WorldWideScience

Sample records for nuclear waste solidification

  1. Nuclear waste solidification

    Science.gov (United States)

    Bjorklund, William J.

    1977-01-01

    High level liquid waste solidification is achieved on a continuous basis by atomizing the liquid waste and introducing the atomized liquid waste into a reaction chamber including a fluidized, heated inert bed to effect calcination of the atomized waste and removal of the calcined waste by overflow removal and by attrition and elutriation from the reaction chamber, and feeding additional inert bed particles to the fluidized bed to maintain the inert bed composition.

  2. Nuclear waste solidification

    International Nuclear Information System (INIS)

    Bjorklund, W.J.

    1977-01-01

    High level liquid waste solidification is achieved on a continuous basis by atomizing the liquid waste and introducing the atomized liquid waste into a reaction chamber including a fluidized, heated inert bed to effect calcination of the atomized waste and removal of the calcined waste by overflow removal and by attrition and elutriation from the reaction chamber, and feeding additional inert bed particles to the fluidized bed to maintain the inert bed composition

  3. Spray solidification of nuclear waste

    International Nuclear Information System (INIS)

    Bonner, W.F.; Blair, H.T.; Romero, L.S.

    1976-08-01

    The spray calciner is a relatively simple machine. Operation is simple and is easily automated. Startup and shutdown can be performed in less than an hour. A wide variety of waste compositions and concentrations can be calcined under easily maintainable conditions. Spray calcination of high-level and mixed high- and intermediate-level liquid wastes has been demonstrated. Waste concentrations of from near infinite dilution to less than 225 liters per tonne of fuel are calcinable. Wastes have been calcined containing over 2M sodium. Feed concentration, composition, and flowrate can vary rapidly by over a factor of two without requiring operator action. Wastes containing mainly sodium cations can be spray calcined by addition of finely divided silica to the feedstock. A remotely replaceable atomizing nozzle has been developed for use in plant-scale equipment. Calciner capacity of over 75 l/h has been demonstrated in pilot-scale equipment. Sintered stainless steel filters are effective in deentraining over 99.9 percent of the solids that result from calcining the feedstock. The volume of recycle required from the effluent treatment system is very small. Vibrator action maintains the calcine holdup in the calciner at less than 1 kg. Successful remote operation and maintenance of a heated-wall spray calciner have been demonstrated while processing high-level waste. Radionuclide volatilization was acceptably low

  4. Species redistribution during solidification of nuclear fuel waste metal castings

    Energy Technology Data Exchange (ETDEWEB)

    Naterer, G F; Schneider, G E [Waterloo Univ., ON (Canada)

    1994-12-31

    An enthalpy-based finite element model and a binary system species redistribution model are developed and applied to problems associated with solidification of nuclear fuel waste metal castings. Minimal casting defects such as inhomogeneous solute segregation and cracks are required to prevent container corrosion and radionuclide release. The control-volume-based model accounts for equilibrium solidification for low cooling rates and negligible solid state diffusion for high cooling rates as well as intermediate conditions. Test problems involving nuclear fuel waste castings are investigated and correct limiting cases of species redistribution are observed. (author). 11 refs., 1 tab., 13 figs.

  5. Plastic solidification of radioactive wastes

    International Nuclear Information System (INIS)

    Moriyama, Noboru

    1981-01-01

    Over 20 years have elapsed after the start of nuclear power development, and the nuclear power generation in Japan now exceeds the level of 10,000 MW. In order to meet the energy demands, the problem of the treatment and disposal of radioactive wastes produced in nuclear power stations must be solved. The purpose of the plastic solidification of such wastes is to immobilize the contained radionuclides, same as other solidification methods, to provide the first barrier against their move into the environment. The following matters are described: the nuclear power generation in Japan, the radioactive wastes from LWR plants, the position of plastic solidification, the status of plastic solidification in overseas countries and in Japan, the solidification process for radioactive wastes with polyethylene, and the properties of solidified products, and the leachability of radionuclides in asphalt solids. (J.P.N.)

  6. Nuclear waste disposal: alternatives to solidification in glass proposed

    International Nuclear Information System (INIS)

    Kerr, R.A.

    1979-01-01

    More than a quarter-million cubic meters of liquid radioactive wastes are now being held at government installations awaiting final disposal. During the past 20 years, the disposal plan of choice has been to incorporate the 40 to 50 radioactive elements dissolved in liquid wastes into blocks of glass, seal the glass in metal canisters, and insert the canisters into deep, geologically stable salt beds. Over the last few years, some geologists and materials scientists have become concerned that perhaps not enough is known yet about the interaction of waste, container, and salt (or any rock) to have a reasonable assurance that the hazardous wastes will be contained successfully. The biggest advantage of glass at present is the demonstrated practicality of producing large, highly radioactive blocks of it. The frontrunner as a successor to glass is ceramics, which are nonmetallic crystalline materials formed at high temperature, such as chinaware or natural minerals. An apparent advantage of ceramics is that they already have an ordered atomic structure, whose properties can be tailored to a particular waste element and to conditions of a specific disposal site. A ceramic tailored for waste disposal called supercalcine-ceramic has been developed. It was emphasized that the best minerals for waste solidification may be those that have proved most stable under natural conditions over geologic time. Disadvantage to ceramics are radiation damage and transmutation. However, it is now obvious that some ceramics are more stable than glass under certain conditions. Metal-encapsulated ceramic, called cermet, is being developed as a waste form. Cermets are considerably more resistant at 100 0 C than a borosilicate waste glass. Researchers are now testing prospective waste forms under the most extreme conditions that might prevail in a waste disposal site

  7. Integral solution of equiaxed solidification with an interface kinetics model for nuclear waste management

    International Nuclear Information System (INIS)

    Naterer, G.F.

    1996-01-01

    In this paper, a one-dimensional analysis of energy and species transport during binary dendritic solidification is presented and compared to experimental results. The paper's objective is a continuation of previous studies of solidification control for the waste management of nuclear materials in the underground disposal concept. In the present analysis, interface kinetics at the solid - liquid interface accounts for recalescent thermal behaviour during solidification. The theoretical results were compared to available experimental results and the agreement appears fair although some discrepancies have been attributed to uncertainties with thermophysical properties. (author)

  8. High-level waste solidification system for the Western New York Nuclear Service Center

    International Nuclear Information System (INIS)

    Carrell, J.R.; Holton, L.K.; Siemens, D.H.

    1982-01-01

    A preconceptual design for a waste conditioning and solidification system for the immobilization of the high-level liquid wastes (HLLW) stored at the Western New York Nuclear Service Center (WNYNSC), West Valley, New York was completed in 1981. The preconceptual design was conducted as part of the Department of Energy's (DOE) West Valley Demonstration Project, which requires a waste management demonstration at the WNYNSC. This paper summarizes the bases, assumptions, results and conclusions of the preconceptual design study

  9. Purification and solidification of reactor wastes at a Canadian nuclear generating station

    International Nuclear Information System (INIS)

    Buckley, L.P.; Burt, D.A.

    1981-01-01

    The study aimed at development and demonstration of volume reduction and solidification of CANDU reactor wastes has been underway at Chalk River Nuclear Laboratories in the Province of Ontario, Canada. The study comprises membrane separation processes, evaporator appraisal and immobilization of concentrated wastes in bitumen. This paper discusses the development work with a wiped-film evaporator and the successful completion of demonstration tests at Douglas Point Nuclear Generating Station. Heavy water from the moderator system was purified and wastes arising from pump bowl decontamination were immobilized in bitumen with the wiped-film evaporator that was used in the development tests at Chalk River

  10. Comparative study of seven glasses for solidification of nuclear wastes

    International Nuclear Information System (INIS)

    Nogues, J.L.; Hench, L.L.; Zarzycki, J.

    1982-06-01

    The relative leaching behavior of seven alkali borosilicate glasses considered for immobilization of high level radioactive wastes was compared using a static 90 0 C leach test. Leaching times studied were 1, 3, 7, 14 and 28 days with ratios of glass surface area (SA) to solution volume (V) being SA/V = 1.0 cm -1 and 0.1 cm -1 . With the range of glass compositions studied, it was not possible to determine the effect of each element on leaching behavior, however some conclusions regarding the general influence of the glass network formers can be made: the addition of Al 2 O 3 , results in a large increase in the chemical durability of the glass. The presence of Fe 2 O 3 , is necessary to develop with Al 2 O 3 a second protective layer on top of the silica-rich film that results from rapid dealkalization. The difference between the results obtained at SA/V = 1.0 cm -1 and 0.1 cm -1 shows the importance of understanding both the effects of glass composition and solution concentrations on the behavior of nuclear waste glasses

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

    International Nuclear Information System (INIS)

    Solbrig, Charles W.; Bateman, Kenneth J.

    2010-01-01

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

  12. Radioactive waste solidification material

    International Nuclear Information System (INIS)

    Nishihara, Yukio; Wakuta, Kuniharu; Ishizaki, Kanjiro; Koyanagi, Naoaki; Sakamoto, Hiroyuki; Uchida, Ikuo.

    1992-01-01

    The present invention concerns a radioactive waste solidification material containing vermiculite cement used for a vacuum packing type waste processing device, which contains no residue of calcium hydroxide in cement solidification products. No residue of calcium hydroxide means, for example, that peak of Ca(OH) 2 is not recognized in an X ray diffraction device. With such procedures, since calcium sulfoaluminate clinker and Portland cement themselves exhibit water hardening property, and slugs exhibit hydration activity from the early stage, the cement exhibits quick-hardening property, has great extension of long term strength, further, has no shrinking property, less dry- shrinkage, excellent durability, less causing damages such as cracks and peeling as processing products of radioactive wastes, enabling to attain highly safe solidification product. (T.M.)

  13. Current high-level waste solidification technology

    International Nuclear Information System (INIS)

    Bonner, W.F.; Ross, W.A.

    1976-01-01

    Technology has been developed in the U.S. and abroad for solidification of high-level waste from nuclear power production. Several processes have been demonstrated with actual radioactive waste and are now being prepared for use in the commercial nuclear industry. Conversion of the waste to a glass form is favored because of its high degree of nondispersibility and safety

  14. Solidification of low and medium level wastes in bitumen at Barsebaeck nuclear power station

    International Nuclear Information System (INIS)

    Harfors, C.

    1979-01-01

    Operating experience is presented from 4 years of bitumen solidification of wastes coming from two boiling water reactors. Methods used to sample, analyse and document the wastes are described. Transport and storage methods without remote handling have been adopted. The risk of fire is discussed and a description is given of the measures taken for fire protection. (author)

  15. Solidification method of radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Baba, Tsutomu; Chino, Koichi; Sasahira, Akira; Ikeda, Takashi

    1992-07-24

    Metal solidification material can completely seal radioactive wastes and it has high sealing effect even if a trace amount of evaporation should be caused. In addition, the solidification operation can be conducted safely by using a metal having a melting point of lower than that of the decomposition temperature of the radioactive wastes. Further, the radioactive wastes having a possibility of evaporation and scattering along with oxidation can be solidified in a stable form by putting the solidification system under an inert gas atmosphere. Then in the present invention, a metal is selected as a solidification material for radioactive wastes, and a metal, for example, lead or tin having a melting point of lower than that of the decomposition temperature of the wastes is used in order to prevent the release of the wastes during the solidification operation. Radioactive wastes which are unstable in air and scatter easily, for example, Ru or the like can be converted into a stable solidification product by conducting the solidification processing under an inert gas atmosphere. (T.M.).

  16. SRTC criticality technical review: Nuclear Criticality Safety Evaluation 93-18 Uranium Solidification Facility's Waste Handling Facility

    International Nuclear Information System (INIS)

    Rathbun, R.

    1993-01-01

    Separate review of NMP-NCS-930058, open-quotes Nuclear Criticality Safety Evaluation 93-18 Uranium Solidification Facility's Waste Handling Facility (U), August 17, 1993,close quotes was requested of SRTC Applied Physics Group. The NCSE is a criticality assessment to determine waste container uranium limits in the Uranium Solidification Facility's Waste Handling Facility. The NCSE under review concludes that the NDA room remains in a critically safe configuration for all normal and single credible abnormal conditions. The ability to make this conclusion is highly dependent on array limitation and inclusion of physical barriers between 2x2x1 arrays of boxes containing materials contaminated with uranium. After a thorough review of the NCSE and independent calculations, this reviewer agrees with that conclusion

  17. Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario Hydro's Bruce Nuclear Generating Station 'A'

    International Nuclear Information System (INIS)

    Day, J.E.; Baker, R.L.

    1995-01-01

    Ontario Hydro at the Bruce Nuclear Generating Station 'A' has undertaken a program to render the station's liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants to satisfy regulatory requirements for emissions. The system will remove radionuclide and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology

  18. Physicochemical characterization of solidification agents used and products formed with radioactive wastes at LWR nuclear power plants

    International Nuclear Information System (INIS)

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

    1978-01-01

    Solidification of evaporator concentrates, filter sludges, and spent ion exchange resins used in LWR streams is discussed. The introduction of solidification agents to immobilize these sludges and resins can increase the volume of these wastes by a factor of slightly over 1 to greater than 2, depending on the binder chosen. The agents and methods used or proposed for use in solidification of LWR power plant wastes are generally suitable for treating most of the other-than-high-level wastes generated throughout the entire fuel cycle. Among the solidification agents most commonly used or suggested for use are the inorganic cements and organic plastics, which are listed and compared. A summary of considerations important in choosing a solidification agent is presented tabularly

  19. Purification and solidification of reactor wastes at a Canadian nuclear generating station

    International Nuclear Information System (INIS)

    Buckley, L.P.; Burt, D.A.

    1981-06-01

    Chalk River Nuclear Laboratories are developing methods to condition power reactor wastes and to immobilize their radionuclides. Evaporation alone and combined with bituminization has been an important part of the program. After testing at the laboratories a 0.5 m 2 wiped-film evaporator was sent to the Douglas Point Nuclear Generating Station (220 MWe) to demonstrate its suitability to handle typical reactor liquid wastes. Two specific tasks undertaken with the wiped-film evaporator were successfully completed. The first was purification of contaminated heavy water which had leaked from the moderator circuit. The heavy water is normally recovered, cleaned by filters and ion-exchange resin and then upgraded by electrolysis. Cleaning the heavy water with the wiped-film evaporator produced better quality water for upgrading than had been achieved by any previous method and at much lower operating cost. The second task was to concentrate and immobilize a decontamination waste. The waste was generated from the decontamination of pump bowls used in the primary heat transport circuit. The simultaneous addition of the liquid waste and bitumen emulsion to the wiped-film evaporator produced a solid containing 30 wt% waste solids in a bitumen matrix. The volume reduction achieved was 16:1 based on the volumes of initial liquid waste and the final product generated. The quantity sent to storage was 20 times less than had the waste been immobilized in a cement matrix. The successful demonstration has resulted in a proposal to install a wiped-film evaporator at the station to clean heavy water and immobilize decontamination wastes. (author)

  20. Solidification of low-level wastes by inorganic binder

    International Nuclear Information System (INIS)

    Sasaki, M.T.; Shimojo, M.; Suzuki, K.; Kajikawa, A.; Karasawa, Y.

    1995-01-01

    The use of an alkali activated slag binder has been studied for solidification and stabilization of low-level wastes in nuclear power stations and spent fuel processing facilities. The activated slag effectively formed waste products having good physical properties with high waste loading for sodium sulfate, sodium nitrate, calcium pyrophosphate/phosphate and spent ion-exchange resins. Moreover, the results of the study suggest the slag has the ability to become a common inorganic binder for the solidification of various radioactive wastes. This paper also describes the fixation of radionuclides by the activated slag binder

  1. Investigation of foaming during nuclear defense-waste solidification by electric melting

    International Nuclear Information System (INIS)

    Blair, H.T.; Lukacs, J.M.

    1980-12-01

    To determine the cause of foaming, the physical and chemical composition of the glass formers that are added to the waste to produce a borosilicate melt were investigated. It was determined that the glass-forming frit was not the source of the foam-causing gases. Incomplete calcination of the waste, which results in residual hydrates, carbonates and nitrates, and the relatively high carbon and sulfate contents of the waste glass composition were also eliminated as possible sources of the foam. It was finally shown that the oxides of the multivalent ions of manganese and iron that are in the defense waste in high concentrations are the source of the foaming. Nickel oxide is also present in the waste and is suspected of contributing to the foaming. In investigating methods to reduce the foam, the focus was on the chemistry of the materials being processed rather than on the mechanical aspects of the processing equipment to avoid increasing the mechanical complexity of the melter operation. Reducing the waste loading in the host glass from 28 to 14 wt. % produced the most significant reduction in the foam. Of course this did not increase the rate at which waste can be processed. Adding carbonaceous additives or barium metaphosphate to the waste/frit mixture (batch) reduced the foaming somewhat. However, if too much reducing agent was added to the batch, iron-nickel alloys separated from the melt. Likewise, melting the batch in an inert or a reducing atmosphere reduced the foaming but produced a heterogeneous product. Finally, initial attempts to control foaming by adding reducing agents to the liquid waste and then spray-calcining it using an inert atomizing gas were not successful. The possibilities for liquid-waste treatment need to be investigated further

  2. Volume reduction/solidification of liquid radioactive waste using bitumen at Ontario hydro's Bruce nuclear generating station open-quotes Aclose quotes

    International Nuclear Information System (INIS)

    Day, J.E.; Baker, R.L.

    1994-01-01

    Ontario Hydro at the Bruce Nuclear Generating Station open-quotes Aclose quotes has undertaken a program to render the station's liquid radioactive waste suitable for discharge to Lake Huron by removing sufficient radiological and chemical contaminants from five different plant waste streams. The contaminants will be immobilized and stored at on-site radioactive waste storage facilities and the purified streams will be discharged. The discharge targets established by Ontario Hydro are set well below the limits established by the Ontario Ministry of Environment (MOE) and are based on the Best Available Technology Economically Achievable Approach (B.A.T.E.A.). ADTECHS Corporation has been selected by Ontario Hydro to provide volume reduction/solidification technology for one of the five waste streams. The system will dry and immobilize the contaminants from a liquid waste stream in emulsified asphalt using thin film evaporation technology

  3. Solidification process for toxic and hazardous wastes. Second part: Cement solidification matrices

    International Nuclear Information System (INIS)

    Donato, A.; Arcuri, L.; Dotti, M.; Pace, A.; Pietrelli, L.; Ricci, G.; Basta, M.; Cali, V.; Pagliai, V.

    1989-05-01

    This paper reports the second part of a general study carried out at the Nuclear Fuel Division aiming at verifying the possible application of the radioactive waste solidification processes to industrial hazardous wastes (RTN). The cement solidification of several RTN types has been taken into consideration, both from the technical and from the economic point of view. After a short examination of the Italian juridical and economical situation in the field, which demonstrates the need of the RTN solidification, the origin and characteristics of the RTN considered in the study and directly provided by the producing industries are reviewed. The laboratory experimental results of the cementation of RTN produced by gold manufacturing industries and by galvanic industries are reported. The cementation process can be considered a very effective mean for reducing both the RTN management costs and the environmental impact of RTN disposal. (author)

  4. Characteristics of Cement Solidification of Metal Hydroxide Waste

    Directory of Open Access Journals (Sweden)

    Dae-Seo Koo

    2017-02-01

    Full Text Available To perform the permanent disposal of metal hydroxide waste from electro-kinetic decontamination, it is necessary to secure the technology for its solidification. The integrity tests on the fabricated solidification should also meet the criteria of the Korea Radioactive Waste Agency. We carried out the solidification of metal hydroxide waste using cement solidification. The integrity tests such as the compressive strength, immersion, leach, and irradiation tests on the fabricated cement solidifications were performed. It was also confirmed that these requirements of the criteria of Korea Radioactive Waste Agency on these cement solidifications were met. The microstructures of all the cement solidifications were analyzed and discussed.

  5. Characteristics of cement solidification of metal hydroxide waste

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Dae Seo; Sung, Hyun Hee; Kim, Seung Soo; Kim, Gye Nam; Choi, Jong Won [Dept. of Decontemination Decommission Technology Development, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2017-02-15

    To perform the permanent disposal of metal hydroxide waste from electro-kinetic decontamination, it is necessary to secure the technology for its solidification. The integrity tests on the fabricated solidification should also meet the criteria of the Korea Radioactive Waste Agency. We carried out the solidification of metal hydroxide waste using cement solidification. The integrity tests such as the compressive strength, immersion, leach, and irradiation tests on the fabricated cement solidifications were performed. It was also confirmed that these requirements of the criteria of Korea Radioactive Waste Agency on these cement solidifications were met. The microstructures of all the cement solidifications were analyzed and discussed.

  6. 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

  7. Low level waste solidification practice in Japan

    International Nuclear Information System (INIS)

    Sakata, S.; Kuribayashi, H.; Kono, Y.

    1981-01-01

    Both sea dumping and land isolation are planned to be accomplished for low level waste disposal in Japan. The conceptual design of land isolation facilities has been completed, and site selection will presently get underway. With respect to ocean dumping, safety surveys are being performed along the lines of the London Dumping Convention and the Revised Definitions and Recommendations of the IAEA, and the review of Japanese regulations and applicable criteria is being expedited. This paper discusses the present approach to waste solidification practices in Japan. It reports that the bitumen solidification process and the plastic solidification process are being increasingly used in Japan. Despite higher investment costs, both processes have advantages in operating cost, and are comparable to the cement solidification process in overall costs

  8. 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.)

  9. Techniques for the solidification of high-level wastes

    International Nuclear Information System (INIS)

    1977-01-01

    The problem of the long-term management of the high-level wastes from the reprocessing of irradiated nuclear fuel is receiving world-wide attention. While the majority of the waste solutions from the reprocessing of commercial fuels are currently being stored in stainless-steel tanks, increasing effort is being devoted to developing technology for the conversion of these wastes into solids. A number of full-scale solidification facilities are expected to come into operation in the next decade. The object of this report is to survey and compare all the work currently in progress on the techniques available for the solidification of high-level wastes. It will examine the high-level liquid wastes arising from the various processes currently under development or in operation, the advantages and disadvantages of each process for different types and quantities of waste solutions, the stages of development, the scale-up potential and flexibility of the processes

  10. Plastic solidification system at Hamaoka Nuclear Power Station

    International Nuclear Information System (INIS)

    Okajima, Hiroyuki; Iokibe, Hiroyuki; Tsukiyama, Shigeru; Suzuki, Michio; Yamaguchi, Masato

    1987-01-01

    In Unit 1 and 2 of the Hamaoka Nuclear Power Station, radioactive waste was previously solidified in cement. By this method, the quantity of waste thus treated is relatively small, resulting in large number of the solidified drums. In order to solve this problem, the solidification facility using a thermosetting resin was employed, which is in operation since January 1986 for Unit 1, 2 and 3. As compared with the cement solidification, the solidified volume of concentrated liquid is about 1/12 and of spent-resin slurry is about 1/4 in plastic solidification. The following are described: course leading to the employment, the plastic solidification facility, features of the facility, operation results so far with the facility, etc. (Mori, K.)

  11. Development of high-level waste solidification technology 1

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Joon Hyung; Kim, Hwan Young; Kim, In Tae [and others

    1999-02-01

    Spent nuclear fuel contains useful nuclides as valuable resource materials for energy, heat and catalyst. High-level wastes (HLW) are expected to be generated from the R and D activities and reuse processes. It is necessary to develop vitrification or advanced solidification technologies for the safe long-term management of high level wastes. As a first step to establish HLW vitrification technology, characterization of HLWs that would arise at KAERI site, glass melting experiments with a lab-scale high frequency induction melter, and fabrication and property evaluation of base-glass made of used HEPA filter media and additives were performed. Basic study on the fabrication and characterization of candidate ceramic waste form (Synroc) was also carried out. These HLW solidification technologies would be directly useful for carrying out the R and Ds on the nuclear fuel cycle and waste management. (author). 70 refs., 29 tabs., 35 figs.

  12. Plastic solidification system for radioactive waste

    International Nuclear Information System (INIS)

    Kani, Jiro; Irie, Hiromitsu; Obu, Etsuji; Nakayama, Yasuyuki; Matsuura, Hiroyuki.

    1979-01-01

    The establishment of a new solidification system is an important theme for recent radioactive-waste disposal systems. The conditions required of new systems are: (1) the volume of the solidified product to be reduced, and (2) the property of the solidified product to be superior to the conventional ones. In the plastic solidification system developed by Toshiba, the waste is first dried and then solidified with thermosetting resin. It has been confirmed that the property of the plastic solidified product is superior to that of the cement-or bitumen-solidified product. Investigation from various phases is being carried on for the application of this method to commercial plants. (author)

  13. Polyethylene solidification of low-level wastes

    International Nuclear Information System (INIS)

    Kalb, P.D.; Colombo, P.

    1985-02-01

    This topical report describes the results of an investigation on the solidification of low-level radioactive waste in polyethylene. Waste streams selected for this study included those which result from advanced volume reduction technologies (dry evaporator concentrate salts and incinerator ash) and those which remain problematic for solidification using contemporary agents (ion exchange resins). Four types of commercially available low-density polyethylenes were employed which encompass a range of processing and property characteristics. Process development studies were conducted to ascertain optimal process control parameters for successful solidification. Maximum waste loadings were determined for each waste and polyethylene type. Property evaluation testing was performed on laboratory-scale specimens to assess the potential behavior of actual waste forms in a disposal environment. Waste form property tests included water immersion, deformation under compressive load, thermal cycling and radionuclide leaching. Recommended waste loadings of 70 wt % sodium sulfate, 50 wt % boric acid, 40 wt % incinerator ash, and 30 wt % ion exchange resins, which are based on process control and waste form performance considerations are reported. 37 refs., 33 figs., 22 tabs

  14. Method of processing radioactive liquid wastes by solidification with cement

    International Nuclear Information System (INIS)

    Yasumura, Keijiro; Matsuura, Hiroyuki.

    1975-01-01

    Object: To subject radioactive liquid wastes to a cement solidification treatment after heating and drying it by a thin film scrape-off drier to render it into the form of power, and then molding it into pellets for the treatment. Structure: Radioactive liquid wastes discharged from a nuclear power plant or nuclear reactor are supplied through a storage tank into a thin film scrape-off drier. In the drier, the radioactive liquid wastes are heated to separate the liquid, and the residue is taken out as dry powder from the scrape-off apparatus. The powder obtained in this way is molded into pellets of a desired form. These pellets are then packed in a drum can or similar container, into which cement paste is then poured for solidification. (Moriyama, K.)

  15. NPP radioactive waste processing and solidification

    International Nuclear Information System (INIS)

    Nikiforov, A.S.; Polyakov, A.S.; Zakharova, K.P.

    1983-01-01

    The problems of proce-sing NPP intermediate level- and low-level liquid radioactive wastes (LRW) are considered. Various methods are compared of LWR solidification on the base of bituminization, cement grouting and inclusion into synthetic resins. It is concluded that the considered methods ensure radioactive radionuclides effluents into open hydronetwork at the level below the sanitary, standards

  16. Microwave solidification development for Rocky Flats waste

    Energy Technology Data Exchange (ETDEWEB)

    Dixon, D.; Erle, R.; Eschen, V. [and others

    1994-04-01

    The Microwave Engineering Team at the Rocky Flats Plant has developed a production-scale system for the treatment of hazardous, radioactive, and mixed wastes using microwave energy. The system produces a vitreous final form which meets the acceptance criteria for shipment and disposal. The technology also has potential for application on various other waste streams from the public and private sectors. Technology transfer opportunities are being identified and pursued for commercialization of the microwave solidification technology.

  17. Microwave solidification development for Rocky Flats waste

    International Nuclear Information System (INIS)

    Dixon, D.; Erle, R.; Eschen, V.

    1994-04-01

    The Microwave Engineering Team at the Rocky Flats Plant has developed a production-scale system for the treatment of hazardous, radioactive, and mixed wastes using microwave energy. The system produces a vitreous final form which meets the acceptance criteria for shipment and disposal. The technology also has potential for application on various other waste streams from the public and private sectors. Technology transfer opportunities are being identified and pursued for commercialization of the microwave solidification technology

  18. Sandia solidification process: a broad range aqueous waste solidification method

    International Nuclear Information System (INIS)

    Lynch, R.W.; Dosch, R.G.; Kenna, B.T.; Johnstone, J.K.; Nowak, E.J.

    1976-01-01

    New ion-exchange materials of the hydrous oxide type were developed for solidifying aqueous radioactive wastes. These materials have the general formula M[M'/sub x/O/sub y/H/sub z/]/sub n/, where M is an exchangeable cation of charge +n and M' may be Ti; Nb; Zr, or Ta. Affinities for polyvalent cations were found to be very high and ion-exchange capacities large (e.g., 4.0--4.5 meq/g for NaTi 2 O 5 H depending on moisture content). The effectiveness of the exchangers for solidifying high-level waste resulting from reprocessing light-water reactor fuel was demonstrated in small-scale tests. Used in conjunction with anion exchange resin, these materials reduced test solution radioactivity from approximately 0.2 Ci/ml to as low as approximately 2 nCi/ml. The residual radioactivity was almost exclusively due to 106 Ru and total α-activity was only a few pCi/ml. Alternative methods of consolidating the solidified waste were evaluated using nonradioactive simulants. Best results were obtained by pressure-sintering which yielded essentially fully dense ceramics, e.g., titanate/titania ceramics with bulk density as high as 4.7 g/cm 3 , waste oxide content as high as 1.2 g/cm 3 , and leach resistance comparable to good borosilicate glass. Based on the above results, a baseline process for solidifying high-level waste was defined and approximate economic analyses indicated costs were not prohibitive. Additional tests have demonstrated that, if desired, operating conditions could be modified to allow recovery of radiocesium (and perhaps other isotopes) during solidification of the remaining constituents of high-level waste. Preliminary tests have also shown that these materials offer promise for treating tank-stored neutralized wastes

  19. Solidification of high-level radioactive wastes. Final report

    International Nuclear Information System (INIS)

    1979-06-01

    A panel on waste solidification was formed at the request of the Nuclear Regulatory Commission to study the scientific and technological problems associated with the conversion of liquid and semiliquid high-level radioactive wastes into a stable form suitable for transportation and disposition. Conclusions reached and recommendations made are as follows. Many solid forms described in this report could meet standards as stringent as those currently applied to the handling, storage, and transportation of spent fuel assemblies. Solid waste forms should be selected only in the context of the total radioactive waste management system. Many solid forms are likely to be satisfactory for use in an appropriately designed system, The current United States policy of deferring the reprocessing of commercial reactor fuel provides additional time for R and D solidification technology for this class of wastes. Defense wastes which are relatively low in radioactivity and thermal power density can best be solidified by low-temperature processes. For solidification of fresh commercial wastes that are high in specific activity and thermal power density, the Panel recommends that, in addition to glass, the use of fully-crystalline ceramics and metal-matrix forms be actively considered. Preliminary analysis of the characteristics of spent fuel pins indicates that they may be eligible for consideration as a waste form. Because the differences in potential health hazards to the public resulting from the use of various solid form and disposal options are likely to be small, the Panel concludes that cost, reliability, and health hazards to operating personnel will be major considerations in choosing among the options that can meet safety requiremens. The Panel recommends that responsibility for all radioactive waste management operations (including solidification R and D) should be centralized

  20. 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.)

