limits on how much the radioactivity concentration may vary or in other words, how homogeneous and well mixed it is. LLW blending is an approach to waste management that can give greater flexibility for disposal options for NPP waste from the entire life cycle of the plant which includes operational wastes such as ion exchange resins and filters, maintenance wastes which include replacement components (discrete items), and large quantities of decommissioning wastes

Blending of Low-Level Radioactive Waste for NPP Decommissioning

Energy Technology Data Exchange (ETDEWEB)

Kessel, David S.; Kim, Chang Lak [KEPCO, Ulsan (Korea, Republic of)

2016-05-15

Radioactive wastes may are generated throughout the life cycle of a nuclear power plant. These wastes can be categorized as follows: Operational wastes in the form of solids, liquids and gases. Plant components resulting from maintenance, modification or life extension work (e.g. steam generators, pumps, valves, control rods, spent filters, etc.). Materials from the structure of the plant and equipment (e.g. metals and concrete that result in large quantities of waste upon decommissioning Large quantities of materials will be generated during decommissioning and dismantling. A significant proportion of these materials will only be slightly contaminated with radioactivity. Due to economies of scale, recycling and reuse options are more likely to be cost effective for such large quantities of materials than for the relatively smaller quantities arising during operation. These materials also present opportunities to manage waste more effectively by utilizing the approaches to blending discussed in this paper. The NRC uses allows blending based on risk and performance measures for public health and safety. Performance-based regulation means that the blended waste must meet the limits on radiation exposures at the disposal facility and limits on how much the radioactivity concentration may vary or in other words, how homogeneous and well mixed it is. LLW blending is an approach to waste management that can give greater flexibility for disposal options for NPP waste from the entire life cycle of the plant which includes operational wastes such as ion exchange resins and filters, maintenance wastes which include replacement components (discrete items), and large quantities of decommissioning wastes.

Environmental assessment for the treatment of Class A low-level radioactive waste and mixed low-level waste generated by the West Valley Demonstration Project

International Nuclear Information System (INIS)

1995-11-01

The U.S. Department of Energy (DOE) is currently evaluating low-level radioactive waste management alternatives at the West Valley Demonstration Project (WVDP) located on the Western New York Nuclear Service Center (WNYNSC) near West Valley, New York. The WVDP's mission is to vitrify high-level radioactive waste resulting from commercial fuel reprocessing operations that took place at the WNYNSC from 1966 to 1972. During the process of high-level waste vitrification, low-level radioactive waste (LLW) and mixed low-level waste (MILLW) will result and must be properly managed. It is estimated that the WVDP's LLW storage facilities will be filled to capacity in 1996. In order to provide sufficient safe storage of LLW until disposal options become available and partially fulfill requirements under the Federal Facilities Compliance Act (FFCA), the DOE is proposing to use U.S. Nuclear Regulatory Commission-licensed and permitted commercial facilities in Oak Ridge, Tennessee; Clive, Utah; and Houston, Texas to treat (volume-reduce) a limited amount of Class A LLW and MLLW generated from the WVDP. Alternatives for ultimate disposal of the West Valley LLW are currently being evaluated in an environmental impact statement. This proposed action is for a limited quantity of waste, over a limited period of time, and for treatment only; this proposal does not include disposal. The proposed action consists of sorting, repacking, and loading waste at the WVDP; transporting the waste for commercial treatment; and returning the residual waste to the WVDP for interim storage. For the purposes of this assessment, environmental impacts were quantified for a five-year operating period (1996 - 2001). Alternatives to the proposed action include no action, construction of additional on-site storage facilities, construction of a treatment facility at the WVDP comparable to commercial treatment, and off-site disposal at a commercial or DOE facility

Measurement of activity of radioactive gas

International Nuclear Information System (INIS)

Zhuo Renhong; Lei Jiarong; Wen Dezhi; Cheng Jing; Zheng Hui

2005-10-01

A set of standard instrument system with their accessories for the measurement of activity of radioactive gas have been developed. The specifications and performances of the system have been tested and examined. The conventional true values of activity of radioactive gas have been measured and its uncertainty has been assessed. The technique of the dissemination of the measurement of activity of radioactive gas has been researched. The specification and performance of the whole set of apparatus meet the requirements of the relational standard, critra, regulation, it can be regard as a work standard for the measurement of activity of radioactive gas in CAEP. (authors)

Radioactive transformations

CERN Document Server

Rutherford, Ernest

2012-01-01

Radioactive Transformations describes Ernest Rutherford's Nobel Prize-winning investigations into the mysteries of radioactive matter. In this historic work, Rutherford outlines the scientific investigations that led to and coincided with his own research--including the work of Wilhelm Rӧntgen, J. J. Thomson, and Marie Curie--and explains in detail the experiments that provided a glimpse at special relativity, quantum mechanics, and other concepts that would shape modern physics. This new edition features a comprehensive introduction by Nobel Laureate Frank Wilczek which engagingly explains how Rutherford's early research led to a better understanding of topics as diverse as the workings of the atom's nucleus, the age of our planet, and the fusion in stars.