  1. Reduction of 68Ge activity containing liquid waste from 68Ga PET chemistry in nuclear medicine and radiopharmacy by solidification

    NARCIS (Netherlands)

    E. de Blois (Erik); H.S. Chan (Ho Sze); K. Roy (Kamalika); E.P. Krenning (Eric); W.A.P. Breeman (Wouter)

    2011-01-01

    textabstractPET with68Ga from the TiO2- or SnO2- based68Ge/68Ga generators is of increasing interest for PET imaging in nuclear medicine. In general, radionuclidic purity (68Ge vs.68Ga activity) of the eluate of these generators varies between 0.01 and 0.001%. Liquid waste containing low amounts

  2. Solidification of ion exchange resin wastes

    International Nuclear Information System (INIS)

    1982-08-01

    Solidification media investigated included portland type I, portland type III and high alumina cements, a proprietary gypsum-based polymer modified cement, and a vinyl ester-styrene thermosetting plastic. Samples formulated with hydraulic cement were analyzed to investigate the effects of resin type, resin loading, waste-to-cement ratio, and water-to-cement ratio. The solidification of cation resin wastes with portland cement was characterized by excessive swelling and cracking of waste forms, both after curing and during immersion testing. Mixed bed resin waste formulations were limited by their cation component. Additives to improve the mechanical properties of portland cement-ion exchange resin waste forms were evaluated. High alumina cement formulations dislayed a resistance to deterioration of mechanical integrity during immersion testing, thus providing a significant advantage over portland cements for the solidification of resin wastes. Properties of cement-ion exchange resin waste forms were examined. An experiment was conducted to study the leachability of 137 Cs, 85 Sr, and 60 Co from resins modified in portland type III and high alumina cements. The cumulative 137 Cs fraction release was at least an order of magnitude greater than that of either 85 Sr or 60 Co. Release rates of 137 Cs in high alumina cement were greater than those in portland III cement by a factor of two.Compressive strength and leach testing were conducted for resin wastes solidified with polymer-modified gypsum based cement. 137 Cs, 85 Sr, and 60 Co fraction releases were about one, two and three orders of magnitude higher, respectively, than in equivalent portland type III cement formulations. As much as 28.6 wt % dry ion exchange resin was successfully solidified using vinyl ester-styrene compared with a maximum of 25 wt % in both portland and gypsum-based cement

  3. Solidification of highly active wastes

    International Nuclear Information System (INIS)

    Morris, J.B.

    1984-11-01

    Final reports are presented on work on the following topics: glass technology; enhancement of off-gas aerosol collection; formation and trapping of volatile ruthenium; volatilisation of caesium, technetium and tellurium in high-level waste vitrification; deposition of ruthenium; and calcination of high-level waste liquors. (author)

  4. Solidification of highly active wastes

    International Nuclear Information System (INIS)

    Morris, J.B.

    1986-07-01

    This document contains the annual reports for the contracts: (A) Glass Technology; (B) Calcination of Highly Active Waste Liquors; (C) Formation and Trapping of Volatile Ruthenium; (D) Deposition of Ruthenium; (E) Enhancement of Off-Gas Aerosol Collection; (F) Volatilisation of Cs, Tc and Te in High Level Waste Vitrification. (author)

  5. Evaluation of process alternatives for solidification of the West Valley high-level liquid wastes

    International Nuclear Information System (INIS)

    Holton, L.K.; Larson, D.E.

    1982-01-01

    The Department of Energy (DOE) established the West Valley Solidification Project (WVSP) in 1980. The project purpose is to demonstrate removal and solidification of the high-level liquid wastes (HLLW) presently stored in tanks at the Western New York Nuclear Service Center (WNYNSC), West Valley, New York. As part of this effort, the Pacific Northwest Laboratory (PNL) conducted a study to evaluate process alternatives for solidifcation of the WNYNSC wastes. Two process approaches for waste handling before solidification, together with solidification processes for four terminal and four interim waste forms, were considered. The first waste-handling approach, designated the salt/sludge separation process, involves separating the bulk of the nonradioactive nuclear waste constituents from the radioactive waste constituents, and the second waste-handling approach, designated the combined-waste process, involves no waste segregation prior to solidification. The processes were evaluated on the bases of their (1) readiness for plant startup by 1987, (2) relative technical merits, and (3) process cost. The study has shown that, based on these criteria, the salt/sludge separation process with a borosilicate glass waste form is preferred when producing a terminal waste form. It was also concluded that if an interim waste form is to be used, the preferred approach would be the combined waste process with a fused-salt waste form

  6. The solidification of radioactive waste

    International Nuclear Information System (INIS)

    Nagaya, Kiichi; Fujimoto, Yoshio; Hashimoto, Yasuo; Nomura, Ichiro

    1985-01-01

    A previous paper covered the decomposition and vitrification of Na 2 SO 4 (the primary component of the liquid waste from BWR) with silica. Now, in order to establish an integrated treatment system for the radioactive waste from BWR, this paper examines the effects of combining incinerator ash and other incinerator wastes with radioactive waste on the durability of the final vitrified products. A bench scale test plat consisting of a waiped file evaporator/dryer, a Joule-heated glass melter and SO 2 absorber was therefore put into operation and run safety for a period of 3000 hours. The combination of the radioactive waste with incinerator ash and the secondary waste of the incinerator was found to make no difference on the durability of the final vitrified products effecting no increase or decrease. Durability similar to that displayed in the beaker tests was proven, with the final vitrified products exhibiting a leaching rate less than 3 x 10 -4 g/cm 2 /day at 95 deg C. (author)

  7. 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.)

  8. Reduction of 68Ge activity containing liquid waste from 68Ga PET chemistry in nuclear medicine and radiopharmacy by solidification.

    Science.gov (United States)

    de Blois, Erik; Chan, Ho Sze; Roy, Kamalika; Krenning, Eric P; Breeman, Wouter A P

    PET with 68 Ga from the TiO 2 - or SnO 2 - based 68 Ge/ 68 Ga generators is of increasing interest for PET imaging in nuclear medicine. In general, radionuclidic purity ( 68 Ge vs. 68 Ga activity) of the eluate of these generators varies between 0.01 and 0.001%. Liquid waste containing low amounts of 68 Ge activity is produced by eluting the 68 Ge/ 68 Ga generators and residues from PET chemistry. Since clearance level of 68 Ge activity in waste may not exceed 10 Bq/g, as stated by European Directive 96/29/EURATOM, our purpose was to reduce 68 Ge activity in solution from >10 kBq/g to <10 Bq/g; which implies the solution can be discarded as regular waste. Most efficient method to reduce the 68 Ge activity is by sorption of TiO 2 or Fe 2 O 3 and subsequent centrifugation. The required 10 Bq per mL level of 68 Ge activity in waste was reached by Fe 2 O 3 logarithmically, whereas with TiO 2 asymptotically. The procedure with Fe 2 O 3 eliminates ≥90% of the 68 Ge activity per treatment. Eventually, to simplify the processing a recirculation system was used to investigate 68 Ge activity sorption on TiO 2 , Fe 2 O 3 or Zeolite. Zeolite was introduced for its high sorption at low pH, therefore 68 Ge activity containing waste could directly be used without further interventions. 68 Ge activity containing liquid waste at different HCl concentrations (0.05-1.0 M HCl), was recirculated at 1 mL/min. With Zeolite in the recirculation system, 68 Ge activity showed highest sorption.

  9. 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

  10. ''New ' technology of solidification of liquid radioactive waste'

    International Nuclear Information System (INIS)

    Sytyl, V.A.; Svistova, L.M.; Spiridonova, V.P.

    1998-01-01

    It is generally accepted that the best method of processing of radioactive waste is its solidification and then storage. At present time, three methods of solidification of radioactive waste are widely used in the world: cementation, bituminous grouting and vitrification. But they do not solve the problem of ecologically processing of waste because of different disadvantages. General disadvantages are: low state of filling, difficulties in solidification of the crystalline hydrated forms of radioactive waste; particular sphere of application and economical difficulties while processing the great volume of waste. In connection with it the urgent necessity is emerging: to develop less expensive and ecologically more reliable technology of solidification of radioactive waste. A new method of solidification is presented with its technical schema. (N.C.)

  11. Inspection method for solidification product of radioactive waste and method of preparing solidification product of radiation waste

    International Nuclear Information System (INIS)

    Izumida, Tatsuo; Tamada, Shin; Matsuda, Masami; Kamata, Shoji; Kikuchi, Makoto.

    1993-01-01

    A powerful X-ray generation device using an electron-ray accelerator is used for inspecting presence or absence of inner voids in solidification products of radioactive wastes during or after solidification. By installing the X-ray CT system and the radioactive waste solidifying facility together, CT imaging for solidification products is conducted in a not-yet cured state of solidifying materials during or just after the injection. If a defect that deteriorates the durability of the solidification products should be detected, the solidification products are repaired, for example, by applying vibrations to the not-yet cured solidification products. Thus, since voids or cracks in the radioactive wastes solidification products, which were difficult to be measured so far, can be measured in a short period of time accurately thereby enabling to judge adaptability to the disposal standards, inspection cost for the radioactive waste solidification product can be saved remarkably. Further, the inside of the radioactive waste solidification products can be evaluated correctly and visually, so that safety in the ground disposal storage of the radioactive solidification products can be improved remarkably. (N.H.)

  12. The solidification of aluminum production waste in geopolymer matrix

    Czech Academy of Sciences Publication Activity Database

    Perná, Ivana; Hanzlíček, Tomáš

    2014-01-01

    Roč. 84, DEC 1 (2014), s. 657-662 ISSN 0959-6526 Institutional support: RVO:67985891 Keywords : aluminum waste * solidification * recycling * geopolymer Subject RIV: DM - Solid Waste and Recycling Impact factor: 3.844, year: 2014

  13. Properties and solidification of decontamination wastes

    International Nuclear Information System (INIS)

    Davis, M.S.; Piciulo, P.L.; Bowerman, B.S.; Adams, J.W.; Milian, L.

    1983-01-01

    LWRs will require one or more chemical decontaminations to achieve their designed lifetimes. Primary system decontamination is designed to lower radiation fields in areas where plant maintenance personnel must work. Chemical decontamination methods are either hard (concentrated chemicals, approximately 5 to 25 weight percent) or soft (dilute chemicals less than 1 percent by weight). These methods may have different chemical reagents, some tailor-made to the crud composition and many methods are and will be proprietary. One factor common to most commercially available processes is the presence of organic acids and chelates. These types of organic reagents are known to enhance the migration of radionuclides after disposal in a shallow land burial site. The NRC sponsors two programs at Brookhaven National Laboratory that are concerned with the management of decontamination wastes which will be generated by the full system decontamination of LWRs. These two programs focus on potential methods for degrading or converting decontamination wastes to more acceptable forms prior to disposal and the impact of disposing of solidified decontamination wastes. The results of the solidification of simulated decontamination resin wastes will be presented. Recent results on combustion of simulated decontamintion wastes will be described and procedures for evaluating the release of decontamination reagents from solidified wastes will be summarized

  14. Solidification of radioactive waste in a cement/lime mixture

    International Nuclear Information System (INIS)

    Zhou, H.; Colombo, P.

    1984-01-01

    The suitability of a cement/lime mixture for use as a solidification agent for different types of wastes was investigated. This work includes studies directed towards determining the wasted/binder compositional field over which successful solidification occurs with various wastes and the measurement of some of the waste from properties relevant to evaluating the potential for the release of radionuclides to the environment. In this study, four types of low-level radioactive wastes were simulated for incorporation into a cement/lime mixture. These were boric acid waste, sodium sulfate wastes, aion exchange resins and incinerator ash. 7 references, 3 figures, 2 tables

  15. Some techniques for the solidification of radioactive wastes in concrete

    International Nuclear Information System (INIS)

    Colombo, P.; Neilson, R. Jr.

    1976-06-01

    Some techniques for the solidification of radioactive wastes in concrete are discussed. The sources, storage, volume reduction, and solidification of liquid wastes at Brookhaven National Laboratory (BNL) using the cement-vermiculite process is described. Solid waste treatment, shipping containers, and off-site shipments of solid wastes at BNL are also considered. The properties of low-heat-generating, high-level wastes, simulating those in storage at the Savannah River Plant (SRP), solidified in concrete were determined. Polymer impregnation was found to further decrease the leachability and improve the durability of these concrete waste forms

  16. Utilization of coal fly ash in solidification of liquid radioactive waste from research reactor.

    Science.gov (United States)

    Osmanlioglu, Ahmet Erdal

    2014-05-01

    In this study, the potential utilization of fly ash was investigated as an additive in solidification process of radioactive waste sludge from research reactor. Coal formations include various percentages of natural radioactive elements; therefore, coal fly ash includes various levels of radioactivity. For this reason, fly ashes have to be evaluated for potential environmental implications in case of further usage in any construction material. But for use in solidification of radioactive sludge, the radiological effects of fly ash are in the range of radioactive waste management limits. The results show that fly ash has a strong fixing capacity for radioactive isotopes. Specimens with addition of 5-15% fly ash to concrete was observed to be sufficient to achieve the target compressive strength of 20 MPa required for near-surface disposal. An optimum mixture comprising 15% fly ash, 35% cement, and 50% radioactive waste sludge could provide the solidification required for long-term storage and disposal. The codisposal of radioactive fly ash with radioactive sludge by solidification decreases the usage of cement in solidification process. By this method, radioactive fly ash can become a valuable additive instead of industrial waste. This study supports the utilization of fly ash in industry and the solidification of radioactive waste in the nuclear industry.

  17. Electric melting furnace for waste solidification

    International Nuclear Information System (INIS)

    Masaki, Toshio.

    1990-01-01

    To avoid electric troubles or reduction of waste processing performance even when platinum group elements are contained in wastes to be applied with glass solidification. For this purpose, a side electrode is disposed to the side wall of a melting vessel and a central electrode serving as a counter electrode is disposed about at the center inside the melting vessel. With such a constitution, if conductive materials are deposited at the bottom of the furnace or the bottom of the melting vessel, heating currents flow selectively between the side electrode and the central electrode. Accordingly, no electric currents flow through the conductive deposits thereby enabling to prevent abnormal heating in the bottom of the furnace. Further, heat generated by electric supply between the side electrode and the central electrode is supplied efficiently to raw material on the surface of the molten glass liquid to improve the processing performance. Further, disposition of the bottom electrode at the bottom of the furnace enables current supply between the central electrode and the bottom electrode to facilitate the temperature control for the molten glass in the furnace than in the conventional structure. (I.S.)

  18. Centralized cement solidification technique for low-level radioactive wastes

    International Nuclear Information System (INIS)

    Matsuda, Masami; Nishi, Takashi; Izumida, Tatsuo; Tsuchiya, Hiroyuki.

    1996-01-01

    A centralized cement solidification system has been developed to enable a single facility to solidify such low-level radioactive wastes as liquid waste, spent ion exchange resin, incineration ash, and miscellaneous solid wastes. Since the system uses newly developed high-performance cement, waste loading is raised and deterioration of waste forms after land burial prevented. This paper describes the centralized cement solidification system and the features of the high-performance cement. Results of full-scale pilot plant tests are also shown from the viewpoint of industrial applicability. (author)

  19. Modified sulfur cement solidification of low-level wastes

    Energy Technology Data Exchange (ETDEWEB)

    1985-10-01

    This topical report describes the results of an investigation on the solidification of low-level radioactive wastes in modified sulfur cement. The work was performed as part of the Waste Form Evaluation Program, sponsored by the US Department of Energy's Low-Level Waste Management Program. Modified sulfur cement is a thermoplastic material developed by the US Bureau of Mines. Processing of waste and binder was accomplished by means of both a single-screw extruder and a dual-action mixing vessel. Waste types selected for this study included those resulting from advanced volume reduction technologies (dry evaporator concentrate salts and incinerator ash) and those which remain problematic for solidification using contemporary agents (ion exchange resins). Process development studies were conducted to ascertain optimal process control parameters for successful solidification. Maximum waste loadings were determined for each waste type and method of processing. Property evaluation testing was carried out on laboratory scale specimens in order to compare with waste form performance for other potential matrix materials. Waste form property testing included compressive strength, water immersion, thermal cycling and radionuclide leachability. Recommended waste loadings of 40 wt. % sodium sulfate and boric acid salts and 43 wt. % incinerator ash, which are based on processing and performance considerations, are reported. Solidification efficiencies for these waste types represent significant improvements over those of hydraulic cements. Due to poor waste form performance, incorporation of ion exchange resin waste in modified sulfur cement is not recommended.

  20. Modified sulfur cement solidification of low-level wastes

    International Nuclear Information System (INIS)

    1985-10-01

    This topical report describes the results of an investigation on the solidification of low-level radioactive wastes in modified sulfur cement. The work was performed as part of the Waste Form Evaluation Program, sponsored by the US Department of Energy's Low-Level Waste Management Program. Modified sulfur cement is a thermoplastic material developed by the US Bureau of Mines. Processing of waste and binder was accomplished by means of both a single-screw extruder and a dual-action mixing vessel. Waste types selected for this study included those resulting from advanced volume reduction technologies (dry evaporator concentrate salts and incinerator ash) and those which remain problematic for solidification using contemporary agents (ion exchange resins). Process development studies were conducted to ascertain optimal process control parameters for successful solidification. Maximum waste loadings were determined for each waste type and method of processing. Property evaluation testing was carried out on laboratory scale specimens in order to compare with waste form performance for other potential matrix materials. Waste form property testing included compressive strength, water immersion, thermal cycling and radionuclide leachability. Recommended waste loadings of 40 wt. % sodium sulfate and boric acid salts and 43 wt. % incinerator ash, which are based on processing and performance considerations, are reported. Solidification efficiencies for these waste types represent significant improvements over those of hydraulic cements. Due to poor waste form performance, incorporation of ion exchange resin waste in modified sulfur cement is not recommended

  1. Underground nuclear waste storage backed

    International Nuclear Information System (INIS)

    Long, J.R.

    1978-01-01

    Latest to hold hearings on nuclear waste disposal problems is the Senate Commerce Subcommittee on Science, Technology and Space. Testimonies by John M. Deutch, Rustum Roy (presenting results of National Research Council panel on waste solidification), and Darleane C. Hoffman are summarized

  2. UJV line for research into radioactive wastes solidification

    International Nuclear Information System (INIS)

    Neumann, L.; Feist, I.; Kepak, F.; Nachmilner, L.; Napravnik, J.; Novak, M.; Pecak, V.; Vojtech, O.

    1985-01-01

    An experimental line with a capacity of 0.01 m 3 /h was developed and built for research of the solidification of liquid radioactive wastes at the Nuclear Research Institute. The line allows the research and pilot plant testing of processes based on vitrification but also on other procedures including calcination. It consists of a horizontal calciner, a resistance melting unit, a homogenization device for research into cementation of the calcinate, and equipment for the disposal of gaseous emissions. The facility is provided with a control console which allows remote control and the control of all basic operating parameters. The design of the line allows its eventual completion with other equipment. (Z.M.)

  3. Process control of Low and Intermediate-level radioactive wastes solidification

    International Nuclear Information System (INIS)

    1993-01-01

    Safety guidelines issued by the Spanish Council of Nuclear Safety (CSN) with basic criteria which must be adopted for the control of the Process for wastes solidification, establishing, in addition, a series of protocols and basic contents to assist the elaboration of Process Control Programs

  4. Solidification of ion exchange resin wastes in hydraulic cement

    International Nuclear Information System (INIS)

    Neilson, R.M. Jr.; Kalb, P.; Fuhrmann, M.; Colombo, P.

    1982-01-01

    Work has been conducted to investigate the solidification of ion exchange resin wastes with portland cements. These efforts have been directed toward the development of acceptable formulations for the solidification of ion exchange resin wastes and the characterization of the resultant waste forms. This paper describes formulation development work and defines acceptable formulations in terms of ternary phase compositional diagrams. The effects of cement type, resin type, resin loading, waste/cement ratio and water/cement ratio are described. The leachability of unsolidified and solidified resin waste forms and its relationship to full-scale waste form behavior is discussed. Gamma irradiation was found to improve waste form integrity, apparently as a result of increased resin crosslinking. Modifications to improve waste form integrity are described. 3 tables

  5. Solidification of Simulated Liquid Effluents Originating From Sodium-Bearing Waste at the Idaho Nuclear Technology and Engineering Center, FY-03 Report

    Energy Technology Data Exchange (ETDEWEB)

    S. V. Raman; A. K. Herbst; B. A. Scholes; S. H. Hinckley; R. D. Colby

    2003-09-01

    In this report, the mechanism and methods of fixation of acidic waste effluents in grout form are explored. From the variations in the pH as a function of total solids addition to acidic waste effluent solutions, the stages of gellation, liquefaction, slurry formation and grout development are quantitatively revealed. Experimental results indicate the completion of these reaction steps to be significant for elimination of bleed liquid and for setting of the grout to a dimensionally stable and hardened solid within a reasonable period of about twenty eight days that is often observed in the cement and concrete industry. The reactions also suggest increases in the waste loading in the direction of decreasing acid molarity. Consequently, 1.0 molar SBW-180 waste is contained in higher quantity than the 2.8 molar SBW-189, given the same grout formulation for both effluents. The variations in the formulations involving components of slag, cement, waste and neutralizing agent are represented in the form of a ternary formulation map. The map in turn graphically reveals the relations among the various formulations and grout properties, and is useful in predicting the potential directions of waste loading in grouts with suitable properties such as slurry viscosity, Vicat hardness, and mechanical strength. A uniform formulation for the fixation of both SBW-180 and SBW-189 has emerged from the development of the formulation map. The boundaries for the processing regime on this map are 100 wt% cement to 50 wt% cement / 50 wt% slag, with waste loadings ranging from 55 wt% to 68 wt%. Within these compositional bounds all the three waste streams SBW-180, SBW-189 and Scrub solution are amenable to solidification. A large cost advantage is envisaged to stem from savings in labor, processing time, and processing methodology by adopting a uniform formulation concept for fixation of compositionally diverse waste streams. The experimental efforts contained in this report constitute the

  6. Nuclear fuel cycle and waste management in France

    International Nuclear Information System (INIS)

    Sousselier, Yves.

    1981-05-01

    After a short description of the nuclear fuel cycle mining, milling, enrichment and reprocessing, radioactive waste management in France is exposed. The different types of radioactive wastes are examined. Storage, solidification and safe disposal of these wastes are described

  7. Stabilization and Solidification of Nitric Acid Effluent Waste at Y-12

    Energy Technology Data Exchange (ETDEWEB)

    Singh, Dileep [Argonne National Lab. (ANL), Argonne, IL (United States); Lorenzo-Martin, Cinta [Argonne National Lab. (ANL), Argonne, IL (United States)

    2016-12-16

    Consolidated Nuclear Security, LLC (CNS) at the Y-12 plant is investigating approaches for the treatment (stabilization and solidification) of a nitric acid waste effluent that contains uranium. Because the pH of the waste stream is 1-2, it is a difficult waste stream to treat and stabilize by a standard cement-based process. Alternative waste forms are being considered. In this regard, Ceramicrete technology, developed at Argonne National Laboratory, is being explored as an option to solidify and stabilize the nitric acid effluent wastes.

  8. Solidification of highly active liquid waste

    International Nuclear Information System (INIS)

    Morris, J.B.

    1985-03-01

    This document contains the annual progress reports on the following subjects: Joule ceramic melter; microwave vitrification; glass technology; identification, evaluation and review of potential alternative solidification processes; rotary kiln calcination; alternative glass feedstocks; volatile ruthenium trapping by solid adsorbents; irrigated baffle column dust scrubber. (author)

  9. Improved cement solidification of low and intermediate level radioactive wastes

    International Nuclear Information System (INIS)

    1993-01-01

    Cementation was the first and is still the most widely applied technique for the conditioning of low and intermediate level radioactive wastes. Compared with other solidification techniques, cementation is relatively simple and inexpensive. However, the quality of the final cemented waste forms depends very much on the composition of the waste and the type of cement used. Different kinds of cement are used for different kinds of waste and the compatibility of a specific waste with a specific cement type should always be carefully evaluated. Cementation technology is continuously being developed in order to improve the characteristics of cemented waste in accordance with the increasing requirements for quality of the final solidified waste. Various kinds of additives and chemicals are used to improve the cemented waste forms in order to meet all safety requirements. This report is meant mainly for engineers and designers, to provide an explanation of the chemistry of cementation systems and to facilitate the choice of solidification agents and processing equipment. It reviews recent developments in cementation technology for improving the quality of cemented waste forms and provides a brief description of the various cement solidification processes in use. Refs, figs and tabs

  10. Solidification of acidic liquid waste from 99Mo isotope production

    International Nuclear Information System (INIS)

    Parsons, G.J.

    2001-01-01

    Full text: The production of the radioisotope molybdenum-99 by the fission process began at ANSTO in the late 1960's. Molybdenum-99, with a half life of 66 hours, decays by beta emission to produce technetium-99m, a metastable isotope. Technetium-99m is the most widely used medical radioisotope due to its near ideal properties, particularly the radioactive half life of only 6 hours. ANSTO has been producing generators for around 30 years for distribution to hospitals and nuclear medicine centres. These generators produce technetium-99m for medical use by decay of the contained molybdenum-99. To produce molybdenum-99, uranium dioxide pellets enriched to 2.2% 235 U are irradiated in ANSTO's HIFAR reactor for about one week. The irradiated pellets are subsequently dissolved in nitric acid to allow the recovery of the molybdenum. An acidic intermediate level liquid waste results from this processing. A primary waste results from the raw leach solution (after removal of the molybdenum onto a packed alumina column) and a weaker secondary waste is produced from a series of column washing steps. The waste solution contains uranium, the majority of the other fission products and low levels of ammonia in a nitric acid solution. This liquid waste had been accumulating and stored in specially designed shielded tanks in a storage facility. A process has been developed at ANSTO to convert this intermediate level liquid waste into a crystalline solid form of considerably less volume and mass, for improved storage. The operation comprises three processing steps. The lower strength secondary waste solution first requires concentration, with the removal of water and some acid into a condensate. The condensate is chemically neutralised and treated through the conventional water treatment plant. Concentrated solution is then treated in a batch chemical process to reduce the low levels of ammonia to very low levels. The final evaporation process removes further water and acid and

  11. Alternative waste management concept for medium and low level wastes by in-situ solidification

    International Nuclear Information System (INIS)

    Kraemer, R.

    1982-01-01

    Since 1976, a German R and D project has been carried out to find an alternative concept for the treatment and disposal of MLW and LLW arising mainly in the planned German reprocessing plant and other nuclear facilities (LWR, fuel fabrication, R and D establishments). The main feature of this concept is an in-situ solidification of preconditioned waste granules in large salt caverns located in the deep geological underground, thus avoiding such non-radioactive ballast as lost concrete shielding and container material. (orig./RW)

  12. 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.)

  13. Alternative method of solidification for low-level class a radioactive waste

    International Nuclear Information System (INIS)

    Mayo, K.S.

    1988-01-01

    New solidification media have been developed that exhibit excellent spatial efficiency over the entire range of virtually all Class A liquid wastes. These new media are being used to incorporate from 41 to 48 gallons of liquid radioactive waste in a 55-gallon drum. To date, wastes processing at nuclear power plants and facilities include oils, evaporator bottoms, sludges, and ion-exchanges resins as well as combinations of these waste streams. This paper comparatively discusses the performance of solidification agents known as AQUASET TM and PETROSET TM with other currently available agents. It presents key advantages of using the AQUASET and PETROSET media over other media. These advantages include improvements in packaging efficiency, leachability, and repeatability

  14. INEL studies concerning solidification of low-level waste in cement

    International Nuclear Information System (INIS)

    Mandler, J.W.

    1989-01-01

    The Idaho National Engineering Laboratory (INEL) has performed numerous studies addressing issues concerning the solidification of low-level radioactive waste in cement. These studies have been performed for both the Nuclear Regulatory Commission (NRC) and the Department of Energy (DOE). This short presentation will only outline the major topics addressed in some of these studies, present a few conclusions, and identify some of the technical concerns we have. More details of the work and pertinent results will be given in the Working Group sessions. The topics that have been addressed at the INEL which are relevant to this Workshop include (1) solidification of ion-exchange resins and evaporator waste in cement at commercial nuclear power plants, (2) leachability and compressive strength of power plant waste solidified in cement, (3) suggested guidelines for preparation of a solid waste process control program (PCP), (4) cement solidification of EPICOR-II resin wastes, and (5) performance testing of cement-solidified EPICOR-II resin wastes

  15. Study of plastic solidification process on solid radioactive waste treatment

    International Nuclear Information System (INIS)

    Jing Weiguan; Zhang Yinsheng; Qian Wenju

    1994-01-01

    Comparisons between the plastic solidification conditions of incinerated ash and waste cation resin by using thermosetting plastic polyvinyl chloride (PVC), polystyrene (PS) and polyethylene (PE), and identified physico-chemical properties and irradiation resistance of solidified products were presented. These solidified products have passed through different tests as compression strength, leachability, durability, stability, permeability and irradiation resistance (10 6 Gy) etc. The result showed that the solidified products possessed stable properties and met the storage requirement. The waste tube of radioimmunoassay, being used as solidification medium to contain incinerated ash, had good mechanical properties and satisfactory volume reduction. This process may develop a new way for disposal solid radioactive waste by means of re-using waste

  16. Nuclear waste

    International Nuclear Information System (INIS)

    1992-05-01

    The Nuclear Waste Policy Act of 1982, as amended in 1987, directed the Secretary of Energy to, among other things, investigate Yucca Mountain, Nevada, as a potential site for permanently disposing of highly radioactive wastes in an underground repository. In April 1991, the authors testified on Yucca Mountain project expenditures before your Subcommittee. Because of the significance of the authors findings regrading DOE's program management and expenditures, you asked the authors to continue reviewing program expenditures in depth. As agreed with your office, the authors reviewed the expenditures of project funds made available to the Department of Energy's (DOE) Lawrence Livermore National Laboratory, which is the lead project contractor for developing a nuclear waste package that wold be used for disposing of nuclear waste at Yucca Mountain. This report discusses the laboratory's use of nuclear waste funds to support independent research projects and to manage Yucca Mountain project activities. It also discusses the laboratory's project contracting practices

  17. Nuclear waste

    International Nuclear Information System (INIS)

    Pligt, J. van der

    1989-01-01

    This chapter present a brief overview of the current situation of siting radioactive wastes. This is followed by an overview of various psychological approaches attempting to analyse public reactions to nuclear facilities. It will be argued that public reactions to nuclear waste factilities must be seen in the context of more general attitudes toward nuclear energy. The latter are not only based upon perceptions of the health and environmental risks but are built on values, and sets of attributes which need not be similar to the representations o the experts and policy-makers. The issue of siting nuclear waste facilities is also embedded in a wider moral and political domain. This is illustrated by the importance of equity issues in siting radioactive wastes. In the last section, the implications of the present line of argument for risk communication and public participation in decisions about siting radioactive wastes will be briefly discussed. (author). 49 refs

  18. Solidification process for toxic and hazardous wastes. Second part: Cement solidification matrices; Inertizzazione di rifiuti tossici e nocivi (RTN). Parte seconda: Inertizzazione in matrici cementizie

    Energy Technology Data Exchange (ETDEWEB)

    Donato, A; Arcuri, L; Dotti, M; Pace, A; Pietrelli, L; Ricci, G [ENEA - Dipartimento Ciclo del Combustibile, Centro Ricerche Energia, Casaccia (Italy); Basta, M; Cali, V; Pagliai, V [ENEA - Dipartimento Ciclo del Combustibile, Centro Ricerche Energia, Saluggia (Italy)

    1989-05-15

    This paper reports the second part of a general study carried out at the Nuclear Fuel Division aiming at verifying the possible application of the radioactive waste solidification processes to industrial hazardous wastes (RTN). The cement solidification of several RTN types has been taken into consideration, both from the technical and from the economic point of view. After a short examination of the Italian juridical and economical situation in the field, which demonstrates the need of the RTN solidification, the origin and characteristics of the RTN considered in the study and directly provided by the producing industries are reviewed. The laboratory experimental results of the cementation of RTN produced by gold manufacturing industries and by galvanic industries are reported. The cementation process can be considered a very effective mean for reducing both the RTN management costs and the environmental impact of RTN disposal. (author)

  19. Nuclear waste

    International Nuclear Information System (INIS)

    Anon.

    1996-01-01

    The NEA Nuclear Waste Bulletin has been prepared by the Radiation Protection and Waste Management Division of the OECD Nuclear Energy Agency to provide a means of communication amongst the various technical and policy groups within the waste management community. In particular, it is intended to provide timely and concise information on radioactive waste management activities, policies and programmes in Member countries and at the NEA. It is also intended that the Bulletin assists in the communication of recent developments in a variety of areas contributing to the development of acceptable technology for the management and disposal of nuclear waste (e.g., performance assessment, in-situ investigations, repository engineering, scientific data bases, regulatory developments, etc)

  20. Solidification of commercial and defense low-level radioactive waste in polyethylene

    International Nuclear Information System (INIS)

    Franz, E.M.; Heiser, L.H.; Colombo, P.

    1987-08-01

    A process was developed for the solidification of salt wastes, incinerator ash and ion-exchange resins in polyethylene. Of the salt wastes, sodium sulfate and boric acid are representative of the wastes produced at commercial nuclear facilities while sodium nitrate in a typical high-volume waste generated at defense-related facilities. Ease of processibility and high loading efficiencies were obtained through the use of low-density polyethylene with melt indices ranging from 2.0 to 55.0 g/minute. The process utilized a commercially available single-screw extruder to incorporate the wastes into the polyethylene at about 120 0 C to produce a homogeneous mixture. Although present studies utilize dry wastes, wet wastes can also be processed using vented extruders of the type used commercially for the bitumen solidification process. Tests were performed on the waste forms to determine leachability and mechanical properties. To confirm the compatibility of polyethylene and nitrate salt waste at elevated temperatures, the self-ignition temperatures were measured and a differential scanning calorimeter was used to characterize the thermal behavior of oxidizing compounds contained in the simulated waste, as well as the real Savannah River Plant waste. No exothermic reactions were observed over the temperature range studied from 50 0 C to 400 0 C. 18 refs., 7 figs., 8 tabs

  1. Glass-solidification method for high level radioactive liquid waste

    International Nuclear Information System (INIS)

    Kawamura, Kazuhiro; Kometani, Masayuki; Sasage, Ken-ichi.

    1996-01-01

    High level liquid wastes are removed with precipitates mainly comprising Mo and Zr, thereafter, the high level liquid wastes are mixed with a glass raw material comprising a composition having a B 2 O 3 /SiO 2 ratio of not less than 0.41, a ZnO/Li 2 O ratio of not less than 1.00, and an Al 2 O 3 /Li 2 O ratio of not less than 2.58, and they are melted and solidified into glass-solidification products. The liquid waste content in the glass-solidification products can be increased up to about 45% by using the glass raw material having such a predetermined composition. In addition, deposition of a yellow phase does not occur, and a leaching rate identical with that in a conventional case can be maintained. (T.M.)

  2. Nuclear wastes

    International Nuclear Information System (INIS)

    2002-01-01

    This scientific document presents an introduction to the nuclear wastes problems, the separation process and the transmutation, the political and technical aspects of the storage, the radioprotection standards and the biological effects. (A.L.B.)

  3. Cement solidification of spent ion exchange resins produced by the nuclear industry

    International Nuclear Information System (INIS)

    Jaouen, C.; Vigreux, B.

    1988-01-01

    Cement solidification technology has been applied to spent ion exchange resins for many years in countries throughout the world (at reactors, research centers and spent fuel reprocessing plants). Changing specifications for storage of radioactive waste have, however, confronted the operators of such facilities with a number of problems. Problems related both to the cement solidification process (water/cement/resin interactions and chemical interactions) and to its utilization (mixing, process control, variable feed composition, etc.) have often led waste producers to prefer other, polymer-based processes, which are very expensive and virtually incompatible with water. This paper discusses research on cement solidification of ion exchange resins since 1983 and the development of application technologies adapted to nuclear service conditions and stringent finished product quality requirements

  4. Solidification of low-level radioactive wastes in masonry cement

    International Nuclear Information System (INIS)

    Zhou, H.; Colombo, P.

    1987-03-01

    Portland cements are widely used as solidification agents for low-level radioactive wastes. However, it is known that boric acid wastes, as generated at pressurized water reactors (PWR's) are difficult to solidify using ordinary portland cements. Waste containing as little as 5 wt % boric acid inhibits the curing of the cement. For this purpose, the suitability of masonry cement was investigated. Masonry cement, in the US consists of 50 wt % slaked lime (CaOH 2 ) and 50 wt % of portland type I cement. Addition of boric acid in molar concentrations equal to or less than the molar concentration of the alkali in the cement eliminates any inhibiting effects. Accordingly, 15 wt % boric acid can be satisfactorily incorporated into masonry cement. The suitability of masonry cement for the solidification of sodium sulfate wastes produced at boiling water reactors (BWR's) was also investigated. It was observed that although sodium sulfate - masonry cement waste forms containing as much as 40 wt % Na 2 SO 4 can be prepared, waste forms with more than 7 wt % sodium sulfate undergo catastrophic failure when exposed to an aqueous environment. It was determined by x-ray diffraction that in the presence of water, the sulfate reacts with hydrated calcium aluminate to form calcium aluminum sulfate hydrate (ettringite). This reaction involves a volume increase resulting in failure of the waste form. Formulation data were identified to maximize volumetric efficiency for the solidification of boric acid and sodium sulfate wastes. Measurement of some of the waste form properties relevant to evaluating the potential for the release of radionuclides to the environment included leachability, compression strengths and chemical interactions between the waste components and masonry cement. 15 refs., 19 figs., 9 tabs

  5. Polymer solidification of mixed wastes at the Rocky Flats Plant

    International Nuclear Information System (INIS)

    Faucette, A.M.; Logsdon, B.W.; Lucerna, J.J.; Yudnich, R.J.

    1994-01-01

    The Rocky Flats Plant is pursuing polymer solidification as a viable treatment option for several mixed waste streams that are subject to land disposal restrictions within the Resource Conservation and Recovery Act provisions. Tests completed to date using both surrogate and actual wastes indicate that polyethylene microencapsulation is a viable treatment option for several mixed wastes at the Rocky Flats Plant, including nitrate salts, sludges, and secondary wastes such as ash. Treatability studies conducted on actual salt waste demonstrated that the process is capable of producing waste forms that comply with all applicable regulatory criteria, including the Toxicity Characteristic Leaching Procedure. Tests have also been conducted to evaluate the feasibility of macroencapsulating certain debris wastes in polymers. Several methods and plastics have been tested for macroencapsulation, including post-consumer recycle and regrind polyethylene

  6. Mobile concrete solidification systems for power reactor waste

    International Nuclear Information System (INIS)

    Tchemitcheff, E.; Bordas, Y.

    1990-01-01

    In late 1988 SGN received an order from Electricite de France (EDF) for the construction of a mobile concrete solidification system to process secondary system resins generated by the P'4 and N4 series PWR power plants in France. This order was placed in view of SGN's experience with low- and medium-level radioactive waste treatment and conditioning over a period of almost 20 years. In addition to the construction of fixed waste processing facilities using more conventional technologies, SGN has been involved in application of the mobile system concept to the bituminization process in the United States, which led to the construction and commissioning of two transportable systems in collaboration with its American licensee US Ecology. It has also conducted large-scale R ampersand D on LLW/MLW concrete solidification, particularly for ion exchange resins. 5 figs

  7. Solidification of radioactive wastes with inorganic binders (literature survey)

    International Nuclear Information System (INIS)

    Rudolph, G.; Koester, R.

    A survey is provided on solidification of radioactive waste solutions, sludges and tritium waste water through cement and other inorganic binders. A general survey of the possibilities described in the literature is followed by a somewhat more detailed description of the work carried on at four research establishments in the United States, Oak Ridge National Laboratory, Savannah River Laboratory, Brookhaven National Laboratory, and Atlantic Richfield Hanford Company, supplemented by personal information. Additional sections describe the experiences with various types of cement and the possibilities for improvement of solidification products through preliminary fixation of the toxic nuclides (transformation into insoluble products or absorption); there is a further possibility of post-treatment through polymer impregnation. Finally, definition and determination of leachability are provided and some results compiled. 74 references, 7 figures, 5 tables

  8. Nuclear waste

    International Nuclear Information System (INIS)

    1990-01-01

    Each year, nuclear power plants, businesses, hospitals, and universities generate more than 1 million cubic feet of hardware, rags, paper, liquid waste, and protective clothing that have been contaminated with radioactivity. While most of this waste has been disposed of in facilities in Nevada, South Carolina, and Washington state, recent legislation made the states responsible - either individually, or through groups of states called compacts - for developing new disposal facilities. This paper discusses the states' progress and problems in meeting facility development milestones in the law, federal and state efforts to resolve issues related to mixed waste (low-level waste that also contains hazardous chemicals) and waste with very low levels of radioactivity, and the Department of Energy's progress in discharging the federal government's responsibility under the law to manage the most hazardous low-level waste

  9. Solidification of radioactive wastes with thermosetting resin

    International Nuclear Information System (INIS)

    Hayashi, M.; Kobayashi, K.; Okamoto, O.; Kagawa, T.; Wakamatsu, K.; Irie, H.; Matsuura, H.; Yasumura, K.; Nakayama, Y.

    1982-01-01

    Dried simulated radioactive wastes were solidified with thermosetting resin and their properties were investigated with laboratory scale and real scale products through extensive testings, such as mechanical resistance, resistance to leaching and swelling in water, radiation resistance, fire resistance and resistance to temperature cycling. The typical results were as follows: over 600 kg/cm 2 of compressive strength, diffusion constant of approx. 10 - 5 cm 2 /day for 137 Cs leaching from solidified waste products, no significant change was found for up to 5 x 10 8 RAD irradiation, and damages were limited to the surface of the products after the thermal test and dropping impact test. 7 figures, 4 tables

  10. Nuclear waste

    International Nuclear Information System (INIS)

    1988-01-01

    The Department of Energy has proposed a draft plan for investigating the Yucca Mountain, Nevada, site to determine if it suitable for a waste repository. This fact sheet provides information on the status of DOE's and the Nuclear Regulatory Commission's efforts to streamline what NRC expects will be the largest and most complex nuclear-licensing proceeding in history, including the development of an electronic information management system called the Licensing Support System

  11. Pilot plant experience on high-level waste solidification and design of the engineering prototype VERA

    Energy Technology Data Exchange (ETDEWEB)

    Guber, W; Diefenbacher, W; Hild, W; Krause, H; Schneider, E; Schubert, G

    1972-11-01

    In the present paper the solidification process for highly active waste solutions as developed in the Karlsruhe Nuclear Research Center is presented. Its principal steps are: denitration, calcination in a spray calciner operated with superheated steam, melting of the calcine with appropriate additives to borosilicate glass in an induction-heated melting furnace. The operational experiences gained so far in the inactive 1:1 pilot plant are reported. Furthermore, a description is given of the projected multi-purpose experimental facility VERA 2 which is provided for processing the highly active waste solutions from the first German reprocessing plant WAK.

  12. Solidification processing method for radioactive waste

    International Nuclear Information System (INIS)

    Hiraki, Akimitsu; Tanaka, Keiji; Heta, Katsutoshi.

    1991-01-01

    The pressure in a vessel containing radioactive wastes is previously reduced and cement mortar prepared by kneading cement, sand and kneading agent with water is poured under shaking substantially to the upper end of the vessel. After the lowering of the mortar level due to the deforming has been terminated, the pressure is increased gradually. Then, the cement mortar is further poured substantially to the upper end of the vessel again. With such a two step pouring method, spaces other than the radioactive wastes in the vessel can be filled substantially completely with the cement mortar. Accordingly, it is possible to avoid the problem in view of the strength due to the formation of gaps at the inside of the vessel, or leaching of radioactive materials due to the intrusion of water into the gaps. Further, if washing water is reutilized as water for kneading or washing after the precipitation of the solid contents, the amount of the secondary wastes generated can be reduced. (T.M.)

  13. Nuclear waste

    International Nuclear Information System (INIS)

    Anon.

    1983-01-01

    The Koeberg nuclear power station, planned to come on stream in 1984, is expected to save South Africa some six million t/annum of coal, and to contribute some 10 per cent of the country's electricity requirements. The use of nuclear energy will provide for growing national energy needs, and reduce high coal transport costs for power generation at the coast. In the long term, however, it gives rise to the controversial question of nuclear waste storage. The Atomic Energy Corporation of South Africa Ltd (AEC) recently announced the purchase of a site in Namaqualand (NW Cape) for the storage of low-level radioactive waste. The Nuclear Development Corporation of South Africa (Pty) Ltd, (NUCOR) will develop and operate the site. The South African Mining and Engineering Journal interviewed Dr P.D. Toens, manager of the Geology Department and Mr P.E. Moore, project engineer, on the subject of nuclear waste, the reasons behind Nucor's choice of site and the storage method

  14. Nuclear waste

    International Nuclear Information System (INIS)

    1989-01-01

    This paper reviews the Department of Energy's management of underground single-shell waste storage tanks at its Hanford, Washington, site. The tanks contain highly radioactive and nonradioactive hazardous liquid and solid wastes from nuclear materials production. Hundreds of thousands of gallons of these wastes have leaked, contaminating the soil, and a small amount of leaked waste has reached the groundwater. DOE does not collect sufficient data to adequately trace the migration of the leaks through the soil, and studies predicting the eventual environmental impact of tank leaks do not provide convincing support for DOE's conclusion that the impact will be low or nonexistent. DOE can do more to minimize the environmental risks associated with leaks. To reduce the environmental impact of past leaks, DOE may be able to install better ground covering over the tanks to reduce the volume of precipitation that drains through the soil and carries contaminants toward groundwater

  15. Decontamination impacts on solidification and waste disposal

    International Nuclear Information System (INIS)

    Kempf, C.R.; Soo, P.

    1988-01-01

    Research to determine chemical and physical conditions which could lead to thermal excursions, gas generation, and/or general degradation of decontamination-reagent-loaded resins has shown that IRN-78, IONAC A-365, and IRN-77 organic ion exchange resin moisture contents vary significantly depending on the counter ion ''loading.'' The extent/vigor of the reaction is very highly dependent on the degree of dewatering of the resins and on the method of solution addition. The heat generation may be due, in part, to the heat of neutralization. In studies of the long-term compatibility effects of decontamination waste resins in contact with waste package container materials in the presence of decontamination reagents, radiolysis products and gamma irradiation, it has been found that the corrosion of carbon steel and austenitic stainless steel in mixed bed resins is enhanced by gamma irradiation. However, cracking in high density polyethylene is essentially eliminated because of the rapid removal of oxygen from the environment by gamma-induced oxidation of the large resin mass. 13 refs., 10 figs., 3 tabs

  16. Device for solidification of gaseous wastes

    International Nuclear Information System (INIS)

    Shimada, Masayuki; Kamei, Hisashi.

    1979-01-01

    Purpose: To provide the subject device wherein gaseous wastes such as krypton 85 and the like are ionized and accelerated to be injected into solid targets and stored therein, thereby removing the redischarge of gas and making it possible to treat a large quantity of said gas. Constitution: Krypton gas is ionized and accelerated to high energy by an accelerator, and then introduced into an ion injection chamber. In the ion injection chamber a band-shaped target is delivered from a first take-up roll, and krypton ions are injected to said target. Thereafter, other band-shaped target delivered from a second take-up roll is brought into contact with the target in which krypton ions have been injected, and both targets are taken up together while compressing these targets. In this way, even when injected energy is small, the injected gas is not redischarged and can be continuously treated. (Kamimura, M.)

  17. Nuclear waste

    International Nuclear Information System (INIS)

    1990-06-01

    DOE estimates that disposing of radioactive waste from civilian nuclear power plants and its defense-related nuclear facilities could eventually end up costing $32 billion. To pay for this, DOE collects fees from utilities on electricity generated by nuclear power plants and makes payments from its defense appropriation. This report states that unless careful attention is given to its financial condition, the nuclear waste program is susceptible to future shortfalls. Without a fee increase, the civilian-waste part of the program may already be underfunded by at least $2.4 billion (in discounted 1988 dollars). Also, DOE has not paid its share of cost-about $480 million-nor has it disclosed this liability in its financial records. Indexing the civilian fee to the inflation rate would address one major cost uncertainty. However, while DOE intends to do this at an appropriate time, it does not use a realistic rate of inflation as its most probable scenario in assessing whether that time has arrived

  18. Nuclear waste

    International Nuclear Information System (INIS)

    1988-01-01

    As required by the Nuclear Waste Policy Act of 1982, the Department of Energy is to annually determine whether the waste disposal fee will produce sufficient revenues to offset the total estimated costs of the waste disposal program. In its June 1987 assessment, DOE recommended that the fee remain unchanged even though its analysis showed that at an inflation rate of 4 percent the current fee would result in end-of-program deficits ranging from $21 billion to $76 billion in 2085. The 1988 assessment calls for reduced total costs because of program changes. Thus, DOE may be able to begin using a realistic inflation rate in determining fee adequacy in 1988 without proposing a major fee increase

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-06-01

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

  20. Solidifications/stabilization treatability study of a mixed waste sludge

    International Nuclear Information System (INIS)

    Spence, R.D.; Stine, E.F.

    1996-01-01

    The Department of Energy Oak Ridge Operations Office signed a Federal Facility Compliance Agreement with the US Environmental Protection Agency Region IV regarding mixed wastes from the Oak Ridge Reservation (ORR) subject to the land disposal restriction provisions of the Resource Conservation and Recovery Act (RCRA). This agreement required treatability studies of solidification/stabilization (S/S) on mixed wastes from the ORR. This paper reports the results of the cementitious S/S studies conducted on a waste water treatment sludge generated from biodenitrification and heavy metals precipitation. For the cementitious waste forms, the additives tested were Portland cement, ground granulated blast furnace slag, Class F fly ash, and perlite. The properties measured on the treated waste were density, free-standing liquid, unconfined compressive strength, and TCLP performance. Spiking up to 10,000, 10,000, and 4,400 mg/kg of nickel, lead, and cadmium, respectively, was conducted to test waste composition variability and the stabilization limitations of the binding agents. The results indicated that nickel, lead and cadmium were stabilized fairly well in the high pH hydroxide-carbonate- ''bug bones'' sludge, but also clearly confirmed the established stabilization potential of cementitious S/S for these RCRA metals

  1. Recent advances in cement solidification of radioactive wastes

    International Nuclear Information System (INIS)

    Vigreux, B.; Jaouen, C.

    1987-01-01

    Advanced cement solidification processes and systems have been developed by SGN to meet changing requirements in radioactive waste processing and packaging and to avoid the difficulties often encountered in waste concreting on an industrial scale. SGN applies a strict development methodology to ensure integration of the most recent information on chemical behavior of solidified wastes plus compliance with the precise needs of waste producers and evolving regulatory requirements concerning waste package storage and disposal. Based on a hierarchical definition of objectives, this methodology was implemented following an overall study on radwaste concreting performed in 1983 and 1984 for Electricite de France (EdF), France's national electric power utility. It ensures that industrial and regulatory factors are fully considered from the start of development work. It also constrains development in the direction of true process optimization and guarantees compliance with defined objectives. The methodology has helped SGN develop concreting processes adapted to various types of radioactive waste. The most widely employed processes are first briefly described in this paper. It then presents continuous and batch systems using these processes, focusing on technological features chosen at a very early stage in development

  2. Immobilisation/solidification of hazardous toxic waste in cement matrices

    Directory of Open Access Journals (Sweden)

    Macías, A.

    1999-06-01

    Full Text Available Immobilization and solidification of polluting waste, introduced into the industrial sector more than 20 years ago, and throughout last 10 years is being the object of a growing interest for engineers and environment scientists, has become a remarkable standardized process for treatment and management of toxic and hazardous liquid wastes, with special to those containing toxic metals. Experimental monitorization of the behaviour of immobilized waste by solidification and stabilisation in life time safe deposits is not possible, reason why it is essential to develop models predicting adequately the behaviour of structures that have to undergo a range of conditions simulating the environment where they are to be exposed. Such models can be developed only if the basic physical and chemical properties of the system matrix/solidifying-waste are known. In this work immobilization/solidification systems are analyzed stressing out the formulation systems based on Portland cement. Finally, some examples of the results obtained from the study of interaction of specific species of wastes and fixation systems are presented.

    La inmovilización y solidificación de residuos contaminantes, implantada en el sector comercial desde hace más de 20 años y que desde hace diez es objeto de creciente interés por parte de ingenieros y científicos medioambientales, se ha convertido en un proceso estandarizado único para el tratamiento y gestión de residuos tóxicos y peligrosos líquidos y, en especial, de los que contienen metales pesados. La monitorización experimental del comportamiento de un residuo inmovilizado por solidificación y estabilización en el tiempo de vida de un depósito de seguridad no es posible, por lo que es imprescindible desarrollar modelos que predigan satisfactoriamente el comportamiento del sistema bajo un rango representativo de condiciones del entorno de exposición. Tales modelos sólo pueden ser desarrollados si se

  3. Management of radioactive waste nuclear power plants

    International Nuclear Information System (INIS)

    Dlouhy, Z.; Marek, J.

    1976-01-01

    The authors give a survey of the sources, types and amounts of radioactive waste in LWR nuclear power stations (1,300 MWe). The amount of solid waste produced by a Novovorenezh-type PWR reactor (2 x 400 resp. 1 x 1,000 MWe) is given in a table. Treatment, solidification and final storage of radioactive waste are shortly discussed with special reference to the problems of final storage in the CSR. (HR) [de

  4. Nuclear waste

    International Nuclear Information System (INIS)

    1991-01-01

    The Privacy Act of 1974 restricts both the type of information on private individuals that federal agencies may maintain in their records and the conditions under which such information may be disclosed. The Nuclear Regulatory Commission, which must approve DOE plans to build a nuclear waste repository at the Yucca Mountain site in Nevada, requires a quality assurance program to guarantee that studies of the site are done by qualified employees. Under such a program, the training and qualifications of DOE and contractor employees would be verified. This report reviews DOE's efforts to identify and resolve the implications of the Privacy Act for DOE's quality assurance program and how the delay in resolving Privacy Act issues may have affected preliminary work on the Yucca Mountain project

  5. Toxic and hazardous waste disposal. Volume 1. Processes for stabilization/solidification

    International Nuclear Information System (INIS)

    Pojasek, R.B.

    1979-01-01

    Processes for the stabilization and/or solidification of toxic, hazardous, and radioactive wastes are reviewed. The types of wastes classified as hazardous are defined. The following processes for the solidification of hazardous wastes are described: lime-based techniques; thermoplastic techniques; organic polymer techniques; and encapsulation. The following processes for the solidification of high-level radioactive wastes are described: calcination; glassification; and ceramics. The solidification of low-level radioactive wastes with asphalt, cement, and polymeric materials is also discussed. Other topics covered include: the use of an extruder/evaporator to stabilize and solidify hazardous wastes; effect disposal of fine coal refuse and flue gas desulfurization slurries using Calcilox additive stabilization; the Terra-Tite Process; the Petrifix Process; the SFT Terra-Crete Process; Sealosafe Process; Chemfix Process; and options for disposal of sulfur oxide wastes

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-04-01

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

  7. Preliminary evaluation of alternative waste form solidification processes. Volume I. Identification of the processes

    International Nuclear Information System (INIS)

    Treat, R.L.; Nesbitt, J.F.; Blair, H.T.; Carter, J.G.; Gorton, P.S.; Partain, W.L.; Timmerman, C.L.

    1980-04-01

    This document contains preconceptual design data on 11 processes for the solidification and isolation of nuclear high-level liquid wastes (HLLW). The processes are: in-can glass melting (ICGM) process, joule-heated glass melting (JHGM) process, glass-ceramic (GC) process, marbles-in-lead (MIL) matrix process, supercalcine pellets-in-metal (SCPIM) matrix process, pyrolytic-carbon coated pellets-in-metal (PCCPIM) matrix process, supercalcine hot-isostatic-pressing (SCHIP) process, SYNROC hot-isostatic-pressing (SYNROC HIP) process, titanate process, concrete process, and cermet process. For the purposes of this study, it was assumed that each of the solidification processes is capable of handling similar amounts of HLLW generated in a production-sized fuel reprocessing plant. It was also assumed that each of the processes would be enclosed in a shielded canyon or cells within a waste facility located at the fuel reprocessing plant. Finally, it was assumed that all of the processes would be subject to the same set of regulations, codes and standards. Each of the solidification processes converts waste into forms that may be acceptable for geological disposal. Each process begins with the receipt of HLLW from the fuel reprocessing plant. In this study, it was assumed that the original composition of the HLLW would be the same for each process. The process ends when the different waste forms are enclosed in canisters or containers that are acceptable for interim storage. Overviews of each of the 11 processes and the bases used for their identification are presented in the first part of this report. Each process, including its equipment and its requirements, is covered in more detail in Appendices A through K. Pertinent information on the current state of the art and the research and development required for the implementation of each process are also noted in the appendices

  8. Alternative solidified forms for nuclear wastes

    International Nuclear Information System (INIS)

    McElroy, J.L.; Ross, W.A.

    1976-01-01

    Radioactive wastes will occur in various parts of the nuclear fuel cycle. These wastes have been classified in this paper as high-level waste, intermediate and low-level waste, cladding hulls, and residues. Solidification methods for each type of waste are discussed in a multiple barrier context of primary waste form, applicable coatings or films, matrix encapsulation, canister, engineered structures, and geological storage. The four major primary forms which have been most highly developed are glass for HLW, cement for ILW, organics for LLW, and metals for hulls

  9. Solidification of radioactive waste solutions by pelletization technique

    International Nuclear Information System (INIS)

    Akbar, A.H.; Koester, R.; Rudolph, G.

    1980-04-01

    A possible way of performing the cement fixation of radioactive wastes is the incorporation into cement pellets on a pan pelletizer, followed by embedding the pellets into an inactive cement matrix. This procedure is suitable for various types of waste, particularly for medium level liquid wastes, and can be used both at drum disposal and at in-situ solidification. This report describes some initial studies on the pelletization technique using a laboratory pelletizer. Formation and size of the pellets have been found to be determined by speed, angle, and load of the pan, ratio and mode of addition of the liquid and solid components, ect. Pellets in various compositions have been produced from cement and water or simulated waste solution, in some cases with the addition of bentonite for improving cesium retention. Some mechanical properties of the pellets such as fall height of fresh pellets, development of hardness (crush test), impact and abrasion resistance, have been determined. Some preliminary experiments were done on backfilling the void space between the pellets - about 40 per cent of the bulk volume - with cement grouts of appropriate compositions. (orig.) [de

  10. Analysis of capital and operating costs associated with high level waste solidification processes

    International Nuclear Information System (INIS)

    Heckman, R.A.; Kniazewycz, B.G.

    1978-03-01

    An analysis was performed to evaluate the sensitivity of annual operating costs and capital costs of waste solidification processes to various parameters defined by the requirements of a proposed Federal waste repository. Five process methods and waste forms examined were: salt cake, spray calcine, fluidized bed calcine, borosilicate glass, and supercalcine multibarrier. Differential cost estimates of the annual operating and maintenance costs and the capital costs for the five HLW solidification alternates were developed

  11. Nuclear waste

    International Nuclear Information System (INIS)

    1989-10-01

    The Department of Energy is awarding grants to the state of Nevada for the state's participation in DOE's program to investigate Yucca Mountain as a possible site for the disposal of civilian nuclear waste. This report has found that DOE's financial assistance budget request of $15 million for Nevada's fiscal year 1990 was not based on the amount the state requested but rather was derived by increasing Nevada's grant funds from the previous year in proportion to the increase that DOE requested for its own activities at the Nevada site. DOE's evaluations of Nevada's requests are performed too late to be used in DOE's budget formulation process because Nevada has been applying for financial assistance at about the same time that DOE submits its budget request to Congress

  12. 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

  13. 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

  14. Solidification of radioactive liquid wastes. A comparison of treatment options for spent resins and concentrates

    International Nuclear Information System (INIS)

    Roth, A.; Willmann, F.; Ebata, M.; Wendt, S.

    2008-01-01

    Ion exchange is one of the most common and effective treatment methods for liquid radioactive waste. However, spent ion exchange resins are considered to be problematic waste that in many cases require special approaches and pre-conditioning during its immobilization to meet the acceptance criteria for disposal. Because of the function that they fulfill, spent ion exchange resins often contain high concentrations of radioactivity and pose special handling and treatment problems. Another very common method of liquid radioactive waste treatment and water cleaning is the evaporation or diaphragm filtration. Both treatment options offer a high volume reduction of the total volume of liquids treated but generate concentrates which contain high concentrations of radioactivity. Both mentioned waste streams, spent resins as well as concentrates, resulting from first step liquid radioactive waste treatment systems have to be conditioned in a suitable manner to achieve stable waste products for final disposal. The most common method of treatment of such waste streams is the solidification in a solid matrix with additional inactive material like cement, polymer etc. In the past good results have been achieved and the high concentration of radioactivity can be reduced by adding the inactive material. On the other hand, under the environment of limited space for interim storage and the absence of a final repository site, the built-up of additional volume has to be considered as very critical. Moreover, corrosive effects on cemented drums during long-term interim storage at the surface have raised doubts about the long-term stability of such waste products. In order to avoid such disadvantages solidification methods have been improved in order to get a well-defined product with a better load factor of wastes in the matrix. In a complete different approach, other technologies solidify the liquid radioactive wastes without adding of any inactive material by means of drying

  15. Low-level waste cement solidification design, installation, and start-up

    International Nuclear Information System (INIS)

    Jezek, G.R.