High Level Radioactive Waste Management

International Nuclear Information System (INIS)

1991-01-01

The proceedings of the second annual international conference on High Level Radioactive Waste Management, held on April 28--May 3, 1991, Las Vegas, Nevada, provides information on the current technical issue related to international high level radioactive waste management activities and how they relate to society as a whole. Besides discussing such technical topics as the best form of the waste, the integrity of storage containers, design and construction of a repository, the broader social aspects of these issues are explored in papers on such subjects as conformance to regulations, transportation safety, and public education. By providing this wider perspective of high level radioactive waste management, it becomes apparent that the various disciplines involved in this field are interrelated and that they should work to integrate their waste management activities. Individual records are processed separately for the data bases

Workplace-related generational characteristics of nurses: A mixed-method systematic review.

Science.gov (United States)

Stevanin, Simone; Palese, Alvisa; Bressan, Valentina; Vehviläinen-Julkunen, Katri; Kvist, Tarja

2018-06-01

The aim of this study was to describe and summarize workplace characteristics of three nursing generations: Baby Boomers, Generations X and Y. Generational differences affect occupational well-being, nurses' performance, patient outcomes and safety; therefore, nurse managers, administrators and educators are interested increasingly in making evidence-based decisions about the multigenerational nursing workforce. Mixed-method systematic review. Medline, CINAHL, PsycINFO and Scopus (January 1991-January 2017). (1) The Joanna Briggs Institute's method for conducting mixed-method systematic reviews; (2) the Preferred Reporting Items for Systematic Reviews and Meta-Analyses and (3) the Enhancing Transparency in Reporting the Synthesis of Qualitative Research guidelines. The studies' methodological quality was assessed with the Mixed-Methods Appraisal Tool. Quantitative and mixed-method studies were transformed into qualitative methods using a convergent qualitative synthesis and qualitative findings were combined with a narrative synthesis. Thirty-three studies were included with three main themes and 11 subthemes: (1) Job attitudes (work engagement; turnover intentions, reasons for leaving; reasons, incentives/disincentives to continue nursing); (2) Emotion-related job aspects (stress/resilience; well-being/job satisfaction; affective commitment; unit climate; work ethic) and (3) Practice and leadership-related aspects (autonomy; perceived competence; leadership relationships and perceptions). Baby Boomers reported lower levels of stress and burnout than did Generations X and Y, different work engagement, factors affecting workplace well-being and retention and greater intention to leave compared with Generation Y, which was less resilient, but more cohesive. Although several studies reported methodological limitations and conflicting findings, generational differences in nurses' job attitudes, emotional, practice and leadership factors should be considered to enhance

Summary of the law relating to atomic energy and radioactive substances

International Nuclear Information System (INIS)

Sim, D.F.; Ritchie, K.J.S.

1982-01-01

This Summary is an updated version of a previous revision of the Summary of the United Kingdom's legislation on atomic energy and reviews the main texts in that field. Reference is made to the regulations on atomic energy, nuclear installations, radioactive substances, transport of such substances, radiation protection etc. It is intended to be a signpost to the relevant law, but does not cover any aspect in detail. The Summary also refers to international agreements in the nuclear field: conventions and regulations on the transport of radioactive substances and nuclear material, nuclear third party liability, radiation protection and environmental protection. (NEA) [fr

Decontamination flowsheet development for a waste oil containing mixed radioactive contaminants

International Nuclear Information System (INIS)

Vijayan, S.; Buckley, L.P.