    1988-08-01

    This report describes the design, installation, and start-up activities of the Cement Solidification System (CSS) at the West Valley Demonstration Project (WVDP), West Valley, New York. The CSS, designed to operate within an existing process cell, automatically and remotely solidifies low-level nuclear waste by mixing it with Portland Type I cement. The qualified waste form mixture is placed into square, 270-litre (71-gallon) metal drums. The drums have an integral polyethylene liner to protect the carbon-steel material from potential corrosion. The CSS produces drums at a continuous operation rate of four drums per hour. All system processing data is monitored by a computerized Data Acquisition System (DAS). 6 figs

  16. Nuclear waste

    International Nuclear Information System (INIS)

    1990-07-01

    The state of Nevada opposed DOE's development of a nuclear waste repository at Yucca Mountain. As a result, disputes have arisen over how Nevada has spent financial assistance provided by DOE to pay the state's repository program costs. This report reviews Nevada's use of about $32 million in grant funds provided by DOE through June 1989 and found that Nevada improperly spent about $1 million. Nevada used as much as $683,000 for lobbying and litigation expenses that were unauthorized or were expressly prohibited by law, court decision, or grant terms; exceeded a legislative spending limit on socioeconomic studies by about $96,000; and used, contrary to grant terms, about $275,000 from one grant period to pay expenses incurred in the prior year. Also, Nevada did not always exercise adequate internal controls over grant funds, such as timely liquidation of funds advanced to contractors. A permissive approach to grant administration by DOE contributed to Nevada's inappropriate use of grant funds

  17. Nuclear wastes

    International Nuclear Information System (INIS)

    2004-01-01

    Here is made a general survey of the situation relative to radioactive wastes. The different kinds of radioactive wastes and the different way to store them are detailed. A comparative evaluation of the situation in France and in the world is made. The case of transport of radioactive wastes is tackled. (N.C.)

  18. Solidification of Savannah River Plant high level waste

    International Nuclear Information System (INIS)

    Maher, R.; Shafranek, L.F.; Kelley, J.A.; Zeyfang, R.W.

    1981-11-01

    Authorization for construction of the Defense Waste Processing Facility (DWPF) is expected in FY 83. The optimum time for stage 2 authorization is about three years later. Detailed design and construction will require approximately five years for stage 1, with stage 2 construction completed about two to three years later. Production of canisters of waste glass would begin in 1988, and the existing backlog of high level waste sludge stored at SRP would be worked off by about the year 2000. Stage 2 operation could begin in 1990. The technology and engineering are ready for construction and eventual operation of the DWPF for immobilizing high level radioactive waste at Savannah River Plant (SRP). Proceeding with this project will provide the public, and the leadership of this country, with a crucial demonstration that a major quantity of existing high level nuclear wastes can be safely and permanently immobilized. Early demonstration will both expedite and facilitate rational decision making on this aspect of the nuclear program. Delay in providing these facilities will result in significant DOE expenditures at SRP for new tanks just for continued temporary storage of wastes, and would probably result in dissipation of the intellectual and planning momentum that has built up in developing the project

  19. Processing and solidification of Savannah River Plant high-level waste

    International Nuclear Information System (INIS)

    Kelley, J.A.

    1981-01-01

    The entire flowsheet for processing and solidification of Savannah River Plant (SRP) high-level wastes has been demonstrated. A new small-scale integrated pilot plant is operating with actual radioactive wastes, and large-scale equipment is being demonstrated with nonradioactive simulated wastes. Design of a full-scale waste solidification plant is in progress. Plant construction is expected to begin in 1983, and startup is anticipated in 1988. The plant will poduce about 500 cans of glass per year with each can containing about 1.5 tons of glass

  20. Solidification of hazardous and mixed radioactive waste at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Boehmer, A.M.; Larsen, M.M.

    1986-01-01

    EG and G Idaho has initiated a program to develop treatment options for the hazardous and mixed wastes generated at the Idaho National Engineering Laboratory (INEL). This program includes development of solidification methods for some of these wastes. Testing has shown that toxic wastes can be successfully solidified using cement, cement-silicate, or ENVIROSTONE binders to produce nontoxic stable waste forms for safe, long term disposal. This paper presents the results of the solidification development program conducted at the INEL by EG and G Idaho

  1. Solidification of hazardous and mixed radioactive waste at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Boehmer, A.M.; Larsen, M.M.

    1986-03-01

    EG and G Idaho has initiated a program to develop treatment options for the hazardous and mixed wastes generated at the Idaho National Engineering Laboratory (INEL). This program includes development of solidification methods for some of these wastes. Testing has shown that toxic wastes can be successfully solidified using cement, cement-silicate, or ENVIROSTONE binders to produce nontoxic stable waste forms for safe, long term disposal. This paper presents the results of the solidification development program conducted at the INEL by EG and G Idaho

  2. Hazardous and mixed waste solidification development conducted at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Boehmer, A.M.; Larsen, M.M.

    1986-04-01

    EG and G Idaho, Inc., has initiated a program to develop safe, efficient, cost-effective solidification treatment methods for the disposal of some of the hazardous and mixed wastes generated at the Idaho National Engineering Laboratory (INEL). Testing has shown that Extraction Procedure (EP) toxic wastes can be successfully solidified using cement, cement-silicate, or ENVIROSTONE binders to produce nontoxic stable waste forms for safe, long-term disposal as general or low-level waste, depending upon the radioactivity. The results of the solidification development program are presented in this report

  3. Solidification of problem wastes: Annual progress report, October 1985-September 1986

    International Nuclear Information System (INIS)

    Franz, E.M.; Heiser, J.H. III; Colombo, P.

    1987-02-01

    This report describes initial work on the development of solidification systems for sodium nitrate waste and compacted waste. Sodium nitrate waste has been solidified in three types of materials: polyethylene, polyester-styrene (PES), and latex cement. Evaluations of the properties of the waste form, such as the ANS 16.1 leaching test, water immersion test and compressive strength measurements were performed on the waste forms containing various amounts of sodium nitrate. 9 refs., 9 figs., 7 tabs

  4. Solidification as low cost technology prior to land filling of industrial hazardous waste sludge.

    Science.gov (United States)

    El-Sebaie, O; Ahmed, M; Ramadan, M

    2000-01-01

    The aim of this study is to stabilize and solidify two different treated industrial hazardous waste sludges, which were selected from factories situated close to Alexandria. They were selected to ensure their safe transportation and landfill disposal by reducing their potential leaching of hazardous elements, which represent significant threat to the environment, especially the quality of underground water. The selected waste sludges have been characterized. Ordinary Portland Cement (OPC), Cement Kiln Dust (CKD) from Alexandria Portland Cement Company, and Calcium Sulphate as a by-product from the dye industry were used as potential solidification additives to treat the selected treated waste sludges from tanning and dyes industry. Waste sludges as well as the solidified wastes have been leach-tested, using the General Acid Neutralization Capacity (GANC) procedure. Concentration of concerning metals in the leachates was determined to assess changes in the mobility of major contaminants. The treated tannery waste sludge has an acid neutralization capacity much higher than that of the treated dyes waste sludge. Experiment results demonstrated the industrial waste sludge solidification mix designs, and presented the reduction of contaminant leaching from two types of waste sludges. The main advantages of solidification are that it is simple and low cost processing which includes readily available low cost solidification additives that will convert industrial hazardous waste sludges into inert materials.

  5. Small-scale demonstration of high-level radioactive waste processing and solidification using actual SRP waste

    International Nuclear Information System (INIS)

    Okeson, J.K.; Galloway, R.M.; Wilhite, E.L.; Woolsey, G.B.; Ferguson, R.B.

    1980-01-01

    A small-scale demonstration of the high-level radioactive waste solidification process by vitrification in borosilicate glass is being conducted using 5-6 liter batches of actual waste. Equipment performance and processing characteristics of the various unit operations in the process are reported and, where appropriate, are compared to large-scale results obtained with synthetic waste

  6. Interim solidification of SRP waste with silica, bentonite, or phosphoric acid

    International Nuclear Information System (INIS)

    Thompson, G.H.

    1976-03-01

    One option for interim waste management at the Savannah River Plant is in-tank solidification of the liquid waste solutions. This would reduce the mobility of these highly radioactive solutions until techniques for their long-term immobilization and storage are developed and implemented. Interim treatments must permit eventual retrieval of waste and subsequent incorporation into a high-integrity form. This study demonstrated the solidification of simulated alkaline waste solutions by reaction with silica, bentonite, and phosphoric acid. Alkaline waste can be solidified by reaction with silica gel, silica flour, or sodium silicate solution. Solidified products containing waste salt can be retrieved by slurrying with water. Alkaline supernate (solution in equilibrium with alkaline sludge in SRP waste tanks) can be solidified by reaction with bentonite to form cancrinite powder. The solidified waste can be retrieved by slurrying with water. Alkaline supernate can be solidified by partial evaporation and reaction with phosphoric acid. Water is incorporated into hydrated complexes of trisodium phosphate. The product is soluble, but actual plant waste would not solidify completely because of decay heat. Reaction of simulated alkaline waste solutions with silica gel, silica flour, or bentonite increases the volume by a factor of approximately 6 over that of evaporated waste; reaction with phosphoric acid results in a volume 1.5 times that of evaporated waste. At present, the best method for in-tank solidification is by evaporation, a method that contributes no additional solids to the waste and does not compromise any waste management options

  7. Nuclear wastes, a questionnaire

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    Questionnaire giving basic information for the public on nuclear wastes and radioactive waste management. Risk and regulations to reduce the risk to permissible limits are more particularly developed. A survey of radioactive wastes is made along the fuel cycle: production, processing, transport, disposal to end on effect of waste management on the cost of nuclear kWh [fr

  8. Solidification of intermediate level liquid waste - ILLW, CEMEX waste form qualification

    International Nuclear Information System (INIS)

    D'Andrea, V.; Guerra, M.; Pancotti, F.; Maio, V.

    2015-01-01

    In the Sogin EUREX Facility about 125 m 3 of intermediate level radioactive waste and about 113 m 3 of low level radioactive waste, produced during the re-processing of MTR and CANDU fuel, are stored. Solidification of these wastes is planned in order to fulfill the specific requirements established by the Safety Authority, taking into account the criteria set up in a Technical Guide on the issue of radioactive waste management. The design of a cementation plant (CEMEX) of all liquid radioactive wastes is currently ongoing. The process requires that the liquid waste is neutralized with NaOH (NaOH 19 M) and metered into 440 liter drum together with the cement, while the mixture is stirred by a lost paddle ('in drum mixing process'). The qualification of the Waste Form consists of all the activities demonstrating that the final cemented product has the minimum requirements (mechanical, chemical and physical characteristics) compliant with all the subsequent management phases: long-term interim storage, transport and long-term disposal of the waste. All tests performed to qualify the conditioning process for immobilizing first extraction cycle (MTR and CANDU) and second extraction cycle liquid wastes, gave results in compliance with the minimum requirements established for disposal

  9. Defense waste solidification studies. Volume 2. Drawing supplement. Savannah River Plant, Project S-1780

    International Nuclear Information System (INIS)

    1977-01-01

    Volume 2 contains the drawings prepared and used in scoping and estimating the Glass-Form Waste Solidification facilities and the alternative studies cited in the report, the Off-Site Shipping Case, the Decontaminated Salt Storage Case, and a revised Reference Plant (Concrete-Form Waste) Case

  10. Application of sulfur concrete for solidification of radioactive wastes and building of repositories

    International Nuclear Information System (INIS)

    Cholerzynski, A.; Tomczak, W.; Switalski, J.

    2000-01-01

    The application of sulfur concrete as solidification material for radioactive wastes and as building material used in repositories have been presented. Their high shear strength, low level of leaching, and high radiation resistance decide of positive recommendation of such material for wide use in radioactive waste treatment processes and repositories building

  11. Nuclear waste

    International Nuclear Information System (INIS)

    1992-08-01

    In September 1989, a New York commission charged with choosing a site for a low-level radioactive waste disposal facility announced its intent to conduct limited investigations at five potential sites. In this paper the authors review the commission's site selection process. After discussions with your office, the authors agreed to determine if the commission's consideration and selection of the Taylor North site was consistent with its prescribed procedures for considering offered sites. The authors also agreed to identify technical and other issues that need to be addressed before the final site evaluation and the selection steps can be completed

  12. Nuclear waste management

    International Nuclear Information System (INIS)

    1982-12-01

    The subject is discussed, with special reference to the UK, under the headings: radiation; origins of the waste (mainly from nuclear power programme; gas, liquid, solid; various levels of activity); dealing with waste (methods of processing, storage, disposal); high-active waste (storage, vitrification, study of means of eventual disposal); waste management (UK organisation to manage low and intermediate level waste). (U.K.)

  13. Solidification of radioactive liquid wastes, Treatment options for spent resins and concentrates - 16405

    International Nuclear Information System (INIS)

    Roth, Andreas

    2009-01-01

    of a final repository site, the built-up of additional volume has to be considered as very critical. Moreover, corrosive effects on cemented drums during long-term interim storage at the surface have raised doubts about the long-term stability of such waste products. In order to avoid such disadvantages solidification methods have been improved in order to get a well-defined product with a better load factor of wastes in the matrix. In a complete different approach, other technologies solidify the liquid radioactive wastes without adding of any inactive material by means of drying. Different installations are available for spent resin or concentrate drying. Such methods produce suitable waste products for final disposal and achieve additional volume reduction factors for final disposal. On the other hand, design of the treatment plant as well as the subsequent drum handling and interim storage plants have to consider the high concentration of radioactivity in the final waste product and have to deal with appropriate packages, remote controlled operations and shielding. The presentation will briefly introduce examples for the mentioned treatment options and report on results achieved with it in nuclear installations with WH (Westinghouse)/ HANSA (Hansa Projekt Anlagentechnik GmbH) technologies. Further on, the paper will discuss the evaluation of the advantages and disadvantages of the treatment options relative to the characteristics of the wastes and the environment to be considered (availability of repository, existing or assumed repository, acceptance criteria etc.). In conclusion such self assessment regarding priorities, background and goals is essential for the selection of a suitable approach. - The industry can address the various specific needs with proven technologies and services; - Westinghouse/ Hansa Projekt Anlagentechnik have served various customers around the globe under different regulatory environment with successful equipment deliveries and

  14. Solidification of radioactive wastes by bituminization technology. II

    International Nuclear Information System (INIS)

    Stuchlik, S.; Brzobohaty, J.

    1985-01-01

    The bituminization line consists of a rotor film evaporator, a condenser, reserve tanks of bitumen emulsion and model concentrates, a roller train, a vapour concentrate tank, a control console, a bitumen emulsion pump, a model concentrates pump, and a tank for model concentrate preparation. Anion-active emulsion Silembit S-60 produced by Paramo Pardubice was chosen as the bitumen emulsion. A block diagram is given of the experimental bituminization line and its processing is described of model nonactive concentrates whose composition corresponds to that of actual wastes from the V-1 nuclear power plant. Successful tests of the line showed that it could be used for the disposal of radioactive wastes. (E.S.)

  15. Nuclear waste

    International Nuclear Information System (INIS)

    England-Joseph, J.

    1991-03-01

    This paper discusses the Department of Energy's (DOE) procedures for annually assessing the adequacy of the fee that utilities pay for disposal of spent (used) nuclear fuel. In a June 1990 report, it was recommended, among other things, that the Congress authorize DOE to automatically adjust the fee each year on the basis of an inflation index. At that time, DOE also favored fee indexing; however, it subsequently reversed its position. Because of this change, it is now believe that Congress should require DOE to index the fee to the rate of inflation

  16. Solidification of Waste Steel Foudry Dust with Portland Cement

    Czech Academy of Sciences Publication Activity Database

    Škvára, F.; Kaštánek, František; Pavelková, I.; Šolcová, Olga; Maléterová, Ywetta; Schneider, Petr

    B89, č. 1 (2001), s. 67-81 ISSN 0304-3894 R&D Projects: GA ČR GA104/99/0440 Institutional research plan: CEZ:AV0Z4072921; CEZ:MSM 223100002 Keywords : solidification, * foundry dust * cement Subject RIV: CI - Industrial Chemistry, Chemical Engineering Impact factor: 0.497, year: 2001

  17. Feasibility study of solidification for low-level liquid waste generated by sulfuric acid elution treatment of spent ion exchange resin

    International Nuclear Information System (INIS)

    Asano, Takashi; Kawasaki, Tooru; Higuchi, Natsuko; Horikawa, Yoshihiko

    2007-01-01

    Low-level liquid waste with relatively high levels of radioactivity is generated by the sulfuric acid elution treatment of spent ion exchange resin used in water purification systems of nuclear power plants. We studied cement-like solidification process for this type waste that contains a high concentration of sodium sulfate. For this type waste, it is important that the sulfate ion should not dissolve from the solid waste because it forms ettringite on reaction with minerals in the concrete, and this leads to cracking during repository storage. It is also preferable that the pH of pore water of the solid waste be low, because the bentonite of the repository changes in quality on exposure to alkaline solution. Our solidification process has two procedures: conversion into insoluble sulfate from sodium sulfate (CIS) and formation of low pH cement-like solid (FLS). In the CIS procedure, BaSO 4 precipitation occurs with addition of Ba(OH) 2 ·8H 2 O to the liquid waste when the Ba/SO 4 molar ratio > 1. In the FLS procedure, silica fume and blast furnace slag are added to the liquid wastes containing Ba S O 4 precipitate. The CIS reaction yield is over 98% and the pH of pore water of the solid waste is 11.5 or less. Therefore, we think that our solidification process is one of the best methods for treating liquid waste that contains a high concentration of sodium sulfate. (author)

  18. Crystalline matter for solidification of highly radioactive wastes

    International Nuclear Information System (INIS)

    Grauer, R.

    1984-02-01

    Highly active wastes from reprocessed nuclear fuels must be incorporated into a solid chemically resistant inorganic matrix prior to final storage. One possible alternative to glassification is to embed the complex oxide mixture in a crystalline ceramic. A discussion from the structural and chemical viewpoint is presented giving guidelines for the selection and development of such a product. The chemical and phase composition concerning the most important developments are described. SYNROC is the most highly developed solid ceramic that has been evaluated to date for power reactor wastes. However, its testing and development so far has been restricted to simulated inactive materials. One of the most important aspects of solid high activity wastes is their behaviour in water. SYNROC reacts more slowly than glasses with water at temperatures over 100 0 C. Its low release of actinides under these conditions is remarkable. At temperatures under 100 0 C the important nuclide Cs 137 is released from SYNROC and from glasses at comparable rates. These assertions concerning chemical stability are however based on short term experiments, which have not considered the possibly complex interactions occurring during final storage. The information is therefore insufficient to describe the basic model required to predict long term behaviour under final storage conditions. Finally the report makes recommendations for a further programme of work. (Auth.)

  19. Solidification of ash from incineration of low-level radioactive waste

    International Nuclear Information System (INIS)

    Roberson, W.A.; Albenesius, E.L.; Becker, G.W.

    1983-01-01

    The safe disposal of both high-level and low-level radioactive waste is a problem of increasing national attention. A full-scale incineration and solidification process to dispose of suspect-level and low-level beta-gamma contaminated combustible waste is being demonstrated at the Savannah River Plant (SRP) and Savannah River Laboratory (SRL). The stabilized wasteform generated by the process will meet or exceed all future anticipated requirements for improved disposal of low-level waste. The incineration process has been evaluated at SRL using nonradioactive wastes, and is presently being started up in SRP to process suspect-level radioactive wastes. A cement solidification process for incineration products is currently being evaluated by SRL, and will be included with the incineration process in SRP during the winter of 1984. The GEM alumnus author conducted research in a related disposal solidification program during the GEM-sponsored summer internship, and upon completion of the Masters program, received full-time responsibility for developing the incineration products solidification process

  20. Japanese Nuclear Waste Avatars

    International Nuclear Information System (INIS)

    Wynn Kirby, Peter; Stier, Daniel

    2016-01-01

    Japan's cataclysmic 2011 tsunami has become a vast, unwanted experiment in waste management. The seismic event and resulting Fukushima Daiichi radiation crisis created an awkwardly fortuitous rupture in Japanese nuclear practice that exposed the lax and problematic management of nuclear waste in this country to broader scrutiny, as well as distortions in its very conception. This article looks at the full spectrum of nuclear waste in post-tsunami Japan, from spent fuel rods to contorted reactor containment, and the ways that nuclear waste mirrors or diverges from more quotidian waste practices in Japanese culture. Significantly, the Fukushima Daiichi plant itself and its erstwhile banal surroundings have themselves transmuted into an unwieldy form of nuclear waste. The immense challenges of the Fukushima Daiichi site have stimulated a series of on-the-fly innovations that furnish perspective on more everyday nuclear waste practices in the industry. While some HLW can be reprocessed for limited use in today's reactors, it cannot be ignored that much of Japan's nuclear waste is simply converted into other forms of waste. In a society that has long been fixated on segregating filth, maintaining (imagined) purity, and managing proximity to pollution, the specter of nuclear waste looms over contemporary Japan and its ongoing debates over resources, risk, and Japanese nuclear identity itself

  1. Solidification of low-level waste - a dilemma for the small user

    International Nuclear Information System (INIS)

    Harris, S.; Gilmore, A.

    1980-01-01

    The requirement that radioactive waste for sea disposal must be solidified by the originator is discussed. Attempts to solidify small quantities of radioactive waste such as contaminated oils and labelled benzyopyrene with other solvents are described. Encapsulation media tested were concrete and interior and exterior grade Polyfilla (a plaster and cellulose based filler). Problems were presented by the difficulty of mixing the materials and by the maximum uptake of solvents while still allowing solidification. In all cases a soft crumbling material resulted. It is concluded that solidification processing on a small scale does not make economic or scientific sense and that if solidification is necessary it would be better carried out as a national operation by collecting liquids from users. (U.K.)

  2. Survey of agents and techniques applicable to the solidification of low-level radioactive wastes

    International Nuclear Information System (INIS)

    Fuhrmann, M.; Neilson, R.M. Jr.; Colombo, P.

    1981-12-01

    A review of the various solidification agents and techniques that are currently available or potentially applicable for the solidification of low-level radioactive wastes is presented. An overview of the types and quantities of low-level wastes produced is presented. Descriptions of waste form matrix materials, the wastes types for which they have been or may be applied and available information concerning relevant waste form properties and characteristics follow. Also included are descriptions of the processing techniques themselves with an emphasis on those operating parameters which impact upon waste form properties. The solidification agents considered in this survey include: hydraulic cements, thermoplastic materials, thermosetting polymers, glasses, synthetic minerals and composite materials. This survey is part of a program supported by the United States Department of Energy's Low-Level Waste Management Program (LLWMP). This work provides input into LLWMP efforts to develop and compile information relevant to the treatment and processing of low-level wastes and their disposal by shallow land burial

  3. Survey of agents and techniques applicable to the solidification of low-level radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Fuhrmann, M.; Neilson, R.M. Jr.; Colombo, P.

    1981-12-01

    A review of the various solidification agents and techniques that are currently available or potentially applicable for the solidification of low-level radioactive wastes is presented. An overview of the types and quantities of low-level wastes produced is presented. Descriptions of waste form matrix materials, the wastes types for which they have been or may be applied and available information concerning relevant waste form properties and characteristics follow. Also included are descriptions of the processing techniques themselves with an emphasis on those operating parameters which impact upon waste form properties. The solidification agents considered in this survey include: hydraulic cements, thermoplastic materials, thermosetting polymers, glasses, synthetic minerals and composite materials. This survey is part of a program supported by the United States Department of Energy's Low-Level Waste Management Program (LLWMP). This work provides input into LLWMP efforts to develop and compile information relevant to the treatment and processing of low-level wastes and their disposal by shallow land burial.

  4. Radioactivity and nuclear waste

    International Nuclear Information System (INIS)

    Saas, A.

    1996-01-01

    Radioactive wastes generated by nuclear activities must be reprocessed using specific treatments before packaging, storage and disposal. This digest paper gives first a classification of radioactive wastes according to their radionuclides content activity and half-life, and the amount of wastes from the different categories generated each year by the different industries. Then, the radiotoxicity of nuclear wastes is evaluated according to the reprocessing treatments used and to their environmental management (surface storage or burial). (J.S.)

  5. Cement matrix solidification of decontamination ion-exchange resin waste

    International Nuclear Information System (INIS)

    Holt, N. S.; Hebditch, D. J.

    1991-01-01

    Crossflow membrane separation has been evaluated as an alternative to more conventional separation methods for the removal of oil from nuclear power station aqueous effluents and liquid wastes. Three commercially available membranes were investigated at small pilot scale; sintered metal power and metal fibre membranes, both of tubular geometries, and hollow fibre polypropylene. The sintered powder membrane gave by far the best oil water separation performance. Less than 10 ppm oil in the aqueous permeate was readily achieved and the oil was concentrated up to 75% by volume from feed concentrations in the range 1000 ppm to 10%. The presence of solids was found to have a profound influence on permeation rates. On the basis of the data presented, a single stage scheme for the treatment of oily effluents is proposed

  6. Preliminary evaluation of alternative waste form solidification processes. Volume II. Evaluation of the processes

    International Nuclear Information System (INIS)

    1980-08-01

    This Volume II presents engineering feasibility evaluations of the eleven processes for solidification of nuclear high-level liquid wastes (HHLW) described in Volume I of this report. Each evaluation was based in a systematic assessment of the process in respect to six principal evaluation criteria: complexity of process; state of development; safety; process requirements; development work required; and facility requirements. The principal criteria were further subdivided into a total of 22 subcriteria, each of which was assigned a weight. Each process was then assigned a figure of merit, on a scale of 1 to 10, for each of the subcriteria. A total rating was obtained for each process by summing the products of the subcriteria ratings and the subcriteria weights. The evaluations were based on the process descriptions presented in Volume I of this report, supplemented by information obtained from the literature, including publications by the originators of the various processes. Waste form properties were, in general, not evaluated. This document describes the approach which was taken, the developent and application of the rating criteria and subcriteria, and the evaluation results. A series of appendices set forth summary descriptions of the processes and the ratings, together with the complete numerical ratings assigned; two appendices present further technical details on the rating process

  7. Economic analysis of a volume reduction/polyethylene solidification system for low-level radioactive wastes

    International Nuclear Information System (INIS)

    Kalb, P.D.; Colombo, P.

    1985-01-01

    A study was conducted at Brookhaven National Laboratory to determine the economic feasibility of a fluidized bed volume reduction/polyethylene solidification system for low-level radioactive wastes. These results are compared with the ''null'' alternative of no volume reduction and solidification of aqueous waste streams in hydraulic cement. The economic analysis employed a levelized revenue requirement (LRR) technique conducted over a ten year period. An interactive computer program was written to conduct the LRR calculations. Both of the treatment/solidification options were considered for a number of scenarios including type of plant (BWR or PWR) and transportation distance to the disposal site. If current trends in the escalation rates of cost components continue, the volume reduction/polyethylene solidification option will be cost effective for both BWRs and PWRs. Data indicate that a minimum net annual savings of $0.8 million per year (for a PWR shipping its waste 750 miles) and a maximum net annual savings of $9 million per year (for a BWR shipping its waste 2500 miles) can be achieved. A sensitivity analysis was performed for the burial cost escalation rate, which indicated that variation of this factor will impact the total levelized revenue requirement. The burial cost escalation rate which yields a break-even condition was determined for each scenario considered. 11 refs., 8 figs., 39 tabs

  8. Solidification Technologies for Radioactive and Chemical Liquid Waste Treatment - Final CRADA Report

    International Nuclear Information System (INIS)

    Castiglioni, Andrew J.; Gelis, Artem V.

    2016-01-01

    This project, organized under DOE/NNSA's Global Initiatives for Proliferation Prevention program, joined Russian and DOE scientists in developing more effective solidification and storage technologies for liquid radioactive waste. Several patent applications were filed by the Russian scientists (Russia only) and in 2012, the technology developed was approved by Russia's Federal State Unitary Enterprise RADON for application throughout Russia in cleaning up and disposing of radioactive waste.

  9. Nuclear waste management

    International Nuclear Information System (INIS)

    Rodger, W.A.

    1985-01-01

    Most of our activities have always produced waste products of one sort or another. Huxley gives a humorous account of wastes throughout antiquity. So it should come as no surprise that some radioactive materials end up as waste products requiring management and disposal. Public perception of nuclear waste hazards places them much higher on the ''worry scale'' than is justified by the actual hazard involved. While the public perception of these hazards appears to revolve mostly around high-level wastes, there are several other categories of wastes that must also be controlled and managed. The major sources of radioactive wastes are discussed

  10. Nuclear waste disposal

    International Nuclear Information System (INIS)

    Lindblom, U.; Gnirk, P.

    1982-01-01

    The subject is discussed under the following headings: the form and final disposal of nuclear wastes; the natural rock and groundwater; the disturbed rock and the groundwater; long-term behavior of the rock and the groundwater; nuclear waste leakage into the groundwater; what does it all mean. (U.K.)

  11. Nuclear waste management

    International Nuclear Information System (INIS)

    Wyatt, A.

    1978-01-01

    The Canadian Nuclear Association has specific views on the following aspects of waste management: a) public information and public participation programs should be encouraged; b) positive political leadership is essential; c) a national plan and policy are necessary; d) all hazardous materials should receive the same care as radioactive wastes; e) power plant construction need not be restricted as long as there is a commitment to nuclear waste management; f) R and D should be funded consistently for nuclear waste management and ancillary topics like alternative fuel cycles and reprocessing. (E.C.B.)

  12. Nuclear waste disposal

    International Nuclear Information System (INIS)

    Schueller, W.

    1976-01-01

    The article cites and summarizes the papers on the topics: economic and ecological importance of waste management, reprocessing of nuclear fuel and recycling of uranium and plutonium, waste management and final storage, transports and organizational aspects of waste management, presented at this symposium. (HR/AK) [de

  13. Nuclear waste landscapes

    International Nuclear Information System (INIS)

    Solomon, B.D.; Cameron, D.M.

    1990-01-01

    In this paper the authors explore the time dimension in nuclear waste disposal, with the hope of untangling future land use issues for a full range of radioactive waste facilities. The longevity and hazards presented by nuclear reactor irradiated (spent) fuel and liquid reprocessing waste are well known. Final repositories for these highly radioactive wastes, to be opened early in the 21st Century, are to be located deep underground in rural locations throughout the developed world. Safety concerns are addressed by engineered and geological barriers containing the waste containers, as well as through geographic isolation from heavily populated areas. Yet nuclear power plants (as well as other applications of atomic energy) produce an abundance of other types of radioactive wastes. These materials are generally known as low level wastes (LLW) in the United States, though their level of longevity and radioactivity can vary dramatically

  14. Nuclear wastes: overview

    International Nuclear Information System (INIS)

    Billard, Isabelle

    2006-01-01

    Nuclear wastes are a major concern for all countries dealing with civil nuclear energy, whatever these countries have decided yet about reprocessing/storage options. In this chapter, a (exact) definition of a (radioactive) waste is given, together with definitions of waste classes and their characteristics (volumes, types etc.). The various options that are currently experienced in the world will be presented but focus will be put on the French case. Envision evolutions will be briefly presented. (author)

  15. Influence of non-technical policies on choices of waste solidification technologies

    International Nuclear Information System (INIS)

    Trubatch, S.L.

    1987-01-01

    This paper describes and discusses non-technical policy considerations which may improperly influence decisions on the solidification of low-level radioactive wastes (''LLW''). These policy considerations are contained principally in several State and Federal statutes which regulate various aspects of LLW disposal. One policy consideration in particular, the unqualified bias in favor of volume reduction, is shown to present a substantial potential for leading to technically suboptimal decisions on the appropriate processes for solidifying LLW. To avoid the unintended skewing of technical decisions by non-technical policy considerations, certain current policies may need to be revised to ensure that the choices of waste treatment, including decisions on solidification, are based primarily on reasonable assurance of adequate protection of public health and safety. This goal may be realized in part by basing any disposal fee structure on more than just LLW volume to include consideration of the waste's activity and its difficulty of confinement

  16. Nuclear waste issue

    International Nuclear Information System (INIS)

    Ryhanen, V.

    2000-01-01

    A prerequisite for future use of nuclear energy in electricity production is safe management of the radioactive wastes generated by nuclear power industry. A number of facilities have been constructed for different stages of nuclear waste management around the world, for example for conditioning of different kind of process wastes and for intermediate storage of spent nuclear fuel. Difficulties have often been encountered particularly when trying to advance plans for final stage of waste management, which is permanent disposal in stable geological formations. The main problems have not been technical, but poor public acceptance and lack of necessary political decisions have delayed the progress in many countries. However, final disposal facilities are already in operation for low- and medium-level nuclear wastes. The most challenging task is the development of final disposal solutions for long-lived high-level wastes (spent fuel or high-level reprocessing waste). The implementation of deep geological repositories for these wastes requires persistent programmes for technology development, siting and safety assessments, as well as for building public confidence in long-term safety of the planned repositories. Now, a few countries are proceeding towards siting of these facilities, and the first high-level waste repositories are expected to be commissioned in the years 2010 - 2020. (author)

  17. Solidification of low-level radioactive liquid waste using a cement-silicate process

    International Nuclear Information System (INIS)

    Grandlund, R.W.; Hayes, J.F.

    1979-01-01

    Extensive use has been made of silicate and Portland cement for the solidification of industrial waste and recently this method has been successfully used to solidify a variety of low level radioactive wastes. The types of wastes processed to date include fuel fabrication sludges, power reactor waste, decontamination solution, and university laboratory waste. The cement-silicate process produces a stable solid with a minimal increase in volume and the chemicals are relatively inexpensive and readily available. The method is adaptable to either batch or continuous processing and the equipment is simple. The solid has leaching characteristics similar to or better than plain Portland cement mixtures and the leaching can be further reduced by the use of ion-exchange additives. The cement-silicate process has been used to solidify waste containing high levels of boric acid, oils, and organic solvents. The experience of handling the various types of liquid waste with a cement-silicate system is described

  18. America's nuclear waste backlog

    International Nuclear Information System (INIS)

    Benenson, R.

    1981-01-01

    This report discusses three topics: concern and controversy relating to nuclear waste; high-level waste storage and politics of waste disposal. The most pressing waste disposal problem concerns spent fuel assemblies from commercial nuclear power plants. It was expected that commercial spent fuel would be sent to commercial reprocessing plants. The feasibility of commercial reprocessing in the United States is contingent on the expansion of the nuclear power industry. The current high-level liquid waste inventory is about 77 million gallons. These are stored at Richland, Washington; Aiken, South Carolina; and Idaho Falls, Idaho. The only commercial high-level wastes ever produced are stored at the defunct reprocessing facility at West Valley, New York. A high-level waste repository must be capable of isolating wastes that will remain dangerous for thousands of years. Salt has long been considered the most suitable medium for high-level and transuranic waste disposal. The timetable for opening a deep geological repository is one of the issues that will have to be dealt with by Congress. The 97th Congress appears ready to act on high-level nuclear waste legislation. Even opponents of nuclear expansion admit the necessity of legislation. Even if Congress gets its act together, it does not mean that the nuclear waste issue is gone. There are still unknowns - future of reprocessing, the needs and demands of the military; the health of the nuclear power industry; the objections of residents in potential site areas; the possibility of a state veto, and the unsolved technological problems in geologic site selection

  19. Nuclear waste disposal

    International Nuclear Information System (INIS)

    Hare, Tony.

    1990-01-01

    The Save Our Earth series has been designed to appeal to the inquiring minds of ''planet-friendly'' young readers. There is now a greater awareness of environmental issues and an increasing concern for a world no longer able to tolerate the onslaught of pollution, the depletion of natural resources and the effects of toxic chemicals. Each book approaches a specific topic in a way that is exciting and thought-provoking, presenting the facts in a style that is concise and appropriate. The series aims to demonstrate how various environmental subjects relate to our lives, and encourages the reader to accept not only responsibility for the planet, but also for its rescue and restoration. This volume, on nuclear waste disposal, explains how nuclear energy is harnessed in a nuclear reactor, what radioactive waste is, what radioactivity is and its effects, and the problems and possible solutions of disposing of nuclear waste. An awareness of the dangers of nuclear waste is sought. (author)

  20. Radioactive wastes from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Tomlinson, R.E.

    1975-01-01

    This symposium of 29 papers covers the following topics: overview; management and regulatory aspects; processing and solidification of low-level liquids; treatment of low-level solids; concentration and storage of high-level liquid wastes; and, solidification and storage of high level wastes. Selected papers are indexed separately

  1. WasteChem Corporation's Volume Reduction and Solidification (VRS) system for low-level radwaste treatment: Final report

    International Nuclear Information System (INIS)

    1988-01-01

    Since 1965, low and medium level radwastes from nuclear power stations, reprocessing plants and nuclear research centers have been stabilized using the Volume Reduction and Solidification (VRS) system. The VRS system uses an extruder/evaporator to evaporate the liquids from waste influents, while simultaneously incorporating the remaining radioactive solids in an asphalt binder. In the period 1965 to 1986 a minimum of 700,000 cubic feet of wastes have been processed with the VRS system. This report provides current operating data from various systems including the volume reduction factors achieved, and the progress of start-ups in the US. The report also provides previously unpublished experience with mixed wastes including uranium raffinate and nitrate-bearing sludges from surface impoundments. VRS systems in the US are currently operating at the Palisades and Hope Creek nuclear stations. These systems produce a variety of waste types including boric acid, bead resin, sodium sulfate and powdered resins. There are three start-ups of VRS systems scheduled in the US in 1987. These systems are at Fermi 2, Seabrook, and Nine Mile Point 2. Overseas, the startup of new systems continues with three VRS process lines coming on-line at the LaHague Reprocessing Center in France in 1986 and a start-up scheduled for 1987 at the Laguna Verde plant in Mexico. The US systems are operating continuously and with little required maintenance. Data on maintenance and the operator exposure are provided in this report. 6 refs., 11 figs., 13 tabs

  2. 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

  3. Solidification of radioactive waste resins using cement mixed with organic material

    Energy Technology Data Exchange (ETDEWEB)

    Laili, Zalina, E-mail: liena@nm.gov.my [Nuclear Science Programme, School of Applied Physics, Faculty of Science and Technology, Universiti Kebangsaan Malaysia (UKM), Bangi, 43600, Selangor Malaysia (Malaysia); Waste and Environmental Technology Division, Malaysian Nuclear Agency (Nuclear Malaysia), Bangi, 43000 Kajang, Selangor (Malaysia); Yasir, Muhamad Samudi [Nuclear Science Programme, School of Applied Physics, Faculty of Science and Technology, Universiti Kebangsaan Malaysia (UKM), Bangi, 43600, Selangor Malaysia (Malaysia); Wahab, Mohd Abdul [Waste and Environmental Technology Division, Malaysian Nuclear Agency (Nuclear Malaysia), Bangi, 43000 Kajang, Selangor (Malaysia)

    2015-04-29

    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.

  4. Method of cement-solidification of radioactive liquid wastes containing surfactant

    Energy Technology Data Exchange (ETDEWEB)

    Sugimoto, Y; Yusa, H

    1979-04-10

    Purpose: To provide the subject method comprising the steps of adjusting the concentration of the surfactant to a value less than the predetermined value even when the concentration of the surfactant is high, and rendering the uniaxial compression strength of the cement-solidification body into more than the defined fabrication reference value. Method: To radioactive liquid wastes there are applied means for boiling and heating liquid wastes by addition of sulfuric acid, means for cracking surfactants by the addition of oxidants and means for precipitating and arresting surfactants. After suppressing the hindrance of the cement hydration reaction by surfactants, the radioactive liquid wastes are cement-solidified. (Nakamura, S.).

  5. Using cement, lignite fly ash and baghouse filter waste for solidification of chromium electroplating treatment sludge

    Directory of Open Access Journals (Sweden)

    Wantawin, C.

    2004-02-01

    Full Text Available The objective of the study is to use baghouse filter waste as a binder mixed with cement and lignite fly ash to solidify sludge from chromium electroplating wastewater treatment. To save cost of solidification, reducing cement in binder and increasing sludge in the cube were focused on. Minimum percent cement in binder of 20 for solidification of chromium sludge was found when controlling lignite fly ash to baghouse filter waste at the ratio of 30:70, sludge to binder ratio of 0.5, water to mixer ratio of 0.3 and curing time of 7 days. Increase of sludge to binder ratio from 0.5 to 0.75 and 1 resulted in increase in the minimum percent cement in binder up to 30 percent in both ratios. With the minimum percent cement in binder, the calculated cement to sludge ratios for samples with sludge to binder ratios of 0.5, 0.75 and 1 were 0.4, 0.4 and 0.3 respectively. Leaching chromium and compressive strength of the samples with these ratios could achieve the solidified waste standard by the Ministry of Industry. For solidification of chromium sludge at sludge to binder ratio of 1, the lowest cost binder ratio of cement to lignite fly ash and baghouse filter waste in this study was 30:21:49. The cost of binder in this ratio was 718 baht per ton dry sludge.

  6. Solidification of Savannah River Plant high-level waste

    International Nuclear Information System (INIS)

    Maher, R.; Shafranek, L.F.; Stevens, W.R. III.

    1983-01-01

    The Department of Energy, in accord with recommendations from the Du Pont Company, has started construction of a Defense Waste Processing Facility (DWPF) at the Savannah River Plant. The facility should be completed by the end of 1988, and full-scale operation should begin in 1990. This facility will immobilize in borosilicate glass the large quantity of high-level radioactive waste now stored at the plant plus the waste to be generated from continued chemical reprocessing operations. The existing wastes at the Savannah River Plant will be completely converted by about 2010. 21 figures

  7. Solidification of TRU wastes in a ceramic matrix

    International Nuclear Information System (INIS)

    Loida, A.; Schubert, G.

    1991-01-01

    Aluminumsilicate based ceramic materials have been evaluated as an alternative waste form for the incorporation of TRU wastes. These waste forms are free of water and - cannot generate hydrogen radiolyticly, - they show good compatibility between the compounds of the waste and the matrix, - they are resistent against aqueous solutions, heat and radiation. R and D-work has been performed to demonstrate the suitability of this waste form for the immobilization of TRU-wastes. Four kinds of original TRU-waste streams and a mixture of all of them have been immobilized by ceramization, using glove box and remote operation technique as well. Clay minerals, (kaolinite, bentonite) and reactive corundum were selected as ceramic raw materials (KAB 78) in an appropriate ratio yielding 78 wt% Al 2 O 3 and 22 wt%SiO 2 . The main process steps are (i) pretreatment of the liquid waste (concentration, denitration, neutralization, solid- liquid separation), (ii) mixing with ceramic raw materials and forming, (iii) heat treatment with T max. of 1300 0 C for 15 minutes. The waste load of the ceramic matrix has been increased gradually from 20 to 50, in some cases to 60 wt.%

  8. Politics of nuclear waste

    International Nuclear Information System (INIS)

    Colglazier, E.W. Jr.

    1982-01-01

    In November of 1979, the Program in Science, Technology and Humanism and the Energy Committee of the Aspen Institute organized a conference on resolving the social, political, and institutional conflicts over the permanent siting of radioactive wastes. This book was written as a result of this conference. The chapters provide a comprehensive and up-to-date overview of the governance issues connected with radioactive waste management as well as a sampling of the diverse views of the interested parties. Chapter 1 looks in depth of radioactive waste management in the United States, with special emphasis on the events of the Carter Administration as well as on the issues with which the Reagen administration must deal. Chapter 2 compares waste management policies and programs among the industralized countries. Chapter 3 examines the factional controversies in the last administration and Congress over nuclear waste issues. Chapter 4 examines the complex legal questions involved in the federal-state conflicts over nuclear waste management. Chapter 5 examines the concept of consultation and concurrence from the perspectives of a host state that is a candidate for a repository and an interested state that has special concerns regarding the demonstration of nuclear waste disposal technology. Chapter 6 examines US and European perspectives concerning public participation in nuclear waste management. Chapter 7 discusses propaganda in the issues. The epilogue attempts to assess the prospects for consensus in the United States on national policies for radioactive waste management. All of the chapter in this book should be interpreted as personal assessments

  9. Politics of nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Colglazier, E.W. Jr. (eds.)

    1982-01-01

    In November of 1979, the Program in Science, Technology and Humanism and the Energy Committee of the Aspen Institute organized a conference on resolving the social, political, and institutional conflicts over the permanent siting of radioactive wastes. This book was written as a result of this conference. The chapters provide a comprehensive and up-to-date overview of the governance issues connected with radioactive waste management as well as a sampling of the diverse views of the interested parties. Chapter 1 looks in depth of radioactive waste management in the United States, with special emphasis on the events of the Carter Administration as well as on the issues with which the Reagen administration must deal. Chapter 2 compares waste management policies and programs among the industralized countries. Chapter 3 examines the factional controversies in the last administration and Congress over nuclear waste issues. Chapter 4 examines the complex legal questions involved in the federal-state conflicts over nuclear waste management. Chapter 5 examines the concept of consultation and concurrence from the perspectives of a host state that is a candidate for a repository and an interested state that has special concerns regarding the demonstration of nuclear waste disposal technology. Chapter 6 examines US and European perspectives concerning public participation in nuclear waste management. Chapter 7 discusses propaganda in the issues. The epilogue attempts to assess the prospects for consensus in the United States on national policies for radioactive waste management. All of the chapter in this book should be interpreted as personal assessments. (DP)

  10. Method of processing concentrated liquid waste in nuclear power plant

    International Nuclear Information System (INIS)

    Hasegawa, Kazuyuki; Kitsukawa, Ryozo; Ohashi, Satoru.

    1988-01-01

    Purpose: To reduce the oxidizable material in the concentrated liquid wastes discharged from nuclear power plants. Constitution: Nitrate bacteria are added to liquid wastes in a storage tank for temporarily storing concentrated liquid wastes or relevant facilities thereof. That is, nitrites as the oxidizable material contained in the concentrated liquid wastes are converted into nitrate non-deleterious to solidification by utilizing biological reaction of nitrate bacteria. For making the conversion more effectively, required time for the biological reaction of the nitrate bacteria is maintained from the injection of nitrate bacteria to solidification, thereby providing advantageous conditions for the propagation of the nitrate bacteria. In this way, there is no problem for the increase of the volume of the powdery wastes formed by the addition of inhibitor for the effect of oxidizable material. Further, heating upon solidification which is indispensable so far is no more necessary to simplify the facility and the operation. Furthermore, the solidification inhibiting material can be reduced stably and reliably under the same operation conditions even if the composition of the liquid wastes is charged or varied. (Kamimura, M.)

  11. Analysis of some nuclear waste management options. Volume II. Appendices

    International Nuclear Information System (INIS)

    Berman, L.E.; Ensminger, D.A.; Giuffre, M.S.; Koplik, C.M.; Oston, S.G.; Pollak, G.D.; Ross, B.I.

    1978-01-01

    This report describes risk analyses performed on that portion of a nuclear fuel cycle which begins following solidification of high-level waste. Risks associated with handling, interim storage and transportation of the waste are assessed, as well as the long term implications of disposal in deep mined cavities. The risk is expressed in terms of expected dose to the general population and peak dose to individuals in the population. This volume consists of appendices which provide technical details of the work performed

  12. Analysis of some nuclear waste management options. Volume II. Appendices

    Energy Technology Data Exchange (ETDEWEB)

    Berman, L.E.; Ensminger, D.A.; Giuffre, M.S.; Koplik, C.M.; Oston, S.G.; Pollak, G.D.; Ross, B.I.

    1978-10-10

    This report describes risk analyses performed on that portion of a nuclear fuel cycle which begins following solidification of high-level waste. Risks associated with handling, interim storage and transportation of the waste are assessed, as well as the long term implications of disposal in deep mined cavities. The risk is expressed in terms of expected dose to the general population and peak dose to individuals in the population. This volume consists of appendices which provide technical details of the work performed.

  13. Transmuting nuclear waste

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    With the problems of disposing of nuclear waste material increasingly the cause for widespread concern, attention is turning to possible new techniques for handling discarded radioactive material and even putting it to good use

  14. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Merrett, G.J.; Gillespie, P.A.

    1983-07-01

    This report discusses events and processes that could adversely affect the long-term stability of a nuclear fuel waste disposal vault or the regions of the geosphere and the biosphere to which radionuclides might migrate from such a vault

  15. Nuclear Waste and Ethics

    Energy Technology Data Exchange (ETDEWEB)

    Damveld, Herman [Groningen (Netherlands)

    2003-10-01

    In the past years in almost all conferences on storage of nuclear waste, ethics has been considered as an important theme. But what is ethics? We will first give a sketch of this branch of philosophy. We will then give a short explanation of the three principal ethical theories. In the discussion about storage of nuclear waste, the ethical theory of utilitarianism is often implicitly invoked. In this system future generations weigh less heavily than the present generation, so that people of the future are not considered as much as those now living. We reject this form of reasoning. The discussion about nuclear waste is also sometimes pursued from ethical points of departure such as equality and justice. But many loose ends remain in these arguments, which gives rise to the question of whether the production and storage of nuclear waste is responsible.

  16. Nuclear Waste and Ethics

    International Nuclear Information System (INIS)

    Damveld, Herman

    2003-01-01

    In the past years in almost all conferences on storage of nuclear waste, ethics has been considered as an important theme. But what is ethics? We will first give a sketch of this branch of philosophy. We will then give a short explanation of the three principal ethical theories. In the discussion about storage of nuclear waste, the ethical theory of utilitarianism is often implicitly invoked. In this system future generations weigh less heavily than the present generation, so that people of the future are not considered as much as those now living. We reject this form of reasoning. The discussion about nuclear waste is also sometimes pursued from ethical points of departure such as equality and justice. But many loose ends remain in these arguments, which gives rise to the question of whether the production and storage of nuclear waste is responsible

  17. Nuclear Waste Fund management

    International Nuclear Information System (INIS)

    Rosselli, R.

    1984-01-01

    The Nuclear Waste Policy Act of 1982 (NWPA) established two separate special bank accounts: the Nuclear Waste Fund (NWF) was established to finance all of the Federal Government activities associated with the disposal of High-Level Waste (HLW) or Spent Nuclear Fuel (SNF). The Interim Storage Fund (ISF) is the financial mechanism for the provision of Federal Interim Storage capacity, not to exceed 1900 metric tons of SNF at civilian power reactors. The management of these funds is discussed. Since the two funds are identical in features and the ISF has not yet been activated, the author's remarks are confined to the Nuclear Waste Fund. Three points discussed include legislative features, current status, and planned activities

  18. Transmuting nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1992-04-15

    With the problems of disposing of nuclear waste material increasingly the cause for widespread concern, attention is turning to possible new techniques for handling discarded radioactive material and even putting it to good use.

  19. SPECIFIC FEATURES OF OLIGOMERIC PRODUCT SOLIDIFICATION FROM POLYURETHANE WASTES AND THEIR PRACTICAL APPLICATION

    OpenAIRE

    V. Belyatsky; Yu. Kryvogus

    2012-01-01

    The paper considers a possibility to use secondary polyurethane obtained by  thermal depolymerization of wastes on the basis of cross-linked polyurethane (polyurethane adduct) and isocyanate. An effect of density dependence of the obtained polyurethane samples on nature and quantity of solvent has been revealed and it is significantly observed while using low-boiling solvents. The influence of adduct/solidification agent ratio on mechanical hardness of the obtained samples has been studied in...

  20. Nuclear waste solutions

    Science.gov (United States)

    Walker, Darrel D.; Ebra, Martha A.

    1987-01-01

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

  1. Nuclear waste for NT

    International Nuclear Information System (INIS)

    Nelson, Brendan

    2005-01-01

    The Northern Territory may be powerless to block the dumping of low-level nuclear waste in the Territory under legislation introduced into Parliament by Minister for Education Science and Training, Dr Brendan Nelson, in October. Despite strong opposition to the dumping of nuclear waste in the NT, the Australian Government will be able to send waste to one of the three nominated Commonwealth-owned Defence sites within the NT under the Commonwealth Radioactive Waste Management Bill 2005 and the Commonwealth Radioactive Waste Management (Related Amendment) Bill 2005. The Bills veto recently drafted NT legislation designed to scuttle the plans. Low-level nuclear waste is stored at more than 100 sites around Australia, including hospitals, factories, universities and defence facilities. Medical isotopes produced at Lucas Heights and provided for medical procedures are the source of much of this waste, including some 16 cubic metres currently held at Darwin Hospital. Dr Nelson stressed that the Government would take all die necessary steps to comply with safety and regulatory precautions, including handling waste in line with relevant environmental, nuclear safety and proliferation safeguards

  2. High-level waste solidification - why we chose glass

    International Nuclear Information System (INIS)

    Grover, J.R.

    1979-05-01

    This paper considers the desirable properties and factors to be assessed in the selection of a solidified waste product, surveys the possible product options and then analyses in detail their suitability in meeting the criteria. (author)

  3. Development of a geopolymer solidification method for radioactive wastes by compression molding and heat curing

    International Nuclear Information System (INIS)

    Shimoda, Chiaki; Matsuyama, Kanae; Okabe, Hirofumi; Kaneko, Masaaki; Miyamoto, Shinya

    2017-01-01

    Geopolymer solidification is a good method for managing waste because of it is inexpensive as compared with vitrification and has a reduced risk of hydrogen generation. In general, when geopolymers are made, water is added to the geopolymer raw materials, and then the slurry is mixed, poured into a mold, and cured. However, it is difficult to control the reaction because, depending on the types of materials, the viscosity can immediately increase after mixing. Slurries of geopolymers easily attach to the agitating wing of the mixer and easily clog the plumbing during transportation. Moreover, during long-term storage of solidified wastes containing concentrated radionuclides in a sealed container without vents, the hydrogen concentration in the container increases over time. Therefore, a simple method using as little water as possible is needed. In this work, geopolymer solidification by compression molding was studied. As compared with the usual methods, it provides a simple and stable method for preparing waste for long-term storage. From investigations performed before and after solidification by compression molding, it was shown that the crystal structure changed. From this result, it was concluded that the geopolymer reaction proceeded during compression molding. This method (1) reduces the energy needed for drying, (2) has good workability, (3) reduces the overall volume, and (4) reduces hydrogen generation. (author)

  4. OVERVIEW OF THE HISTORY, PRESENT STATUS, AND FUTURE DIRECTION OF SOLIDIFICATION/STABILIZATION TECHNOLOGIES FOR HAZARDOUS WASTE TREATMENT

    Science.gov (United States)

    Solidification/stabilization (S/S) technology processes are currently being utilized in the United States to treat inorganic and organic hazardous waste and radioactive waste. These wastes are generated from operating industry or have resulted from the uncontrolled management of ...

  5. High level nuclear wastes

    International Nuclear Information System (INIS)

    Lopez Perez, B.

    1987-01-01

    The transformations involved in the nuclear fuels during the burn-up at the power nuclear reactors for burn-up levels of 33.000 MWd/th are considered. Graphs and data on the radioactivity variation with the cooling time and heat power of the irradiated fuel are presented. Likewise, the cycle of the fuel in light water reactors is presented and the alternatives for the nuclear waste management are discussed. A brief description of the management of the spent fuel as a high level nuclear waste is shown, explaining the reprocessing and giving data about the fission products and their radioactivities, which must be considered on the vitrification processes. On the final storage of the nuclear waste into depth geological burials, both alternatives are coincident. The countries supporting the reprocessing are indicated and the Spanish programm defined in the Plan Energetico Nacional (PEN) is shortly reviewed. (author) 8 figs., 4 tabs

  6. U.S. Department of Energy's 'initiatives for proliferation prevention' program: solidification technologies for radioactive waste treatment in Russia - 16037

    International Nuclear Information System (INIS)

    Pokhitonov, Yuri; Kelley, Dennis

    2009-01-01

    Large amounts of liquid radioactive waste have existed in the U.S. and Russia since the 1950's as a result of the Cold War. Comprehensive action to treat and dispose of waste products has been lacking due to insufficient funding, ineffective technologies or no proven technologies, low priority by governments among others. Today the U.S. and Russian governments seek new, more reliable methods to treat liquid waste, in particular the legacy waste streams. A primary objective of waste generators and regulators is to find economical and proven technologies that can provide long-term stability for repository storage. In 2001, the V.G. Khlopin Radium Institute (Khlopin), St. Petersburg, Russia, and Pacific Nuclear Solutions (PNS), Indianapolis, Indiana, began extensive research and test programs to determine the validity of polymer technology for the absorption and immobilization of standard and complex waste streams. Over 60 liquid compositions have been tested including extensive irradiation tests to verify polymer stability and possible degradation. With conclusive scientific evidence of the polymer's effectiveness in treating liquid waste, both parties have decided to enter the Russian market and offer the solidification technology to nuclear sites for waste treatment and disposal. In conjunction with these efforts, the U.S. Department of Energy (DOE) will join Khlopin and PNS to explore opportunities for direct application of the polymers at predetermined sites and to conduct research for new product development. Under DOE's 'Initiatives for Proliferation Prevention' (IPP) program, funding will be provided to the Russian participants over a three year period to implement the program plan. This paper will present updated details of U.S. DOE's IPP program, the project structure and its objectives both short and long-term, polymer tests and applications for LLW, ILW and HLW, and new product development initiatives. (authors)

  7. Nuclear waste: good news

    International Nuclear Information System (INIS)

    Gay, Michel

    2014-01-01

    The author states that the problem of nuclear wastes is solved. He states that 90 per cent of radioactive wastes are now permanently managed and that technical solutions for deep geological storage and for transmutation will soon solve the problem for the remaining 10 pc. He states that geological storage will be funded (it is included in electricity price). He denounces why these facts which he consider as good news, do not prevail. He proposes several documents in appendix: a text explaining the nuclear fuel cycle in France, and an extract of a report made by the national inventory of radioactive materials and wastes

  8. Problems of solidificated radioactive wastes burial into deep geological structures

    International Nuclear Information System (INIS)

    Kedrovskij, O.L.; Leonov, E.A.; Romadin, N.M.; Shishcits, I.Yu.

    1981-01-01

    Perspectives are noted of the radioactive wastes burial into deep geopogical structures. For these purposes it has been proposed to investigate severap types of rocks, which do not have intensive gas-generation when beeng heated; salt deposits and clays. Basing on the results of calculations it has been shown that the dimentions of zones of substantial deformations in the case of the high-level radioactive wastes burial to not exceed several hundreds of meters. Conclusion is made that in the case of choosing the proper geotogicat structure for burial and ir the case of inclusion in the structure of the burial site a zone of sanitary alienation, it is possible to isolate wastes safely for all the period of preservation. Preliminary demands have been formulated to geological structures and underground burial sites. As main tasks for optimizatiop of burial sited are considered: determination of necessary types, number and reliability of barriers which ensure isolation of wastes; to make prognoses of the stressed and deformed state of a geological massif on the influence of thermal field; investigation in changes of chemical and physical properties of rocks under heat, radiative and chemical influence; estimation of possible diffusion of radioactivity in a mountin massif; development of a rational mining-thechnological schemes of the burual of wastes of different types. A row of tasks in the farmeworks of this probtem are sotved successfutty. Some resutts are given of the theoretical investigations in determination of zones of distructions of rocks because of heat-load [ru

  9. Estimation of potential ecological hazard of solidificated waste disposal

    International Nuclear Information System (INIS)

    Krylova, N.V.

    1980-01-01

    The results of estimation of potential ecological hazard of vitrificated high-level radioactive wastes resulted from spent fuel reprocessing of LWR connected with a hypothetic storage damage being occurred in the 5O0-6000-year geologic period are presented. The total volume of the vitrificated wastes in the storage used for calculations is 12000 blocks. The data on vitrificated block radioactivity depending on the time after fuel regeneration, the density of the uniform distribution of vitrificated wastes over the earth surface, as well as the results of estimation of the man external and internal exposures due to radionuclide escape into the biosphere are given in tables. It is shown that the main hazard is caused by external irradiation. The inhalation dose may be significant for man, though the hazard due to radionuclide intake by ingestion is less

  10. Method for solidification of radioactive iodine-containing solid wastes

    International Nuclear Information System (INIS)

    Ozawa, Yoshihiro; Funabashi, Kiyomi; Uetake, Naoto.

    1987-01-01

    Purpose: To process radioactive iodine containing solid wastes as non-leaching solidified wastes with no risk of iodine release. Method: It has been known for the thermal stability of CuI, PbI 2 or adsorbents containing the same that they do not release iodine in an inert gas atmosphere or in a reducing atmosphere at a temperature lower than 480 deg C. In view of the above, adsorbents containing iodine in the chemical form of CuI or PbI 2 , or CuI or powdery PbI 2 per se are sealed and solidified into low melting glass at a temperature of lower than 480 deg C at which no iodine release occurs in a non-oxidative atmosphere. Since the products are vitrified wastes, they scarcely show leaching property and are excellent in durability and stability. (Takahashi, M.)

  11. Method for solidification and disposal of radioactive pellet waste

    International Nuclear Information System (INIS)

    Yasumura, Keijiro; Matsuura, Hiroyuki.

    1975-01-01

    Object: To form radioactive waste into pellet, which is impregnated with plastic monomer for polymerization, and then packed into a drum can to have gaps between composites filled with cement, mortar, and molten asphalt, thus increasing water resistance and strength. Structure: Radioactive powdery bodies discharged from a thin film scaraping drier are formed into pellets in the desired shape. The thus pelletized radioactive solid waste is impregnated with a fluid plastic monomer such as styrene monomer and methacrylacidmethyl, and a polymerization accelerator is added thereto for polymerization. As a consequence, a composite pellet of powdery solid waste and plastic may be obtained. This is packed into the drum can container, into which cement paste, cement mortar or molten asphalt are put to fill the space between the plastic pellet composites, thus obtaining a solidified body integral with the drum can. (Taniai, N.)

  12. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    1982-01-01

    This film for a general audience deals with nuclear fuel waste management in Canada, where research is concentrating on land based geologic disposal of wastes rather than on reprocessing of fuel. The waste management programme is based on cooperation of the AECL, various universities and Ontario Hydro. Findings of research institutes in other countries are taken into account as well. The long-term effects of buried radioactive wastes on humans (ground water, food chain etc.) are carefully studied with the help of computer models. Animated sequences illustrate the behaviour of radionuclides and explain the idea of a multiple barrier system to minimize the danger of radiation hazards

  13. Nuclear waste management news

    International Nuclear Information System (INIS)

    Stoeber, H.

    1987-01-01

    In view of the fact that nuclear waste management is an important factor determining the future perspectives of the peaceful uses of nuclear energy, it seems suitable to offer those who are interested in this matter a source of well-founded, concise information. This first newsletter will be followed by others at irregular intervals, reviewing the latest developments and the state of the art in West Germany and abroad. The information presented in this issue reports the state of the art of nuclear waste management in West Germany and R and D activities and programmes, refers to conferences or public statements, and reviews international relations and activities abroad. (orig.) [de

  14. Nuclear Waste Fund management

    International Nuclear Information System (INIS)

    Mills, L.