1993-01-01

The majority of waste oils contaminated with both radioactive and hazardous components are generated in nuclear power plant, research lab. and uranium-refinery operations. The waste oils are complex, requiring a detailed examination of the waste management strategies and technology options. It may appear that incineration offers a total solution, but this may not be true in all cases. An alternative approach is to decontaminate the waste oils to very low contaminant levels, so that the treated oils can be reused, burned as fuel in boilers, or disposed of by commercial incineration. This paper presents selected experimental data and evaluation results gathered during the development of a decontamination flowsheet for a specific waste oil stores at Chalk River Labs. (CRL). The waste oil contains varying amounts of lube oils, grease, paint, water, particulates, sludge, light chloro- and fluoro-solvents, polychlorinated biphenyls (PCB), complexing chemicals, uranium, chromium, iron, arsenic and manganese. To achieve safe management of this radioactive and hazardous waste, several treatment and disposal methods were screened. Key experiments were performed at the laboratory-scale to confirm and select the most appropriate waste-management scheme based on technical, environmental and economic criteria. The waste-oil-decontamination flowsheet uses a combination of unit operations, including prefiltration, acid scrubbing, and aqueous-leachage treatment by precipitation, microfiltration, filter pressing and carbon adsorption. The decontaminated oil containing open-quotes de minimisclose quotes levels of contaminants will undergo chemical destruction of PCBs and final disposal by incineration. The recovered uranium will be recycled to a uranium milling process

Regulatory focussing of the relevant aspects related to the transport of radioactive materials in Argentina

International Nuclear Information System (INIS)

Lopez Vietri, J.R.; Novo, R.G.; Bianchi, A.J.

1998-01-01

Full text: This paper points out a summary of the relevant aspects related to the transport of radioactive material in Argentina treated only from a regulatory focussing, it is to say from the point of view of its competent authority of application the Nuclear Regulatory Authority (in Spanish, the Autoridad Regulatoria Nuclear, ARN). Firstly, it is introduced the legal and regulatory framework applicable to the transport of radioactive material and the corresponding authorities involved (ARN, Secretary of Transport, and the Argentine Air Force, Naval Prefecture and Navy). Then, it is presented a schedule of the main characteristics of the shipments of radioactive material used in both the nuclear cycle and in medicine, industry and research, and an average of the shipments annually transported in Argentina. Further on the paper briefly analyses the ARN sources and the way in which it performs the compliance assurance with the in-force transport regulations in the country. Particularly, it is explained certain main tools used by the compliance system, as for example, transport notice, data base, licensing of certain design packages, shipments and materials, inspection and audits, and fees and sanctions regimes. On the other hand, it is mentioned the Argentine experience in the development, licensing, manufacture and use of domestic designs of Type B(U) packages and special form radioactive material (cobalt 60 and iridium 192 sealed sources). Moreover, it is concisely described test facilities available in the country necessary to perform the mentioned designs. Finally, the paper shortly describes the ARN main transport activities exclusively concerning the relationship with other national organisations (Federal Police, Gendarmerie, Naval Prefecture and Argentine Institute of Material Rationalisation, in Spanish Instituto Argentino de Racionalizacion de Materiales - IRAM) and with regional and inter regional organisations (South American Common Market, in Spanish

Volume Reduction of Decommissioning Radioactive Burnable and Metal Wastes

Energy Technology Data Exchange (ETDEWEB)

Min, B. Y.; Lee, Y. J.; Yun, G. S.; Lee, K. W.; Moon, J. K. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Choi, Y. K.; Cho, J. H. [SunKwang Atomic Energy Safety Co., Seoul (Korea, Republic of)

2014-10-15

A large quantity of radioactive waste was generated during the decommissioning projects. For the purpose of the volume reduction and clearance for decommissioning wastes from decommissioning projects, the incineration and high melting technology has been selected for the decommissioning wastes treatment. The volume reduction of the combustible wastes through the incineration technologies has merits from the view point of a decrease in the amount of waste to be disposed of resulting in a reduction of the disposal cost. Incineration is generally accepted as a method of reducing the volume of radioactive waste. The incineration technology is an effective treatment method that contains hazardous chemicals as well as radioactive contamination. Incinerator burns waste at high temperature. Incineration of a mixture of chemically hazardous and radioactive materials, known as 'mixed waste,' has two principal goals: to reduce the volume and total chemical toxicity of the waste. Incineration itself does not destroy the metals or reduce the radioactivity of the waste. A proven melting technology is currently used for low-level waste (LLW) at several facilities worldwide. These facilities use melting as a means of processing LLW for unrestricted release of the metal or for recycling within the nuclear sector. About 16.4 tons of decommissioning combustible waste has been treated using Oxygen Enriched incineration. The incineration facility operated quite smoothly through the analysis major critical parameters of off-gas.

Volume Reduction of Decommissioning Radioactive Burnable and Metal Wastes