    1984-01-01

    The Nuclear Waste Policy Acts requires that DOE enter into contracts with nuclear utilities and others to accept their nuclear wastes at some unspecified date, at some unspecified rate, hopefully starting in 1998. Contracts between DOE and the states, and with civilian and other government agencies must be sufficiently detailed to secure competitive bids on definable chunks of work at a fixed-cost basis with incentives. The need is stressed for a strong central program for the selection of contractors on the basis of competitive bidding on a fixed price basis to perform the task with defined deliverables

  15. Concentration and solidification of liquid radioactive wastes. Laboratory studies

    International Nuclear Information System (INIS)

    Nuche Vazquez, F.; Lora Soria, F. de

    1969-01-01

    Bench scale runs on concentration of intermediate level radioactive wastes, and incorporation of the concentrates in asphalt, are described. The feasibility of the process has been demonstrated, with a maximum incorporation of 60 percent of salts into the asphaltic matrix and a volume reduction factor of 10. (Author) 14 refs

  16. Nuclear waste in Seibersdorf

    International Nuclear Information System (INIS)

    Anon.

    1988-01-01

    Forschungszentrum Seibersdorf (short: Seibersdorf) is the company operating the research reactor ASTRA. A controversy arose, initied by the Greens and some newspapers on the fact that the waste conditioning plant in Seibersdorf treated not only Austrian waste (from hospitals etc.) but also a large quantity of ion exchange resins from the Caorso nuclear power station, against payment. The author argues that it is untenable that an Austrian institution (peaceful use of nuclear energy in Austria being abandoned by a referendum) should support nuclear power abroad. There is also a short survey on nuclear waste conditioning and an account of an exchange of letters, between the Seibersdorf and the Ecology Institute on the claim of being an 'independent measuring institution' of food, soil, etc. samples. The author argues that the Ecology Institute is the sole independent institution in Austria because it is part of the ecology- and antinuclear movement, whereas Seibersdorf is dependent on the state. (qui)

  17. Nuclear waste - a fresh perspective

    International Nuclear Information System (INIS)

    Tammemagi, H.Y.

    1996-01-01

    Rather than looking at the nuclear waste problem in isolation, it should be viewed in the broader context of how society disposes of all of its wastes. A comparison of radioactive and non-radioactive wastes shows, contrary to popular perception, that the properties of these two waste types are actually very similar. However, the methods of regulation and management of the two waste types are very different. It is time that these differences were reconciled - both the nuclear and the non-nuclear waste industries have a lot to gain. There are three main categories of (non-nuclear) waste: municipal wastes, hazardous wastes, and industrial wastes. Rather than treating each of these waste types in separate, isolated compartments, there should be an integration of the principles and regulations involved in their management. The non-nuclear waste industry has much to learn from the nuclear approach

  18. Processing of nuclear waste

    International Nuclear Information System (INIS)

    Hennelly, E.J.

    1981-01-01

    The processing of nuclear waste to transform the liquid waste from fuel reprocessing activities is well defined. Most solid waste forms, if they are cooled and contain diluted waste, are compatible with many permanent storage environments. The public acceptance of methods for disposal is being delayed in the US because of the alternatives studies of waste forms and repositories now under way that give the impression of indecision and difficulty for the disposal of HLW. Conservative programs that dilute and cool solid waste are under way in France and Sweden and demonstrate that a solution to the problem is available now. Research and development should be directed toward improving selected methods rather than seeking a best method, which at best, may always be illusory

  19. High-level waste solidification: why we chose glass

    International Nuclear Information System (INIS)

    Grover, J.R.

    1980-01-01

    This paper considers the desirable properties and factors to be assessed in the selection of a solidified waste product, surveys the possible product options and then analyzes in detail their suitability in meeting the criteria. It concludes that glasses are currently the preferred choice for the following reasons: their ability to fix the full spectrum of elements contained in the waste; their tolerance of the composition variations that will occur on a day to day basis in practice; their relatively low formation temperatures that lead to simpler and hence safer processing; their radiation stability; and their adequate leach rates. Suitable compositions are available for the wastes that will arise in the UK and techniques are available for manufacture on a production scale. Lower leach rates might be obtained by choosing glasses with higher formation temperatures or ceramics. However, these latter generally also have higher formation temperatures, have less tolerance for composition variations and their radiation stability is unproven. Supercalcines and synthetic rocks (SYNROC) may eventually be demonstrated to have some advantageous properties, but present indications are that these could be major disadvantages which more than offset any gains. Other advanced concepts (for example, the dispersion of glass beads in a metal matrix) have lower leach rates, but lead to additional complexity in manufacture

  20. Ordinary Portland Cement matrix for solidification of cellulosic protective clothes hazardous wastes

    International Nuclear Information System (INIS)

    Shatta, H.A.; Saleh, H.M.

    2006-01-01

    The used cellulosic protective clothes constitutes considerable fraction of the hazardous and radioactive wastes accumulated during the practical daily life. The direct solidification of these wastes with ordinary Portland cement resulted in waste forms having undesired characters, therefore, it is recommended to immobilize the secondary waste solutions coming from the oxidative degradation of the used protective clothes waste simulates rather than direct imbedding. IR analyses, X-ray diffraction and thermal characteristics for products of both direct encapsulation of the waste and the cementation of its degradation products were performed to evaluate the properties of the final waste cemented form before their disposal. Based on the results reached from X-ray diffraction, IR spectrograms and thermal analyses reports, it could be stated that no detectable changes in hydration and curing coarse of ordinary Portland cement when mixing the residual secondary waste solution resulting from the oxidative degradation of the used protective clothes waste simulate compared with mixing cement with water and in reverse with imbedding the unprocessed waste in cement matrix

  1. Mixed waste solidification testing on polymer and cement-based waste forms in support of Hanford's WRAP 2A facility

    International Nuclear Information System (INIS)

    Burbank, D.A. Jr.; Weingardt, K.M.

    1993-10-01

    A testing program has been conducted by the Westinghouse Hanford Company to confirm the baseline waste form selection for use in Waste Receiving and Processing (WRAP) Module 2A. WRAP Module 2A will provide treatment required to properly dispose of containerized contact-handled, mixed low-level waste at the US Department of Energy Hanford Site in south-central Washington State. Solidification/stabilization has been chosen as the appropriate treatment for this waste. This work is intended to test cement-based, thermosetting polymer, and thermoplastic polymer solidification media to substantiate the technology approach for WRAP Module 2A. Screening tests were performed using the major chemical constituent of each waste type to measure the gross compatibility with the immobilization media and to determine formulations for more detailed testing. Surrogate materials representing each of the eight waste types were prepared in the laboratory. These surrogates were then solidified with the selected immobilization media and subjected to a battery of standard performance tests. Detailed discussion of the laboratory work and results are contained in this report

  2. Development and evaluation of polyethylene as solidification agent for low-level waste

    International Nuclear Information System (INIS)

    Franz, E.M.; Colombo, P.

    1986-09-01

    A polyethylene solidification process, using an extrusion system, has been developed for the immobilization of dry wastes resulting from volume reduction technologies. Ease of processibility and high packing efficiencies were obtained through the use of low-density polyethylene (0.917 to 0.924 g/cm 3 ) with melt indices from 2.0 to 55.0 g/10 min. Maximum waste loadings of 70 wt % sodium sulfate, 50 wt % boric acid, 40 wt % incinerator ash and 65 wt % ion exchnge were obtained. A series of tsts were conducted to assess the acceptability of polyethylene waste forms to meet the requirements of 10 CFR 61. Based on test results and process control considerations, optimal waste loadings of 70 wt % sodium sulfate, 50 wt % boric acid, 40 wt % incinerator ash and 30 wt % ion exchange resins are recommended

  3. Volume reduction and solidification of liquid and solid low-level radioactive waste

    International Nuclear Information System (INIS)

    May, J.R.

    1979-01-01

    This paper presents a brief background of the development of a method of radioactive waste volume reduction using a unique fluidized bed calciner/incinerator. The volume reduction system is capable of processing a variety of liquid chemical wastes, spent ion exchange resin beads, filter treatment sludges, contaminated lubricating oils, and miscellaneous combustible solids such as paper, rags, protective clothing, wood, etc. All of these wastes are processed in one chemical reaction vessel. Detailed process data is presented that shows the system is capable of reducing the total volume of disposable radioactive waste generated by light water reactors by a factor of 10. Equally important to reducing the volume of power reactor radwaste is the final form of the stored or disposable radwaste. This paper also presents process data related to a new radwaste solidification system, presently being developed, that is particularly suited for immobilizing the granular solids and ashes resulting from volume reduction by calcination and/or incineration

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1980-09-01

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

  5. Radioactive wastes of Nuclear Industry

    International Nuclear Information System (INIS)

    1995-01-01

    This conference studies the radioactive waste of nuclear industry. Nine articles and presentations are exposed here; the action of the direction of nuclear installations safety, the improvement of industrial proceedings to reduce the waste volume, the packaging of radioactive waste, the safety of radioactive waste disposal and environmental impact studies, a presentation of waste coming from nuclear power plants, the new waste management policy, the international panorama of radioactive waste management, the international transport of radioactive waste, finally an economic analysis of the treatment and ultimate storage of radioactive waste. (N.C.)

  6. Cement-Based Materials for Nuclear Waste Storage

    CERN Document Server

    Cau-di-Coumes, Céline; Frizon, Fabien; Lorente, Sylvie

    2013-01-01

    As the re-emergence of nuclear power as an acceptable energy source on an international basis continues, the need for safe and reliable ways to dispose of radioactive waste becomes ever more critical. The ultimate goal for designing a predisposal waste-management system depends on producing waste containers suitable for storage, transportation and permanent disposal. Cement-Based Materials for Nuclear-Waste Storage provides a roadmap for the use of cementation as an applied technique for the treatment of low- and intermediate-level radioactive wastes.Coverage includes, but is not limited to, a comparison of cementation with other solidification techniques, advantages of calcium-silicate cements over other materials and a discussion of the long-term suitability and safety of waste packages as well as cement barriers. This book also: Discusses the formulation and production of cement waste forms for storing radioactive material Assesses the potential of emerging binders to improve the conditioning of problemati...

  7. Swedish nuclear waste efforts

    International Nuclear Information System (INIS)

    Rydberg, J.

    1981-09-01

    After the introduction of a law prohibiting the start-up of any new nuclear power plant until the utility had shown that the waste produced by the plant could be taken care of in an absolutely safe way, the Swedish nuclear utilities in December 1976 embarked on the Nuclear Fuel Safety Project, which in November 1977 presented a first report, Handling of Spent Nuclear Fuel and Final Storage of Vitrified Waste (KBS-I), and in November 1978 a second report, Handling and Final Storage of Unreprocessed Spent Nuclear Fuel (KBS II). These summary reports were supported by 120 technical reports prepared by 450 experts. The project engaged 70 private and governmental institutions at a total cost of US $15 million. The KBS-I and KBS-II reports are summarized in this document, as are also continued waste research efforts carried out by KBS, SKBF, PRAV, ASEA and other Swedish organizations. The KBS reports describe all steps (except reprocessing) in handling chain from removal from a reactor of spent fuel elements until their radioactive waste products are finally disposed of, in canisters, in an underground granite depository. The KBS concept relies on engineered multibarrier systems in combination with final storage in thoroughly investigated stable geologic formations. This report also briefly describes other activities carried out by the nuclear industry, namely, the construction of a central storage facility for spent fuel elements (to be in operation by 1985), a repository for reactor waste (to be in operation by 1988), and an intermediate storage facility for vitrified high-level waste (to be in operation by 1990). The R and D activities are updated to September 1981

  8. Safeguards on nuclear waste

    International Nuclear Information System (INIS)

    Crawford, D.W.

    1995-01-01

    Safeguards and security policies within the Department of Energy (DOE) have been implemented in a graded fashion for the protection, control and accountability of nuclear materials. This graded philosophy has meant that safeguards on low-equity nuclear materials, typically considered of low diversion attractiveness such as waste, has been relegated to minimal controls. This philosophy has been and remains today an acceptable approach for the planning and implementation of safeguards on this material. Nuclear waste protection policy and guidance have been issued due to a lack of clear policy and guidance on the identification and implementation of safeguards controls on waste. However, there are issues related to safe-guarding waste that need to be clarified. These issues primarily stem from increased budgetary and resource pressures to remove materials from safeguards. Finally, there may be an unclear understanding, as to the scope and content of vulnerability assessments required prior to terminating safeguards on waste and other discardable materials and where the authority should lie within the Department for making decisions regarding safeguards termination. This paper examines these issues and the technical basis for Departmental policy for terminating safeguards on waste

  9. Managing the nation's nuclear waste. Overview: Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    1985-10-01

    Signed into law by the President on January 7, 1983, the Nuclear Waste Policy Act established a national policy for safely storing, transporting, and disposing of spent nuclear fuel and high-level radioactive waste. This overview presents the following information on the Nuclear Waste Policy Act: (1) background; (2) permanent repository; (3) siting guidelines and mission plan; (4) monitored retrievable storage; and (5) nuclear waste funds. (DT)

  10. Why partition nuclear waste

    International Nuclear Information System (INIS)

    Cohen, J.J.

    1976-01-01

    A cursory review of literature dealing with various separatory processes involved in the handling of high-level liquid nuclear waste discloses that, for the most part, discussion centers on separation procedures and methodology for handling the resulting fractions, particularly the actinide wastes. There appears to be relatively little discussion on the incentives or motivations for performing these separations in the first place. Discussion is often limited to the assumption that we must separate out ''long-term'' from our ''short-term'' management problems. This paper deals with that assumption and devotes primary attention to the question of ''why partition waste'' rather than the question of ''how to partition waste'' or ''what to do with the segregated waste.''

  11. Ten questions on nuclear wastes

    International Nuclear Information System (INIS)

    Guillaumont, R.; Bacher, P.

    2004-01-01

    The authors give explanations and answers to ten issues related to nuclear wastes: when a radioactive material becomes a waste, how radioactive wastes are classified and particularly nuclear wastes in France, what are the risks associated with radioactive wastes, whether the present management of radioactive wastes is well controlled in France, which wastes are raising actual problems and what are the solutions, whether amounts and radio-toxicity of wastes can be reduced, whether all long life radionuclides or part of them can be transmuted, whether geologic storage of final wastes is inescapable, whether radioactive material can be warehoused over long durations, and how the information on radioactive waste management is organised

  12. Method of producing solidification product of radioactive waste

    International Nuclear Information System (INIS)

    Masuda, Shunji; Iwami, Etsuji; Kadota, Keishi.

    1989-01-01

    Layers of thermosetting resin composition capable of curing at normal temperature are formed to a thickness of 2 to 5 mm at the bottom of a container. As the thermosetting resin composition capable of curing at normal temperature, there can be mentioned, for example, unsaturated polyester resin comprising a polymerizable monomer and an unsaturated polyester. After the layers are cured, a mixture of radioactive wastes and the thermosetting resin composition capable of curing at normal temperature is filled on the layer. After curing, thermosetting resin composition capable of curing at normal temperature is filled so as to fill gaps between the curing product and the container caused by curing shrinkage and at the upper surface of the curing products. After curing, plastic layers are formed at the surface. This can avoid residual bubbles in the layers or development of cracks. Further, leaching rate of Na ions is low and water proofness can be improved as well. (T.M.)

  13. Large-scale demonstration of waste solidification in saltstone

    International Nuclear Information System (INIS)

    McIntyre, P.F.; Oblath, S.B.; Wilhite, E.L.

    1988-05-01

    The saltstone lysimeters are a large scale demonstration of a disposal concept for decontaminated salt solution resulting from in-tank processing of defense waste. The lysimeter experiment has provided data on the leaching behavior of large saltstone monoliths under realistic field conditions. The results also will be used to compare the effect of capping the wasteform on contaminant release. Biweekly monitoring of sump leachate from three lysimeters has continued on a routine basis for approximately 3 years. An uncapped lysimeter has shown the highest levels of nitrate and 99 Tc release. Gravel and clay capped lysimeters have shown levels equivalent to or slightly higher than background rainwater levels. Mathematical model predictions have been compared to lysimeter results. The models will be applied to predict the impact of saltstone disposal on groundwater quality. 9 refs., 5 figs., 3 tabs

  14. Measurement and control of cement set times in waste solidification

    International Nuclear Information System (INIS)

    Stone, J.A.; d'Entremont, P.D.

    1976-09-01

    Fixation of radioactive waste in concrete was investigated on laboratory scale. Some cement formulations containing simulated or actual sludges from the Savannah River Plant had set times that would be too short for reliable handling in plant equipment. Set times could be controlled by use of excess water, but the concrete forms produced had inferior strength. A commercial organic retarder was found to be effective for increasing set times of cement-sludge formulations. However, the dosage of retarder required to control set times of high-alumina cement formulations was 1.0 to 1.5 wt percent of dry solids, which is 5 to 10 times the normal dosage for Portland cements. Data were obtained to predict the optimum content of retarder and water

  15. Attitudes to nuclear waste

    International Nuclear Information System (INIS)

    Sjoeberg, L.; Drottz-Sjoeberg, B.M.

    1993-08-01

    This is a study of risk perception and attitudes with regard to nuclear waste. Two data sets are reported. In the first set, data were obtained from a survey of the general population, using an extensive questionnaire. The second set constituted a follow-up 7 years later, with a limited number of questions. The data showed that people considered the topic of nuclear waste risks to be very important and that they were not convinced that the technological problems had been solved. Experts associated with government agencies were moderately trusted, while those employed by the nuclear industry were much distrusted by some respondents, and very much trusted by others. Moral obligations to future generations were stressed. A large portion (more than 50 per cent) of the variances in risk perception could be explained by attitude to nuclear power, general risk sensitivity and trust in expertise. Most background variables, except gender, had little influence on risk perception and attitudes. The follow-up study showed that the attitude to nuclear power had become more positive over time, but that people still doubted that the problems of nuclear waste disposal had been solved. 49 refs

  16. Solidification/stabilization of fly and bottom ash from medical waste incineration facility.

    Science.gov (United States)

    Anastasiadou, Kalliopi; Christopoulos, Konstantinos; Mousios, Epameinontas; Gidarakos, Evangelos

    2012-03-15

    In the present work, the stabilization/solidification of fly and bottom ash generated from incinerated hospital waste was studied. The objectives of the solidification/stabilization treatment were therefore to reduce the leachability of the heavy metals present in these materials so as to permit their disposal in a sanitary landfill requiring only a lower degree of environmental protection. Another objective of the applied treatment was to increase the mechanical characteristics of the bottom ash using different amounts of Ordinary Portland Cement (OPC) as a binder. The solidified matrix showed that the cement is able to immobilize the heavy metals found in fly and bottom ash. The TCLP leachates of the untreated fly ash contain high concentrations of Zn (13.2 mg/l) and Pb (5.21 mg/l), and lesser amounts of Cr, Fe, Ni, Cu, Cd and Ba. Cement-based solidification exhibited a compressive strength of 0.55-16.12 MPa. The strength decreased as the percentage of cement loading was reduced; the compressive strength was 2.52-12.7 MPa for 60% cement mixed with 40% fly ash and 6.62-16.12 MPa for a mixture of 60% cement and 40% bottom ash. The compressive strength reduced to 0.55-1.30 MPa when 30% cement was mixed with 70% fly ash, and to 0.90-7.95 MPa when 30% cement was mixed with 70% bottom ash, respectively. Copyright © 2011 Elsevier B.V. All rights reserved.

  17. Laboratory stabilization/solidification of surrogate and actual mixed-waste sludge in glass and grout

    International Nuclear Information System (INIS)

    Spence, R.D.; Gilliam, T.M.; Mattus, C.H.; Mattus, A.J.

    1998-01-01

    Grouting and vitrification are currently the most likely stabilization/solidification technologies for mixed wastes. Grouting has been used to stabilize and solidify hazardous and low-level waste for decades. Vitrification has long been developed as a high-level-waste alternative and has been under development recently as an alternative treatment technology for low-level mixed waste. Laboratory testing has been performed to develop grout and vitrification formulas for mixed-waste sludges currently stored in underground tanks at Oak Ridge National Laboratory (ORNL) and to compare these waste forms. Envelopes, or operating windows, for both grout and soda-lime-silica glass formulations for a surrogate sludge were developed. One formulation within each envelope was selected for testing the sensitivity of performance to variations (±10 wt%) in the waste form composition and variations in the surrogate sludge composition over the range previously characterized in the sludges. In addition, one sludge sample of an actual mixed-waste tank was obtained, a surrogate was developed for this sludge sample, and grout and glass samples were prepared and tested in the laboratory using both surrogate and the actual sludge. The sensitivity testing of a surrogate tank sludge in selected glass and grout formulations is discussed in this paper, along with the hot-cell testing of an actual tank sludge sample

  18. Performance of cement solidification with barium for high activity liquid waste including sulphate

    International Nuclear Information System (INIS)

    Waki, Toshikazu; Yamada, Motoyuki; Horikawa, Yoshihiko; Kaneko, Masaaki; Saso, Michitaka; Haruguchi, Yoshiko; Yamashita, Yu; Sakai, Hitoshi

    2009-01-01

    The target liquid waste to be solidified is generated from PWR primary loop spent resin treatment with sulphate acid, so, its main constituent is sodium sulphate and the activity of this liquid is relatively high. Waste form of this liquid waste is considered to be a candidate for the subsurface disposal. The disposed waste including sulphate is anticipated to rise a concentration of sulphate ion in the ground water around the disposal facility and it may cause degradation of materials such as cement and bentonite layer and comprise the disposal facility. There could be two approaches to avoid this problem, the strong design of the disposal facility and the minimization of sulphaste ion migration from the solidified waste. In this study, the latter approach was examined. In order to keep the low concentration of sulphate ion in the ground water, it is effective to make barium sulphate by adding barium compound into the liquid waste in solidification. However, adding equivalent amount of barium compound with sulphate ion causes difficulty of mixing, because production of barium sulphate causes high viscosity. In this study, mixing condition after and before adding cement into the liquid waste was estimated. The mixing condition was set with consideration to keep anion concentration low in the ground water and of mixing easily enough in practical operation. Long term leaching behavior of the simulated solidified waste was also analyzed by PHREEQC. And the concentration of the constitution affected to the disposal facility was estimated be low enough in the ground water. (author)

  19. Evaluation of concrete as a matrix for solidification of Savannah River Plant waste

    International Nuclear Information System (INIS)

    Stone, J.A.

    1978-01-01

    Some of the favorable and unfavorable characteristics of concrete as a matrix for solidification of SRP waste, as found in this study, are listed. Compressive strength and leachability of waste forms containing 90 Sr and alpha emitters are very good. The waste forms have reasonable long-term thermal stability up to 400 0 C, although water is evolved above 100 0 C. Long-term radiation stability of the solid, as measured by strength and leachability, is excellent. For the unfavorable characteristics, methods are available to overcome any problems these properties might cause. 137 Cs leachability can be reduced by additives such as zeolite. Steam generation can be reduced by an initial degassing step; however, radiolytic gassing may require further study. Set times can be retarded with additives. 10 figs

  20. A comparison of solidification media for the stabilization of low- level radioactive wastes

    International Nuclear Information System (INIS)

    Cowgill, M.G.

    1991-10-01

    When requirements exist to stabilize low-level radioactive waste (LLW) prior to disposal, efforts to achieve this stability often center on the mixing of the waste with a solidification medium. Although historically the medium of choice has been based on the use of portland cement as the binder material, several other options have been developed and subsequently implemented. These include thermoplastic polymers, thermosetting polymers and gypsum. No one medium has thus far been successful in providing stability to all forms of LLW. The characteristics and attributes of these different binder materials are reviewed and compared. The aspects examined include availability of information, limitations to use, sensitivity to process or waste chemistry changes, radionuclide retention ability, modeling of radionuclide release processes, ease and safety of use, and relative costs

  1. Public attitudes regarding nuclear wastes

    International Nuclear Information System (INIS)

    Rankin, W.L.

    1978-01-01

    This paper traces the history of public attitudes regarding nuclear waste issues. A majority of the public has recently developed the attitude that nuclear wastes are a serious problem, and a small percentage of the public opposes nuclear power mainly because of nuclear waste issues. However, a majority of the public has confidence in the ability of technologists to solve the problems associated with nuclear waste disposal. Finally, the attitudes of nuclear technologists regarding waste disposal differed greatly from the attitudes of other groups, especially environmentalists

  2. Solidification of high level liquid waste (HLLW) into ceramics by sintering process

    International Nuclear Information System (INIS)

    Masuda, Sumio; Oguino, Naohiko; Tsunoda, Naomi; O-oka, Kazuo; Ohta, Takao.

    1979-01-01

    One of the alternatives to vitrified solid which is acceptable and well characterized for storing radioactive HLLW with desirable long-term stability is ceramics. On the other hand, the solidification process of highly radioactive wastes should be simple and suitable for continuous production. On the above described basis, the authors have made preliminary study on the production of sintered ceramics by the addition of several oxides to HLLW. The simulated waste and additive oxides were pressed in a mold to make the preforms of 50 mm diameter and 10 to 15 mm thick. The preforms were then normally sintered at temperature from 1000 to 1400 deg C for 2 to 4 hours. The characterization of the sintered solids revealed the following facts. (1) X-ray diffraction analysis showed that the expected crystals were formed by normal-sintering as well as by hot-pressing. (2) The bulk density of the ceramics by normal-sintering was around 90 to 95% of the assumed theoretical values. (3) The leach-rate of the solids was affected by the bulk density. (4) Other properties of the solids, such as thermal expansion or thermal conductivity, are dominantly determined by those of main crystals in the solids. Sintering process is generally simple and productive as far as normal sintering is concerned. However, hot-pressing is an intermittent and time consuming process. From this fact, the authors intended to adopt the normal sintering process for the ceramic solidification of high level liquid wastes. (Wakatsuki, Y.)

  3. Waste management - nuclear style

    International Nuclear Information System (INIS)

    McCall, P.

    1977-01-01

    Possible ways of disposing of highly radioactive wastes arising from the United Kingdom nuclear industry are briefly reviewed: projecting into outer space, dumping in containers in the ocean, or storage on land. The problems in each case and, in particular, the risks of environmental contamination from marine or land disposal, are discussed. (U.K.)

  4. Nuclear waste repository siting

    International Nuclear Information System (INIS)

    Soloman, B.D.; Cameron, D.M.

    1987-01-01

    This paper discusses the geopolitics of nuclear waste disposal in the USA. Constitutional choice and social equity perspectives are used to argue for a more open and just repository siting program. The authors assert that every potential repository site inevitably contains geologic, environmental or other imperfections and that the political process is the correct one for determining sites selected

  5. Nuclear Waste Education Project

    International Nuclear Information System (INIS)

    1989-01-01

    In summary, both the Atlanta and Albuquerque pilot seminars achieved the Nuclear Waste Education Project's goal of informing citizens on both the substance and the process of nuclear waste policy so that they can better participate in future nuclear waste decisions. Nuclear waste issues are controversial, and the seminars exposed the nature of the controversy, and utilized the policy debates to create lively and provocative sessions. The format and content of any citizen education curriculum must be made to fit the particular goal that has been chosen. If the Department of Energy and the LWVEF decide to continue to foster an informed dialogue among presenters and participants, the principles of controversial issues education would serve this goal well. If, however, the Department of Energy and/or the LWVEF decide to go beyond imparting information and promoting a lively discussion of the issues, towards some kind of consensus-building process, it would be appropriate to integrate more interactive sessions into the format. As one evaluator wrote, ''In-depth participation in finding solutions or establishing policy -- small group discussion'' would have been preferable to the plenary sessions that mostly were in the form of lectures and expert panel discussion. The evaluator continued by saying, ''Since these [small group discussions] would require more time commitment, they might be part of follow-up workshops focused on particular topics.''

  6. Nuclear waste management

    International Nuclear Information System (INIS)

    Wicks, G.G.; Ross, W.A.

    1984-01-01

    Papers from the Second International Symposium on Ceramics in Nuclear Waste Management, held during the American Ceramic Society's 85th Annual Meeting, comprise this eighth volume in the Advances in Ceramics series. The 81 papers included in this volume were compiled by George G. Wicks, of Savannah River Lab, and Wayne A. Ross, of Battelle, Pacific Northwest Labs

  7. Nuclear fuel waste disposal

    International Nuclear Information System (INIS)

    Allan, C.J.

    1993-01-01

    The Canadian concept for nuclear fuel waste disposal is based on disposing of the waste in a vault excavated 500-1000 m deep in intrusive igneous rock of the Canadian Shield. The author believes that, if the concept is accepted following review by a federal environmental assessment panel (probably in 1995), then it is important that implementation should begin without delay. His reasons are listed under the following headings: Environmental leadership and reducing the burden on future generations; Fostering public confidence in nuclear energy; Forestalling inaction by default; Preserving the knowledge base. Although disposal of reprocessing waste is a possible future alternative option, it will still almost certainly include a requirement for geologic disposal

  8. Nuclear waste - perceptions and realities

    International Nuclear Information System (INIS)

    Wilkinson, D.

    1984-01-01

    This paper discusses the complex scientific, sociological, political and emotive aspects of nuclear waste. The public perception of the hazards and risks, to present and future generations, in the management of nuclear wastes are highlighted. The cost of nuclear waste management to socially acceptable and technically achievable standards is discussed. (UK)

  9. Who wants nuclear waste

    International Nuclear Information System (INIS)

    Fernie, John; Openshaw, Stanley

    1986-01-01

    The criteria involved in selecting sites for disposal of low and short-lived intermediate-level radioactive wastes are explained. The wastes and the sources are identified and the current procedure for their disposal, at Drigg, next to the Sellafield reprocessing plant, is given. If alternative sites could be found for non-Sellafield-produced wastes the lifetime of the Drigg site could be extended. The sites chosen by NIREX (Nuclear Industry Radioactive Waste Executive) have to be cost effective. Indeed, those identified are conveniently situated and would not incur excessive transport costs. However, more remote sites may have to be chosen, even at greater transport cost, because of public protests. Even this may not be satisfactory because the transportation itself incurs risks. (UK)

  10. Development of recycling techniques for nuclear power plant decommissioning waste

    International Nuclear Information System (INIS)

    Ishikura, Takeshi; Oguri, Daiichiro; Abe, Seiji; Ohnishi, Kazuhiko

    2003-01-01

    Recycling of concrete and metal waste will provide solution to reduce waste volume, contributing to save the natural resources and to protect the environment. Nuclear Power Engineering Corporation has developed techniques of concrete and metal recycling for decommissioning waste of commercial nuclear power plants. A process of radioactive concrete usage for mortar solidification was seen to reduce concrete waste volume by 2/3. A concrete reclamation process for high quality aggregate was confirmed that the reclaimed aggregate concrete is equivalent to ordinary concrete. Its byproduct powder was seen to be utilized various usage. A process of waste metal casting to use radioactive metal as filler could substantially decrease the waste metal volume when thinner containers are applied. A pyro-metallurgical separation process was seen to decrease cobalt concentration by 1/100. Some of these techniques are finished of demonstration tests for future decommissioning activity. (author)

  11. SULFUR POLYMER STABILIZATION/SOLIDIFICATION (SPSS) TREATABILITY OF SIMULATED MIXED-WASTE MERCURY CONTAMINATED SLUDGE.

    Energy Technology Data Exchange (ETDEWEB)

    ADAMA, J.W.; BOWERMAN, B.S.; KALB, P.D.

    2002-10-01

    The Environmental Protection Agency (EPA) is currently seeking to validate technologies that can directly treat radioactively contaminated high mercury (Hg) subcategory wastes without removing the mercury from the waste. The Sulfur Polymer Stabilization/Solidification (SPSS) process developed at Brookhaven National Laboratory is one of several candidate technologies capable of successfully treating various Hg waste streams. To supplement previously supplied data on treatment of soils, EPA needs additional data concerning stabilization of high Hg subcategory waste sludges. To this end, a 5000 ppm sludge surrogate, containing approximately 50 wt% water, was successfully treated by pilot-scale SPSS processing. In two process runs, 85 and 95 wt% of water was recovered from the sludge during processing. At waste loadings of 30 wt% dry sludge, the treated waste form had no detectable mercury (<10 ppb) in TCLP leachates. Data gathered from the demonstration of treatment of this sludge will provide EPA with information to support revisions to current treatment requirements for high Hg subcategory wastes.

  12. SULFUR POLYMER STABILIZATION/SOLIDIFICATION (SPSS) TREATABILITY OF SIMULATED MIXED-WASTE MERCURY CONTAMINATED SLUDGE

    Energy Technology Data Exchange (ETDEWEB)

    Adams, J. W.; Bowerman, B. S.; Kalb, P. D.

    2002-02-25

    The Environmental Protection Agency (EPA) is currently evaluating alternative treatment standards for radioactively contaminated high mercury (Hg) subcategory wastes, which do not require the removal of mercury from the waste. The Sulfur Polymer Stabilization/Solidification (SPSS) process developed at Brookhaven National Laboratory is one of several candidate technologies capable of successfully treating various Hg waste streams. To supplement previously supplied data on treatment of soils, EPA needed additional data concerning stabilization of high Hg subcategory waste sludges. To this end, a 5000 ppm sludge surrogate, containing approximately 50 wt% water, was successfully treated by pilot-scale SPSS processing. In two process runs, 85 and 95 wt% of water was recovered from the sludge during processing. At waste loadings of 46 wt% (30 wt% dry) sludge, the treated waste form had no detectable mercury (<10 ppb) in TCLP leachates. Data gathered from the demonstration of treatment of this sludge will provide the EPA with information to support revisions to current treatment requirements for high Hg subcategory wastes.

  13. SULFUR POLYMER STABILIZATION/SOLIDIFICATION (SPSS) TREATABILITY OF SIMULATED MIXED-WASTE MERCURY CONTAMINATED SLUDGE

    International Nuclear Information System (INIS)

    ADAMA, J.W.; BOWERMAN, B.S.; KALB, P.D.

    2002-01-01

    The Environmental Protection Agency (EPA) is currently seeking to validate technologies that can directly treat radioactively contaminated high mercury (Hg) subcategory wastes without removing the mercury from the waste. The Sulfur Polymer Stabilization/Solidification (SPSS) process developed at Brookhaven National Laboratory is one of several candidate technologies capable of successfully treating various Hg waste streams. To supplement previously supplied data on treatment of soils, EPA needs additional data concerning stabilization of high Hg subcategory waste sludges. To this end, a 5000 ppm sludge surrogate, containing approximately 50 wt% water, was successfully treated by pilot-scale SPSS processing. In two process runs, 85 and 95 wt% of water was recovered from the sludge during processing. At waste loadings of 30 wt% dry sludge, the treated waste form had no detectable mercury (<10 ppb) in TCLP leachates. Data gathered from the demonstration of treatment of this sludge will provide EPA with information to support revisions to current treatment requirements for high Hg subcategory wastes

  14. SULFUR POLYMER STABILIZATION/SOLIDIFICATION (SPSS) TREATABILITY OF SIMULATED MIXED-WASTE MERCURY CONTAMINATED SLUDGE

    International Nuclear Information System (INIS)

    Adams, J. W.; Bowerman, B. S.; Kalb, P. D.

    2002-01-01

    The Environmental Protection Agency (EPA) is currently evaluating alternative treatment standards for radioactively contaminated high mercury (Hg) subcategory wastes, which do not require the removal of mercury from the waste. The Sulfur Polymer Stabilization/Solidification (SPSS) process developed at Brookhaven National Laboratory is one of several candidate technologies capable of successfully treating various Hg waste streams. To supplement previously supplied data on treatment of soils, EPA needed additional data concerning stabilization of high Hg subcategory waste sludges. To this end, a 5000 ppm sludge surrogate, containing approximately 50 wt% water, was successfully treated by pilot-scale SPSS processing. In two process runs, 85 and 95 wt% of water was recovered from the sludge during processing. At waste loadings of 46 wt% (30 wt% dry) sludge, the treated waste form had no detectable mercury (<10 ppb) in TCLP leachates. Data gathered from the demonstration of treatment of this sludge will provide the EPA with information to support revisions to current treatment requirements for high Hg subcategory wastes

  15. Commercial nuclear-waste management

    International Nuclear Information System (INIS)

    Andress, D.A.

    1981-04-01

    This report is primarily concerned with nuclear waste generated by commercial power operations. It is clear, however, that the total generation of commercial nuclear waste does not tell the whole story, there are sizeable stockpiles of defense nuclear wastes which will impact areas such as total nuclide exposure to the biosphere and the overall economics of waste disposal. The effects of these other nuclear waste streams can be factored in as exogenous inputs. Their generation is essentially independent of nuclear power operations. The objective of this report is to assess the real-world problems associated with nuclear waste management and to design the analytical framework, as appropriate, for handling nuclear waste management issues in the International Nuclear Model. As such, some issues that are not inherently quantifiable, such as the development of environmental Impact Statements to satisfy the National Environmental Protection Act requirements, are only briefly mentioned, if at all

  16. Nuclear waste. Last stop Siberia?

    International Nuclear Information System (INIS)

    Popova, L.

    2006-01-01

    Safe and environmentally sound management of nuclear waste and spent fuel is an unresolved problem of nuclear power. But unlike other nuclear nations, Russia has much more problems with nuclear waste. Russia inherited these problems from the military programs and decades of nuclear fuel cycle development. Nuclear waste continue to mount, while the government does not pay serious enough attention to the solution of the waste problem and considers to increase the capacity of nuclear power plants (NPPs). There are more than 1000 nuclear waste storages in Russia.1 More than 70 million tons of the solid waste has been accumulated by the year 2005, including 14 million tons of tails of the decommissioned uranium mine in the North Caucasus. President Putin said that ''infrastructure of the waste processing is extremely insufficient''. (orig.)

  17. Ceramics in nuclear waste management

    Energy Technology Data Exchange (ETDEWEB)

    Chikalla, T D; Mendel, J E [eds.

    1979-05-01

    Seventy-three papers are included, arranged under the following section headings: national programs for the disposal of radioactive wastes, waste from stability and characterization, glass processing, ceramic processing, ceramic and glass processing, leaching of waste materials, properties of nuclear waste forms, and immobilization of special radioactive wastes. Separate abstracts were prepared for all the papers. (DLC)

  18. Solidification of liquid concentrate and solid waste generated as by-products of the liquid radwaste treatment systems in light-water reactors

    International Nuclear Information System (INIS)

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

    1977-01-01

    The treatment of liquid concentrate and solid waste produced in light-water reactors as by-products of liquid radwaste treatment systems consists of five basic operations: waste collection, waste pretreatment, solidification agent handling, mixing/packaging (solidification) and waste package handling. This paper will concern itself primarily with the solidification operation, however, the other operations enumerated as well as the types of wastes treated and their origins will be briefly described, especially with regards to their effects on solidification. During solidification, liquid concentrate and solid wastes are incorporated with a solidification agent to form a monolithic, free-standing solid. The basic solidification agent types either currently used in the United States or proposed for use include absorbants, hydraulic cement, urea-formaldehyde, other polymer systems, and bitumen. The operation, formulations and limitations of these agents as used for radwaste solidification will be discussed. Properties relevant to the evaluation of solidified waste forms will be identified and relative comparisons made for wastes solidified by various processes

  19. Development of stable solidification methods for toxic lead oxide in radioactive wastes

    International Nuclear Information System (INIS)

    Hitoshi Mimura; Shingo Ikeda; Yuichi Niibori

    2009-01-01

    The objective of this study is to develop the advanced solidification methods for the toxic lead oxide contained in radioactive wastes and to examine their chemical durability in terms of leachability and surface alteration; the solidification characteristics and leachability for the following three kinds of solidified products immobilizing lead were examined, and the experimental results were summarized as follows. (a) Mineral solidified products: A-zeolite or fly ash (FA) was used as a binder, and NaAlO 2 and Na 2 SiO 3 were mixed as additives. The leachability of lead ions in pure water was considerably lowered by the heat treatment at higher temperature (1,000 degree C), and the concentration of lead ions leached was under criterion value of 0.3 mg/l. The products prepared by mixing A-zeolite and fly ash also had low leachability under 0.3 mg/l even in the saturated Ca(OH)2 solution. (b) Melted solidified products: A-zeolite or fly ash was used as a binder and glass-forming reagents of B 2 O 3 and NaH 2 PO 4 were used as additives. The XRD peaks assigned PbO were not observed in all products. The products for the mixtures of FA:NaH 2 PO 4 :PbO (2:2:1 and 3:1:1) had low leachability under criterion value in both leachants of deionized water and saturated Ca(OH) 2 solution. (c) Phosphate ceramics products: the chemically bonded phosphate ceramics were produced by using MgKPO 4 , MgHPO 4 , Zr(HPO 4 ) 2 , potassium iron phosphate and sodium iron phosphate, and FA was used as additives. In particular, by using MgHPO 4 , the leachability of the products was lowered less than 0.3 mg/l in both leachants. The phosphate ceramics products and melted solidified products are favorable as the waste solid forms immobilizing lead. In particular, novel ceramics products have advantages in the simple solidification procedure similarly to the cement products. As for mineral solidification, natural zeolites and FA as binder also useful from the viewpoint of cost efficiency

  20. 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.)

  1. Nuclear waste vs. democracy

    International Nuclear Information System (INIS)

    Treichel, J.

    1999-01-01

    In the United States the storage and disposal of high-level nuclear waste is a highly contentious issue because under current plans the public is subjected to unaccepted, involuntary risks. The proposed federal policy includes the forced siting of a repository and interim storage facilities in Nevada, and the transport of waste across the entire nation through large cities and within 2 mile of over 50 million people. At its destination in Nevada, the residents would face coexistence with a facility housing highly radioactive wastes that remain dangerous for many thousands of years. Scientific predictions about the performance and safety of these facilities is highly uncertain and the people foresee possibly catastrophic threats to their health, safety and economic well-being for generations to come. The public sees this currently proposed plan as one that seeks to maximise the profits of the commercial nuclear industry through imposing risk and sacrifice to communities who reap no benefit. And there is no evidence that this plan is actually a solution to the problem. The American public has never had the opportunity to participate in the nuclear waste debate and government plans are presented to people as being necessary and inevitable. To allow democracy into the decisions could be costly to the nuclear industry and it might thwart the government program, but that is the nature of democracy. If the utilities are established to provide a public service, and the government is founded on the principle of public representation, then the nuclear waste debate must conform to those requirements. What we see in this case is a continuing change of rule and law to accommodate a corporate power and the subrogation of national principle. The result of this situation has been that the public exercises its only option - which is obstructing the federal plan. Because the odds are so heavily stacked in favour of government and industry and average citizens have so little access

  2. Liquid low-level waste (LLLW) solidification at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Schultz, R.M.; Monk, T.H.; duMont, S.P.; Helms, R.E.; Keigan, M.V.; Morris, M.I.

    1987-01-01

    In general, the presentation describes the disposal of liquid, low-level (radioactive) waste (LLLW) by the hydrofracture process at Oak Ridge National Laboratory until 1984, when it was shut down due to regulatory concerns and operational anomalies. As a result of this, about 400,000 gallons of concentrated LLLW and 50,000 gallons of transuranic waste-bearing sludges have accumulated in the active, double-contained tank system which is reaching its operational capacity. A major initiative to develop an alternative means of LLLW treatment and disposal was begun about two years ago. This presentation summarizes the implementation strategy of the most likely process options. The strategy is being developed in two phases; a near-term flowsheet and a long-term or reference flowsheet. First, reliable and fully demonstrated commercial, cement solidification systems are being assessed for execution of an initial 50,000 gallon campaign in 1988. Second, development is under way to determine viable sludge separation, LLLW decontamination and solidification alternatives. A flowsheet analysis and cost study is being conducted by a consultant to ensure proper consideration of process developments at other sites. It is estimated that, depending upon funding requirements, it could take up to six years to implement the reference flowsheet

  3. Disposal of nuclear wastes

    International Nuclear Information System (INIS)

    Albrecht, E.; Kuehn, K.

    1977-01-01

    Final storage of nuclear wastes in the salt mine at Asse is described. Until the end of 1976, all in all 73,000 containers with slightly radioactive wastes were deposited there within the framework of a test programme - the Asse pit is a pilot plant. Final storage of medium active waste was started in 1972. So far, about 1,150 barrels with medium active waste were deposited. Storage techniques applied, radiation exposure of the personnel and experience gained so far are reported on in this context. Final storage at Asse of highly active wastes developing decay heat is still in a preparatory stage, as here radiation as well as heat problems have to be mastered. Technical mining activities for the recoverable storage of highly-active, heat-developing wastes in the form of ceramic glasses are still in a planning phase, whereas advance work, e.g. cutting storage chambers out of seams 775 m thick have already begun. (HPH) [de

  4. Nuclear criticality safety assessment of the Consolidated Edison Uranium-Solidification Program Facility

    International Nuclear Information System (INIS)

    Thomas, J.T.

    1984-01-01

    A nuclear criticality assessment of the Consolidated Edison Uranium-Solidification Program facility confirms that all operations involved in the process may be conducted with an acceptable margin of subcriticality. Normal operation presents no concern since subcriticality is maintained by design. Several recommendations are presented to prevent, or mitigate the consequences of, any abnormal events that might occur in the various portions of the process. These measures would also serve to reduce to a minimum the administrative controls required to prevent criticality

  5. Problems of nuclear waste

    International Nuclear Information System (INIS)

    Rodionov, D.

    1999-01-01

    An enormous stockpile of nuclear weapons was reduced during the Cold War as a result of frantic Soviet-US competition, accompanied by considerable radioactive pollution of the environment. This pollution was inevitable. Former adversaries began to sober only recently. As a result, areas of weapons complexes both in the USA (Hanford, Savannah, Oak Ridge) and in Russia (Chelyabinsk-65, Tomsk-7, Krasnoyarsk-25) look like battlefields of the Cold War. A Nuclear weapon-free world will only be achieved (if at all) after reaching changes in the principles that guide state policies and actions. A nuclear-waste-free world implies that the environment's radioactive pollution of a military nature would be eliminated and all potential dangers from civil nuclear energy prevented. This can be attained after solution of some economic, political and social problems

  6. Management of metal-bearing industrial solid waste by stabilization/solidification process

    Energy Technology Data Exchange (ETDEWEB)

    Sunitha, C.; Palanivelu, K. [Anna University, Chennai (India). Centre for Environmental Studies

    2005-07-01

    Metal-bearing sludge from an electroplating industry was immobilised by the solidification stabilisation treatment method. Reduction of the leachability of metals from the waste was studied in different combinations of waste and additives - cement, lime and fly ash. The study revealed that the optimum proportion for cement: metal hydroxide sludge: fly ash as 1:2:2 is the best. The encapsulation efficiency calculated for the metals such as Cu, Cr, Ni, Pb, and Zn was above 92%. The unconfined compressive strength (UCS) for the developed block was found to be 11.5 kg/cm{sup 2} after curing. The toxicity characteristic leach test (TCLP) test reveals that the heavy metal content in the leachate was well below the maximum permissible limit of WHO drinking water standard. 10 refs., 6 tabs.

  7. Nuclear waste vault sealing

    International Nuclear Information System (INIS)

    Gyenge, M.

    1980-01-01

    A nuclear waste vault must be designed and built to ensure adequate isolation of the nuclear wastes from human contact. Consequently, after a vault has been fully loaded, it must be adequately sealed off to prevent radionuclide migration which may be provided by circulating groundwater. Vault sealing entails four major aspects, i.e.: (a) vault grouting; (b) borehole sealing; (c) buffer packing; and (d) backfilling. Of particular concern in vault sealing are the physical and chemical properties of the sealing material, its long-term durability and stability, and the techniques used for its emplacement. Present sealing technology and sealing materials are reviewed in terms of the particular needs of vault sealing. Areas requiring research and development are indicated

  8. Nuclear wastes: research programs

    International Nuclear Information System (INIS)

    Anon.

    2003-01-01

    The management of long-living and high level radioactive wastes in France belongs to the framework of the December 30, 1991 law which defines three ways of research: the separation and transmutation of radionuclides, their reversible storage or disposal in deep geologic formations, and their processing and surface storage during long duration. Research works are done in partnership between public research and industrial organizations in many French and foreign laboratories. Twelve years after its enforcement, the impact of this law has overstepped the simple research framework and has led to a deep reflection of the society about the use of nuclear energy. This short paper presents the main results obtained so far in the three research ways, the general energy policy of the French government, the industrial progresses made in the framework of the 1991 law and the international context of the management of nuclear wastes. (J.S.)

  9. Glasses for the solidification of high-level radioactive waste: their behavior in the presence of water

    International Nuclear Information System (INIS)

    Grauer, R.

    1983-02-01

    Because of their amorphous structure, glasses are particularly suitable for the solidification of the mixture of high-level radioactive wastes resulting from reactor fuel reprocessing: they are not sensitive to variations in the compositions of waste oxides and are resistant to the damaging effects of radiation. The borosilicate glasses used for this purpose have been investigated for about 25 years, and waste vitrification techniques have been tested on a commercial scale. In view of possible accidents in a final waste repository, the chemical resistance of this type of glasses to attack by groundwaters is of special interest. The present report deals with the corrosion behaviour of glasses and discusses the most significant controlling parameters. The dissolution rates needed for safety analysis must be determined in relatively short-term experiments. Since the results can depend strongly on the type of test procedures used, a critical assessment of these techniques is necessary. Experimental results are illustrated by means of selected examples. Particular emphasis is placed upon the effects of increased temperatures and of nuclear radiation. The models which have been proposed for the estimation of the long-term behavior of vitrified waste are not yet fully complete and require improvement. Furthermore, the actual dissolution rates which are used in such models should be revised: to be desired are values which take into account the actual environmental conditions at the storage site. It should be noted, however, that even with current conservative input data on corrosion rates, a lifetime on the order of 10 5 years can be expected for the glass blocks to be deposited. The report concludes with recommendations fo further investigations

  10. Analysis by Fourier Transform Infrared (FTIR) of the gamma radiation effect on epoxy resin, used as solidification agent of radioactive wastes

    International Nuclear Information System (INIS)

    Liu, C.H.; Riella, H.G.; Guedes, S.M.L.

    1995-01-01

    The effects of gamma radiation on Epoxy resin, used as solidification agent of radioactive wastes, were studied by Fourier Transform Infrared (FTIR). The spectra showed no significant modifications on Epoxy resin functional groups (irradiated with dose from 0 to 1 MGy). Up to 1 MGy Epoxy resin did not oxidize, confirming the Epoxy good radiation strength. The presence of aromatic chain and amine group, mainly tertiary amine, give good radiolytic stability to the Epoxy, increasing the interest to use this material in nuclear facilities. (author). 3 refs, 2 figs

  11. Nuclear waste: the political realities

    International Nuclear Information System (INIS)

    Arnott, D.

    1983-01-01

    The land dumping of nuclear waste has again come to the attention of anti-nuclear groups, environmentalists and the media, following the announcement of the proposed sites for intermediate-level nuclear waste at Billingham and Bedford. Opposition has already surfaced on a large scale, with public meetings in both areas and a revitalisation of the waste dumping network. This article explains some of the political realities in the nuclear debate, and suggests how we can tackle the issue of waste dumping, remembering that, even if the industry closes tomorrow, there are vast quantities of waste which must be safely and democratically dealt with. (author)

  12. Risks from nuclear waste

    International Nuclear Information System (INIS)

    Liljenzin, J.O.; Rydberg, J.

    1996-11-01

    The first part of this review discusses the importance of risk. If there is any relation between the emotional and rational risk perceptions (for example, it is believed that increased knowledge will decrease emotions), it will be a desirable goal for society, and the nuclear industry in particular, to improve the understanding by the laymen of the rational risks from nuclear energy. This review surveys various paths to a more common comprehension - perhaps a consensus - of the nuclear waste risks. The second part discusses radioactivity as a risk factor and concludes that it has no relation in itself to risk, but must be connected to exposure leading to a dose risk, i.e. a health detriment, which is commonly expressed in terms of cancer induction rate. Dose-effect relations are discussed in light of recent scientific debate. The third part of the report describes a number of hazard indexes for nuclear waste found in the literature and distinguishes between absolute and relative risk scales. The absolute risks as well as the relative risks have changed over time due to changes in radiological and metabolic data and by changes in the mode of calculation. To judge from the literature, the risk discussion is huge, even when it is limited to nuclear waste. It would be very difficult to make a comprehensive review and extract the essentials from that. Therefore, we have chosen to select some publications, out of the over 100, which we summarize rather comprehensively; in some cases we also include our remarks. 110 refs, 22 figs

  13. Risks from nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Liljenzin, J.O.; Rydberg, J. [Radiochemistry Consultant Group, Vaestra Froelunda (Sweden)

    1996-11-01

    The first part of this review discusses the importance of risk. If there is any relation between the emotional and rational risk perceptions (for example, it is believed that increased knowledge will decrease emotions), it will be a desirable goal for society, and the nuclear industry in particular, to improve the understanding by the laymen of the rational risks from nuclear energy. This review surveys various paths to a more common comprehension - perhaps a consensus - of the nuclear waste risks. The second part discusses radioactivity as a risk factor and concludes that it has no relation in itself to risk, but must be connected to exposure leading to a dose risk, i.e. a health detriment, which is commonly expressed in terms of cancer induction rate. Dose-effect relations are discussed in light of recent scientific debate. The third part of the report describes a number of hazard indexes for nuclear waste found in the literature and distinguishes between absolute and relative risk scales. The absolute risks as well as the relative risks have changed over time due to changes in radiological and metabolic data and by changes in the mode of calculation. To judge from the literature, the risk discussion is huge, even when it is limited to nuclear waste. It would be very difficult to make a comprehensive review and extract the essentials from that. Therefore, we have chosen to select some publications, out of the over 100, which we summarize rather comprehensively; in some cases we also include our remarks. 110 refs, 22 figs.

  14. Solidification of metal chloride waste from pyrochemical process via dechlorination-chlorination reaction system

    Energy Technology Data Exchange (ETDEWEB)

    Park, H.S.; Cho, I.H.; Lee, K.R.; Choi, J.H.; Eun, H.C.; Kim, I.T.; Park, G.I. [Korea Atomic Energy Research Inst., Deajeon (Korea, Republic of)

    2014-07-01

    The metal chloride wastes generated from the pyro-chemical process to recover uranium and TRUs has been considered as a problematic waste due to the high volatility and low compatibility with conventional silicate glass. Our research group has suggested the dechlorination approach for the solidification of this kind of waste by using a synthetic composite, SAP (SiO{sub 2}-Al{sub 2}O{sub 3}-P{sub 2}O{sub 5}). During the dechlorination, metal elements are chemically interacted with the inorganic composite, SAP, while chlorine is vaporized as gaseous chlorine. Metal elements in the salt were immobilized into phosphate and silicate glass which are uniformly distributed in tens of nm scale. During the dechlorination, gaseous chlorine is captured by Li{sub 2}O-Li{sub 2}O{sub 2} composite that can be converted into metal chloride (LiCl). About 98wt% of oxide composite was converted into LiCl that can be used as an electrolyte in the electrochemical process. The method suggested in this study can provide a chance to minimize the waste volume for the final disposal of salt wastes from a pyro-chemical process. (author)

  15. PD and I works to improve the waste solidification performance of Angra 1

    International Nuclear Information System (INIS)

    Tello, Cledola C.O. de; Gomes, Nelson J.P.O.

    2009-01-01

    Angra 1 Power Plant is the first Brazilian NPP, and started its commercial operation in 1985. The wastes from its operation are spent ion exchange resins, expended filter cartridges, boric acid evaporator concentrates; and solid wastes such as gloves, cleaning tools, plastics and protective clothing. Liquid waste streams are treated by evaporation to reduce the volume, and the concentrate is solidified in cement. The original cementation unit was designed to meet the US product acceptance criteria of the early seventies, when environmental and safety requirements were less restrictive than now. This system had a very low efficiency, and the waste product quality was very poor. A new solidification plant was bought, and R and D project was carried out to study and develop a suitable cementation process and the PCP - process control program - to guarantee the licensing of the plant and maximize its efficiency using Brazilian materials. To accomplish these objectives, a huge amount of experiments were carried on. Tests were performed to determine the main properties of the process and the product, e.g. the workability, set time, compressive strength (stress resistance) and leachability. After reaching the established parameters, the mixture system was optimized. The paddle and container designs were modified and also the motor specifications, so that the process efficiency could be improved. The performance of this new system is increased allowing solidifying from 56 till 69% in volume of waste, much better in comparison of the old one, whose maximum value was about 20%. (author)

  16. SULFUR POLYMER STABILIZATION/SOLIDIFICATION (SPSS) TREATABILITY OF LOS ALAMOS NATIONAL LABORATORY MERCURY WASTE.

    Energy Technology Data Exchange (ETDEWEB)

    ADAMS,J.W.; KALB,P.D.

    2001-11-01

    Brookhaven National Laboratory's Sulfur Polymer Stabilization/Solidification (SPSS) process was used to treat approximately 90kg of elemental mercury mixed waste from Los Alamos National Laboratory. Treatment was carried out in a series of eight batches using a 1 ft{sup 3} pilot-scale mixer, where mercury loading in each batch was 33.3 weight percent. Although leach performance is currently not regulated for amalgamated elemental mercury (Hg) mixed waste, Toxicity Characteristic Leach Procedure (TCLP) testing of SPSS treated elemental mercury waste indicates that leachability is readily reduced to below the TCLP limit of 200 ppb (regulatory requirement following treatment by retort for wastes containing > 260 ppb Hg), and with process optimization, to levels less than the stringent Universal Treatment Standard (UTS) limit of 25 ppb that is applied to waste containing < 260 ppm Hg. In addition, mercury-contaminated debris, consisting of primary glass and plastic containers, as well as assorted mercury thermometers, switches, and labware, was first reacted with SPSS components to stabilize the mercury contamination, then macroencapsulated in the molten SPSS product. This treatment was done by vigorous agitation of the sulfur polymer powder and the comminuted debris. Larger plastic and metal containers were reacted to stabilize internal mercury contamination, and then filled with molten sulfur polymer to encapsulate the treated product.

  17. Green remediation and recycling of contaminated sediment by waste-incorporated stabilization/solidification.

    Science.gov (United States)

    Wang, Lei; Tsang, Daniel C W; Poon, Chi-Sun

    2015-03-01

    Navigational/environmental dredging of contaminated sediment conventionally requires contained marine disposal and continuous monitoring. This study proposed a green remediation approach to treat and recycle the contaminated sediment by means of stabilization/solidification enhanced by the addition of selected solid wastes. With an increasing amount of contaminated sediment (20-70%), the 28-d compressive strength of sediment blocks decreased from greater than 10MPa to slightly above 1MPa. For augmenting the cement hydration, coal fly ash was more effective than lime and ground seashells, especially at low sediment content. The microscopic and spectroscopic analyses showed varying amounts of hydration products (primarily calcium hydroxide and calcium silicate hydrate) in the presence of coal fly ash, signifying the influence of pozzolanic reaction. To facilitate the waste utilization, cullet from beverage glass bottles and bottom ashes from coal combustion and waste incineration were found suitable to substitute coarse aggregate at 33% replacement ratio, beyond which the compressive strength decreased accordingly. The mercury intrusion porosimetry analysis indicated that the increase in the total pore area and average pore diameter were linearly correlated with the decrease of compressive strength due to waste replacement. All the sediment blocks complied with the acceptance criteria for reuse in terms of metal leachability. These results suggest that, with an appropriate mixture design, contaminated sediment and waste materials are useful resources for producing non-load-bearing masonry units or fill materials for construction uses. Copyright © 2014 Elsevier Ltd. All rights reserved.

  18. Evaluation of concrete as a matrix for solidification of Savannah River Plant waste

    International Nuclear Information System (INIS)

    Stone, J.A.

    1977-06-01

    The properties of concrete as a matrix for solidification of Savannah River Plant (SRP) high-level radioactive wastes were studied. In an experimental, laboratory-scale program, concrete specimens were prepared and evaluated with both simulated and actual SRP waste sludges. Properties of concrete were found adequate for fixation of SRP wastes. Procedures were developed for preparation of simulated sludges and concrete-sludge castings. Effects of cement type, simulated sludge type, sludge loading, and water content on concrete formulations were tested in a factorial experiment. Compressive strength, leachability of strontium and plutonium, thermal stability, and radiation stability were measured for each formulation. From these studies, high-alumina cement and a portland-pozzolanic cement were selected for additional tests. Incorporation of cesium-loaded zeolite into cement-sludge mixtures had no adverse effects on mechanical or chemical properties of waste forms. Effects of heating concrete-sludge castings were investigated; thermal conductivity and DTA-TGA-EGA data are reported. Formulations of actual SRP waste sludges in concrete were prepared and tested for compressive strength; for leachability of 90 Sr, 137 Cs, and alpha emitters; and for long-term thermal stability. The radioactive sludges were generally similar in behavior to simulated sludges in concrete. 37 tables, 34 figures

  19. SULFUR POLYMER STABILIZATION/SOLIDIFICATION (SPSS) TREATABILITY OF LOS ALAMOS NATIONAL LABORATORY MERCURY WASTE

    International Nuclear Information System (INIS)

    ADAMS, J.W.; KALB, P.D.

    2001-01-01

    Brookhaven National Laboratory's Sulfur Polymer Stabilization/Solidification (SPSS) process was used to treat approximately 90kg of elemental mercury mixed waste from Los Alamos National Laboratory. Treatment was carried out in a series of eight batches using a 1 ft(sup 3) pilot-scale mixer, where mercury loading in each batch was 33.3 weight percent. Although leach performance is currently not regulated for amalgamated elemental mercury (Hg) mixed waste, Toxicity Characteristic Leach Procedure (TCLP) testing of SPSS treated elemental mercury waste indicates that leachability is readily reduced to below the TCLP limit of 200 ppb (regulatory requirement following treatment by retort for wastes containingandgt; 260 ppb Hg), and with process optimization, to levels less than the stringent Universal Treatment Standard (UTS) limit of 25 ppb that is applied to waste containingandlt; 260 ppm Hg. In addition, mercury-contaminated debris, consisting of primary glass and plastic containers, as well as assorted mercury thermometers, switches, and labware, was first reacted with SPSS components to stabilize the mercury contamination, then macroencapsulated in the molten SPSS product. This treatment was done by vigorous agitation of the sulfur polymer powder and the comminuted debris. Larger plastic and metal containers were reacted to stabilize internal mercury contamination, and then filled with molten sulfur polymer to encapsulate the treated product

  20. Nuclear waste management: a perspective

    International Nuclear Information System (INIS)

    Leuze, R.E.

    1980-01-01

    The scope of our problems with nuclear waste management is outlined. Present and future inventories of nuclear wastes are assessed for risk. A discussion of what is presently being done to solve waste management problems and what might be done in the future are presented

  1. 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.)

  2. Proceedings of the international seminar on chemistry and process engineering for high-level liquid waste solidification

    International Nuclear Information System (INIS)

    Odoj, R.; Merz, E.

    1981-06-01

    The proceedings record a very distinct phase of the chemistry and process engineering for high-level liquid waste solidification in the past years. The main purpose is to provide solutions which guarantee sufficient safe and economically acceptable measure causing no adverse consequence to man and his environment. (DG)

  3. Turning nuclear waste into glass

    Energy Technology Data Exchange (ETDEWEB)

    Pegg, Ian L.

    2015-02-15

    Vitrification has emerged as the treatment option of choice for the most dangerous radioactive waste. But dealing with the nuclear waste legacy of the Cold War will require state-of-the-art facilities and advanced glass formulations.

  4. Industrial wastes solidification and material recovery: prospectives in Italy. Prospettive dell'applicazione delle tecniche di inertizzazione

    Energy Technology Data Exchange (ETDEWEB)

    De Angelis, G; Balzano, S

    1988-12-01

    This paper focuses on state-of-the-art materials recovery techniques employed in the solidification/stabilization of industrial wastes. Particular consideration is given to the Italian situation. After a review, with reference to waste/matrix compatibility inherent problems, of the presently employed main encapsulation techniques (with matrices based on cement, lime, clay, thermoplastic materials, organic polymers, macroencapsulating compounds), attention is addressed to solidification systems which allow a recovery of the waste material as low-technology by-products. Regarding the most important industrial waste streams: thermoplastic refuse, incinerator ashes, chemical sludges, the paper reviews efforts devoted not only to their chemical fixation in order to fulfill the current land disposal requirements, but mainly to their employment for production of manufactured articles.

  5. Solidifications of wastewater sludge from nuclear power stations

    International Nuclear Information System (INIS)

    Hanzlicek, T.; Steinerova, M.; Perna, L.; Straka, P.

    2006-01-01

    Our task was to incorporate wastewater slag containing 30 wt. % and 60 wt. % water into a geopolymer matrix and encapsulate the mixture of materials into an inorganic polymer network. Prepared from activated kaolinitic clay by reaction with alkali aqueous solution. the geopolymer matrix accepts different types of inorganic materials, such as quartz, mica and limestone, in its formatted network. The geopolymer matrix also encapsulates and inhibits metals, including radioactive ones. By using the radioactive slag as the filler of a geopolymer matrix, the slag can be solidified in the form of a stable insoluble material suitable for storage. Application as a geopolymer matrix is an economic way to use the enormous quantities of waste clays emerging from industrial production. A cheap primary raw material and lower energy demands in comparison with the activation of clay with cement fabrication is one of the advantages of the geopolymer matrix. The only problem to resolve is the high quantities of water (60 wt. %), which must be reduced by using an additional inorganic filler (other type of waste could be used). In that moment the content of inhibited slag is lowered and recalculation in dry slug does not exceed 15 wt. %. The result of compression resistance is better than 10 MPa and leaching tests did not give any results exceeding the standards

  6. Nuclear Waste Fund management

    International Nuclear Information System (INIS)

    Hobart, L.

    1984-01-01

    The Nuclear Waste Fund involves a number of features which make it a unique federal program. Its primary purpose is to finance one of the largest and most controversial public works programs in the history of the United States. Despite the program's indicated size and advance publicity, no one knows exactly where the anticipated projects will be built, who will construct them, what they will look like when they are done or how they will be operated and by whom. Implimentation of this effort, if statutory targets are actually met, covers a 16-year period. To cover the costs of the program, the Federal Government will tax nuclear power at the rate of 1 mil per kilowatt hour generated. This makes it one of the biggest and longest-lived examples of advance collections for construction work in progress in the history of the United States. While the Department of Energy is authorized to collect funds for the program the Nuclear Regulatory Commission has the authority to cut off this revenue stream by the shutdown of particular reactors or particular reactor types. If all goes well, the Federal Government will begin receiving spent nuclear fuel by 1998, continuing to assess a fee which will cover operating and maintenance costs. If all does not go well, the Federal Government and/or utilities will have to take other steps to solve the problem of permanent disposal. Should the latter circumstance prevail, presumably not only used to date but the $7.5 billion would be spent. The Nuclear Waste Policy Act of 1982, contains no clear provision for utility refunds in that case

  7. Whither nuclear waste disposal?

    International Nuclear Information System (INIS)

    Cotton, T.A.

    1990-01-01

    With respect to the argument that geologic disposal has failed, I do not believe that the evidence is yet sufficient to support that conclusion. It is certainly true that the repository program is not progressing as hoped when the Nuclear Waste Policy Act of 1982 established a 1998 deadline for initial operation of the first repository. The Department of Energy (DOE) now expects the repository to be available by 2010, and tat date depends upon a finding that the Yucca Mountain site - the only site that DOE is allowed by law to evaluate - is in fact suitable for use. Furthermore, scientific evaluation of the site to determine its suitability is stopped pending resolution of two lawsuits. However, I believe it is premature to conclude that the legal obstacles are insuperable, since DOE just won the first of the two lawsuits, and chances are good it will win the second. The concept of geologic disposal is still broadly supported. A recent report by the Board on Radioactive Waste Management of the National Research Council noted that 'There is a worldwide scientific consensus that deep geological disposal, the approach being followed in the United States, is the best option for disposing of high-level radioactive waste'. The U.S. Nuclear Regulatory Commission (USNRC) recently implicitly endorsed this view in adopting an updated Waste Confidence position that found confidence that a repository could be available in the first quarter of the next century - sufficient time to allow for rejection of Yucca Mountain and evaluation of a new site

  8. Whither nuclear waste disposal?

    Energy Technology Data Exchange (ETDEWEB)

    Cotton, T A [JK Research Associates, Silver Spring, MD (United States)

    1990-07-01

    With respect to the argument that geologic disposal has failed, I do not believe that the evidence is yet sufficient to support that conclusion. It is certainly true that the repository program is not progressing as hoped when the Nuclear Waste Policy Act of 1982 established a 1998 deadline for initial operation of the first repository. The Department of Energy (DOE) now expects the repository to be available by 2010, and tat date depends upon a finding that the Yucca Mountain site - the only site that DOE is allowed by law to evaluate - is in fact suitable for use. Furthermore, scientific evaluation of the site to determine its suitability is stopped pending resolution of two lawsuits. However, I believe it is premature to conclude that the legal obstacles are insuperable, since DOE just won the first of the two lawsuits, and chances are good it will win the second. The concept of geologic disposal is still broadly supported. A recent report by the Board on Radioactive Waste Management of the National Research Council noted that 'There is a worldwide scientific consensus that deep geological disposal, the approach being followed in the United States, is the best option for disposing of high-level radioactive waste'. The U.S. Nuclear Regulatory Commission (USNRC) recently implicitly endorsed this view in adopting an updated Waste Confidence position that found confidence that a repository could be available in the first quarter of the next century - sufficient time to allow for rejection of Yucca Mountain and evaluation of a new site.

  9. SPECIFIC FEATURES OF OLIGOMERIC PRODUCT SOLIDIFICATION FROM POLYURETHANE WASTES AND THEIR PRACTICAL APPLICATION

    Directory of Open Access Journals (Sweden)

    V. Belyatsky

    2012-01-01

    Full Text Available The paper considers a possibility to use secondary polyurethane obtained by  thermal depolymerization of wastes on the basis of cross-linked polyurethane (polyurethane adduct and isocyanate. An effect of density dependence of the obtained polyurethane samples on nature and quantity of solvent has been revealed and it is significantly observed while using low-boiling solvents. The influence of adduct/solidification agent ratio on mechanical hardness of the obtained samples has been studied in the paper. The paper shows that the most optimal ratio is within the following limits – from 7/1 to 10/1. Plasticizing effect of polyurethane adduct on bitumen materials has been also found in the paper.A conclusion has been made that there is a possibility of practical usage of composites in building and road-building materials. 

  10. Nuclear wastes management

    International Nuclear Information System (INIS)

    2005-01-01

    This document is the proceedings of the debate that took place at the French Senate on April 13, 2005 about the long-term French policy of radioactive wastes management. The different points tackled during the debate concern: the 3 axes of research of the 1991 law, the public acceptance about the implementation of repositories, the regional economic impact, the cost and financing, the lack of experience feedback, the reversibility or irreversibility of the storage, the share of nuclear energy in the sustainable development policy, the European Pressurized Reactor (EPR) project, the privatization of Electricite de France (EdF) etc. (J.S.)

  11. Waste canister for storage of nuclear wastes

    Science.gov (United States)

    Duffy, James B.

    1977-01-01

    A waste canister for storage of nuclear wastes in the form of a solidified glass includes fins supported from the center with the tips of the fins spaced away from the wall to conduct heat away from the center without producing unacceptable hot spots in the canister wall.

  12. Waste canister for storage of nuclear wastes

    International Nuclear Information System (INIS)

    Duffy, J.B.

    1977-01-01

    A waste canister for storage of nuclear wastes in the form of a solidified glass includes fins supported from the center with the tips of the fins spaced away from the wall to conduct heat away from the center without producing unacceptable hot spots in the canister wall. 4 claims, 4 figures

  13. Nuclear waste processing

    International Nuclear Information System (INIS)

    Nienhuys, K.; Noordegraaf, D.

    1977-04-01

    This report is composed with a view to the discussions around the selection of a site in F.R.Germany near the Netherlands' border for a fuel reprocessing plant. Most of the scientific data available are placed side by side, especially those which are contradictory in order to promote better judgement of affairs before governmental decisions are made. The report comprises a brief introduction to nuclear power plants, fuel cycle, radioactive materials and their properties. Next the transportation of wastes from the nuclear power plants to the reprocessing plants is dealt with more extensively, including the processing and the effluents of as well as the experiences with operational reprocessing plants. The hazards from manipulation of radioactive materials accidents and theft are outlined in each case, followed by a problem discussion. The appendix illustrates the German concept of 'industrial park for after-treatment and disposal'

  14. Defense waste solidification studies, 200-S area. Savannah River Plant work request 860504, Project S-1780

    International Nuclear Information System (INIS)

    1977-05-01

    A scope of work and a venture guidance appraisal were prepared for a conceptual process and plant facilities for the solidification and long-term storage of radioactive wastes removed from underground storage tanks in the 241 F and H Areas at the Savannah River Plant. Conceptual design was based on incorporating the highly radioactive waste components in a borosilicate type glass. The scope of work describes facilities for: reclaiming liquid and sludge wastes from F and H area tank farms; separating the sludge from the liquid salt solution by physical processes; removing radioactive cesium from the salt solution by ion exchange techniques; incorporating the dried sludge and cesium in a borosilicate glass in stainless steel containers; evaporating the liquid salt solution and encapsulating the resulting salt cake in a stainless steel container; and storing two years' worth of glass and salt containing cyclinders in separate retrievable surface storage facilities. Operations are to be located in a new area, designated the 200-S area. A full complement of power, general, and service facilities are provided. The venture guidance appraisal based on FY 82 authorization and FY 87 turnover is $2,900,000,000. The figure is suitable for planning purposes only. The Glass-form Waste Case is a variation of the concrete-form waste case (or the Reference Plant Case) reported in DPE--3410. The new venture guidance appraisal for the concrete-form case (updated to a consistent time basis with the glass-form case) is $2,900,000,000, indicating no apparent cost advantage between the two waste product forms

  15. Retrofit of existing Dow solidification system at quad cities nuclear station

    International Nuclear Information System (INIS)

    Dekitis, L.; Jarvis, N.; Petri, R.; Testa, J.

    1983-01-01

    Over the past year ATCOR has been involved in the design, testing and supply of an In-container Mixing System Retrofit for Commonwealth Edison's Quad Cities Nuclear Station Solidification System. The system supplied by DOW, itself a retrofit of a urea formaldehyde system, was based upon use of 50 cubic foot containers (liners). ATCOR's retrofit increased liner capacity to 170 cubic feet and allowed in-cask solidification of highly radioactive material. This paper discusses the reasons for the decision to replace equipment within the originally furnished system and the development of the ATCOR plan to proof-test this equipment prior to delivery at the site. Results of this pre-testing, and a comparison between pre-tested conditions and the actual in-plan start-up tests are presented. Development of improved instrumentation and mechanical modifications which enhance the reliability of the ATCOR/DOW process In-container Mixing System was provided as a part of this project. Test results are presented on instruments, controls and the unique method of mechanical attachment of the Mixing Head to the solidification container

  16. Sulfur polymer cement, a solidification and stabilization agent for hazardous and radioactive wastes

    International Nuclear Information System (INIS)

    Darnell, G.R.

    1992-01-01

    Hydraulic cements have been the primary radioactive waste stabilization agents in the United States for 50 years. Twelve years ago, Brookhaven National Laboratory was funded by the Department of Energy's Defense Low-Level Waste Management Program to test and develop sulfur polymer cement (SPC). It has stabilized routine wastes as well as some troublesome wastes with high waste-to-agent ratios. The Department of Energy's Hazardous Waste Remedial Action Program joined the effort by providing funding for testing and developing sulfur polymer cement as a hazardous-waste stabilization agent. Sulfur polymer cement has passed all the laboratory scale tests required by the US Environmental Protection Agency and US Nuclear Regulatory Commission. Two decades of tests by the US Bureau of Mines and private concrete contractors indicate this agent is likely to exceed other agents in longevity. This bulletin provides technical data from pertinent tests conducted by these various entities

  17. Immobilization of wet solid wastes at nuclear power plants

    International Nuclear Information System (INIS)

    Neilson, R.M. Jr.

    1977-01-01

    Wet solid wastes are classified into four basic types: spent resins, filter sludges, evaporator concentrates, and miscellaneous liquids. Although the immobilization of wet solid wastes is primarily concerned with the incorporation of the waste with a solidification agent, there are a number of other discrete operations or subsystems involved in the treatment of these wastes that may affect the immobilized waste product. The immobilization process may be broken down into five basic operations: waste collection, waste pretreatment, solidification agent handling, mixing/packaging, and waste package handling. The properties of the waste forms that are ultimately shipped from the reactor site are primarily influenced by the methods utilized during the waste collection, waste pretreatment and mixing/packaging operations. The mixing/packaging (solidification) operation is perhaps the most important stage of the immobilization process. The basic solidification agent types are: absorbants, hydraulic cement, urea-formaldehyde, bitumen, and other polymer systems

  18. Glasses used in the solidification of high level radioactive waste: their behaviour in aqueous solutions

    International Nuclear Information System (INIS)

    Grauer, R.

    1983-02-01

    Because of their amorphous structure, glasses are particularly suitable matrixes for the solidification of the mixture of radionuclides included in the high level wastes from reactor fuel reprocessing. They are not sensitive to variations in the fractions present of different waste oxides and are resistent to the effects of irradiation. In particular, borosilicate glasses have been investigated for around 25 years and the vitrification techniques have been tested on the technological scale. The environmental conditions within a final waste repository are expected to be such that the chemical resistance of glasses to attack by groundwaters is of special interest. In the present report the corrosion behaviour is described, with emphasis being placed upon the most significant controlling parameters. Since experimental determination of corrosion rates must be done in relatively short-time experiments, the results of which can depend strongly upon the measurement methods employed, it is necessary to carry out a critical assessment of the techniques commonly used in laboratory work. Experimental results are illustrated by means of selected examples. Particular emphasis is placed upon the effects of increased temperatures and of irradiation. The models which have been proposed for the estimation of the long-term corrosion behaviour of glasses are not yet fully sufficient and improvements are required. Furthermore, the actual corrosion rates which are fed into such models must be replaced by values more appropriate for the actual environmental conditions to which the glasses are most likely to be exposed within high level waste repositories. It should be noted, however, that even with current conservative input data on corrosion rates, typical estimated lifetimes for vitrified waste blocks are of the order of 10 5 years. The report concludes with recommendations concerning the most useful areas for further investigations. (author)

  19. Science, society, and America's nuclear waste: Unit 1, Nuclear waste

    International Nuclear Information System (INIS)

    1992-01-01

    This is unit 1 in a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  20. Nuclear waste disposal in space

    Science.gov (United States)

    Burns, R. E.; Causey, W. E.; Galloway, W. E.; Nelson, R. W.

    1978-01-01

    Work on nuclear waste disposal in space conducted by the George C. Marshall Space Flight Center, National Aeronautics and Space Administration, and contractors are reported. From the aggregate studies, it is concluded that space disposal of nuclear waste is technically feasible.

  1. Nuclear waste - the unsolved problem

    International Nuclear Information System (INIS)

    Boyle, S.

    1986-01-01

    Nuclear waste is identified and the problems created by reprocessing are mentioned. The disposal option for low, intermediate and high-level radioactive wastes are discussed. Sites where disposal has taken place have been found to be unsatisfactory because of contamination and radionuclide migration. The Nuclear Industry Radioactive Waste Executive (NIREX) is not seen as having any more credibility than the other nuclear authorities involved (BNFL, UKAEA, CEGB). Until an adequate, publically acceptable, method of disposing of the wastes already created has been found the author states that no more should be created. (U.K.)

  2. Goals for nuclear waste management

    International Nuclear Information System (INIS)

    Watson, R.A.

    1978-01-01

    Establishing a publicly, politically, economically, and technologically acceptable waste management system for the fuel cycle is a necessary condition for accepting the nuclear program as a national energy option. Findings are given on the technology, politics, economics, morality, aesthetics, and societal impact of waste management. Proposed goals are outlined for the regulation of waste management

  3. Geological disposal of nuclear waste

    International Nuclear Information System (INIS)

    1979-01-01

    Fourteen papers dealing with disposal of high-level radioactive wastes are presented. These cover disposal in salt deposits, geologic deposits and marine disposal. Also included are papers on nuclear waste characterization, transport, waste processing technology, and safety analysis. All of these papers have been abstracted and indexed

  4. The wastes of nuclear fission

    International Nuclear Information System (INIS)

    Doubre, H.

    2005-01-01

    In this paper the author presents the problems of the radioactive wastes generated by the nuclear fission. The first part devoted to the fission phenomenon explains the incident neutron energy and the target nuclei role. The second part devoted to the nuclear wastes sources presents the production of wastes upstream of the reactors, in the reactors and why these wastes are dangerous. The third part discusses the radioactive wastes management in France (classification, laws). The last part details the associated research programs: the radionuclides separation, the disposal, the underground storage, the transmutation and the thorium cycle. (A.L.B.)

  5. Storage of nuclear wastes

    International Nuclear Information System (INIS)

    Ahlstroem, P.E.

    1988-01-01

    The Swedish system of handling and storage of nuclear wastes is well-developed. Existing plants and systems provide great freedom of action and flexibility regarding future development and decisions of ultimate storage of the spent fuel. The interim storage in CLAB - Central interim storage facility for spent nuclear fuel - could continue without any safety related problems for more than 40 years. In practice the choice of ultimate treatment system is not locked until the encapsulation of the fuel starts. At the same time it is of importance that the generation benefiting by the nuclear power production also be responsible for the development of the ultimate storage system and not unnecessarily postpones important decisions. The ultimate storage system for spent fuel could and should be developed within existing schedule. At the same time is should be worked out to provide coming generations with possibilities to do the type of supervision they like without maintenance and supervision requiring to become a prerequisite for a safe function. (O.S.)

  6. Radioactive waste treatment at the Boris Kidric Institute of nuclear sciences

    Energy Technology Data Exchange (ETDEWEB)

    Vukovic, Z [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

    1989-07-01

    The results of many years work on the problems of treatment and interim storage of radioactive waste at the Boris Kidric Institute of nuclear sciences are presented. The main R/D work based on chemical treatment, solidification and pressing is described (author)

  7. Radioactive waste treatment at the Boris Kidric Institute of nuclear sciences

    International Nuclear Information System (INIS)

    Vukovic, Z.

    1989-01-01

    The results of many years work on the problems of treatment and interim storage of radioactive waste at the Boris Kidric Institute of nuclear sciences are presented. The main R/D work based on chemical treatment, solidification and pressing is described (author)

  8. Status of nuclear waste management

    International Nuclear Information System (INIS)

    Kittel, J.H.

    1980-01-01

    This paper discusses what nuclear waste is and where it comes from, what the technical strategies are for disposing of this waste, compares the toxicity of nuclear waste to other materials that are more familiar to us, and finally, comments on why it is taking so long to get on with the job of isolating nuclear waste permanently. The author believes that the technical solutions for the management and disposal of high-level and low-level nuclear waste are adequately in hand. The issues that are delaying the implementation of this technology are almost entirely related to sociological and political considerations. High-level nuclear waste can be safely stored and isolated through a multiple barrier approach. Although it is a hazardous material and must be handled properly, its toxicity diminishes rapidly. It then becomes less hazardous than other materials that we deal with everyday in routine industrial or household operations. The disposal of low-level waste has not attracted as much public attention as high-level waste management. Nevertheless, it is just as important to the public. For example, the use of radioactive isotopes in medicine, and the many lives that are saved as a result, would be very greatly reduced if medical institutions had no place to dispose of their radioactive waste. The management of uranium mill tailings is similar in many technical aspects to low-level waste management. Institutional issues, however, have not become as important in the case of mill tailings disposal

  9. The problematic of nuclear wastes

    International Nuclear Information System (INIS)

    Rozon, D.

    2004-01-01

    Within the frame of a project of modification of radioactive waste storage installations, and of refurbishing the Gentilly-2 nuclear plant (Quebec, Canada), the author first gives an overview and comments assessments of the volume and nature of nuclear wastes produced by Canadian nuclear power plants. He presents the Canadian program of nuclear waste management (history, Seaborn assessment Commission, mission of the SGDN-NWMO). He discusses the relationship between risk and dose, the risk duration, and the case of non radioactive wastes. He discusses energy challenges in terms of CO 2 emissions and with respect to climate change, proposes an alternative scenario on a long term, compares nuclear energy and wind energy, and discusses the nuclear technology evolution

  10. Solidification/stabilisation of liquid oil waste in metakaolin-based geopolymer

    Energy Technology Data Exchange (ETDEWEB)

    Cantarel, V.; Nouaille, F.; Rooses, A.; Lambertin, D., E-mail: david.lambertin@cea.fr; Poulesquen, A.; Frizon, F.

    2015-09-15

    Highlights: • Formulation with 20 vol.% of oil in a geopolymer have been successful tested. • Oil waste is encapsulated as oil droplets in metakaolin-based geopolymer. • Oil/geopolymer composite present good mechanical performance. • Carbon lixiviation of oil/geopolymer composite is very low. - Abstract: The solidification/stabilisation of liquid oil waste in metakaolin based geopolymer was studied in the present work. The process consists of obtaining a stabilised emulsion of oil in a water-glass solution and then adding metakaolin to engage the setting of a geopolymer block with an oil emulsion stabilised in the material. Geopolymer/oil composites have been made with various oil fraction (7, 14 and 20 vol.%). The rigidity and the good mechanical properties have been demonstrated with compressive strength tests. Leaching tests evidenced the release of oil from the composite material is very limited whereas the constitutive components of the geopolymer (Na, Si and OH{sup −}) are involved into diffusion process.

  11. Production of solidified high level wastes: a cost comparison of solidification processes

    International Nuclear Information System (INIS)

    1977-06-01

    Differential cost estimates of the annual operating and maintenance costs and the capital costs for five HLW Waste Solidification Alternates were developed. The annual operating and maintenance cost estimates included the cost of labor, consumables, utilities, shipping casks, shipping and disposal at a federal repository. The capital cost included the cost of the component, installation and building. The differential cost estimates do not include equipment and facilities which are either shared with the reprocessing facility or are common between all of the alternates. Total annual cost differential between the five waste form alternates is summarized in tabular form. The Borosilicate Glass Alternate has the lowest total annual cost. The other alternates have higher costs which range from $6.6 M to $7.4 M per year higher than the Glass alternate with the Supercalcine being the highest cost at $7.4 M per year differential. The major items in the cost estimates are then disposal costs in the operating cost estimates and the HLW Storage Tanks in the capital cost estimates. The Supercalcine Multibarrier Alternate ships 180 canisters per year more than the other alternates and consequently has a significantly higher operating cost. However, off-setting this the Supercalcine Multibarrier Alternate does not require HLW Storage Tanks for decay because of the high heat conductivity of this product and correspondingly the capital cost for this alternate is significantly lower than the other alternates. The radiological risk values are correlated with the cost evaluation normalized to cost ($)/MWe-yr

  12. Solidification of oils and organic liquids

    International Nuclear Information System (INIS)

    Clark, D.E.; Colombo, P.; Neilson, R.M. Jr.

    1982-07-01

    The suitability of selected solidification media for application in the disposal of low-level oil and other organic liquid wastes has been investigated. In the past, these low-level wastes (LLWs) have commonly been immobilized by sorption onto solid absorbents such as vermiculite or diatomaceous earth. Evolving regulations regarding the disposal of these materials encourage solidification. Solidification media which were studied include Portland type I cement; vermiculite plus Portland type I cement; Nuclear Technology Corporation's Nutek 380-cement process; emulsifier, Portland type I cement-sodium silicate; Delaware Custom Materiel's cement process; and the US Gypsum Company's Envirostone process. Waste forms have been evaluated as to their ability to reliably produce free standing monolithic solids which are homogeneous (macroscopically), contain < 1% free standing liquids by volume and pass a water immersion test. Solidified waste form specimens were also subjected to vibratory shock testing and flame testing. Simulated oil wastes can be solidified to acceptable solid specimens having volumetric waste loadings of less than 40 volume-%. However, simulated organic liquid wastes could not be solidified into acceptable waste forms above a volumetric loading factor of about 10 volume-% using the solidification agents studied

  13. Glass containing radioactive nuclear waste

    International Nuclear Information System (INIS)

    Boatner, L.A.; Sales, B.C.

    1985-01-01

    Lead-iron phosphate glasses containing a high level of Fe 2 O 3 for use as a storage medium for high-level-radioactive nuclear waste. By combining lead-iron phosphate glass with various types of simulated high-level nuclear waste, a highly corrosion resistant, homogeneous, easily processed glass can be formed. For corroding solutions at 90 C, with solution pH values in the range between 5 and 9, the corrosion rate of the lead-iron phosphate nuclear waste glass is at least 10 2 to 10 3 times lower than the corrosion rate of a comparable borosilicate nuclear waste glass. The presence of Fe 2 O 3 in forming the lead-iron phosphate glass is critical. Lead-iron phosphate nuclear waste glass can be prepared at temperatures as low as 800 C, since they exhibit very low melt viscosities in the 800 to 1050 C temperature range. These waste-loaded glasses do not readily devitrify at temperatures as high as 550 C and are not adversely affected by large doses of gamma radiation in H 2 O at 135 C. The lead-iron phosphate waste glasses can be prepared with minimal modification of the technology developed for processing borosilicate glass nuclear waste forms. (author)

  14. Nuclear wastes: lets talk about

    International Nuclear Information System (INIS)

    1995-01-01

    This colloquium is entirely devoted to the problem of nuclear wastes management and to the anxiety of the French public opinion with respect to radioactive wastes in general. Nuclear wastes, generally are perceived as the unique problem of nuclear industry and as a new and unknown problem for which no solutions have been proposed so far. The aim of this colloquium is to demonstrate that such solutions exist and that, probably, they have been more thoroughly examined than in other industrial sectors. The two first talks give the inventory of possible solutions and the policy followed by nuclear operators for the conditioning and packaging of radioactive wastes. The other talks give the point of view of the producers and of the managers of nuclear wastes and the legal aspects of the management and storage of nuclear wastes, in particular the December 30, 1991 law. A particular attention is given to the importance of communication and public information in the successful management of nuclear wastes. (J.S.)

  15. Aspects of nuclear waste management

    International Nuclear Information System (INIS)

    Moberg, L.

    1990-10-01

    Six areas of concern in nuclear waste management have been dealt with in a four-year Nordic research programme. They include work in two international projects, Hydrocoin dealing with modelling of groundwater flow in crystalline rock, and Biomovs, concerned with biosphere models. Geologic questions of importance to the prediction of future behaviour are examined. Waste quantities from the decommissioning of nuclear power stations are estimated, and total amounts of waste to be transported in the Nordic countries are evaluated. Waste amounts from a hypothetical reactor accident are also calculated. (au)

  16. Nuclear waste. Storage at Vaalputs

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    The Vaalputs nuclear waste dump site in Namaqualand is likely to be used to store used fuel from Koeberg, as well as low and intermediate waste. It is argued that Vaalputs is the most suitable site in the world for the disposal of nuclear waste. The Vaalputs site is sparsely populated, there are no mineral deposits of any value, the agricultural potential is minimal. It is a typical semi-desert area. Geologically it lend itself towards the ground-storage of used nuclear fuel

  17. A literature review of mixed waste components: Sensitivities and effects upon solidification/stabilization in cement-based matrices

    International Nuclear Information System (INIS)

    Mattus, C.H.; Gilliam, T.M.

    1994-03-01

    The US DOE Oak Ridge Field Office has signed a Federal Facility Compliance Agreement (FFCA) regarding Oak Ridge Reservation (ORR) mixed wastes subject to the land disposal restriction (LDR) provisions of the Resource conservation and Recovery Act. The LDR FFCA establishes an aggressive schedule for conducting treatability studies and developing treatment methods for those ORR mixed (radioactive and hazardous) wastes listed in Appendix B to the Agreement. A development, demonstration, testing, and evaluation program has been initiated to provide those efforts necessary to identify treatment methods for all of the wastes that meet Appendix B criteria. The program has assembled project teams to address treatment development needs in a variety of areas, including that of final waste forms (i.e., stabilization/solidification processes). A literature research has been performed, with the objective of determining waste characterization needs to support cement-based waste-form development. The goal was to determine which waste species are problematic in terms of consistent production of an acceptable cement-based waste form and at what concentrations these species become intolerable. The report discusses the following: hydration mechanisms of Portland cement; mechanisms of retardation and acceleration of cement set-factors affecting the durability of waste forms; regulatory limits as they apply to mixed wastes; review of inorganic species that interfere with the development of cement-based waste forms; review of radioactive species that can be immobilized in cement-based waste forms; and review of organic species that may interfere with various waste-form properties

  18. Nuclear waste transmutation

    International Nuclear Information System (INIS)

    Salvatores, M.; Zaetta, A.; Delpech, M.; Girard, C.; Slessarev, I.; Tommasi, J.

    1994-01-01

    A deep repository for safe long-term storage of long-lived radioactive materials (waste) arising from nuclear fuel irradiation in reactors is a need generally accepted, whatever the strategy envisaged for further use of the irradiated fuel (e.g.: reprocessing and re-use of uranium and plutonium; no reprocessing and final disposal). To assess the impact on the environment of a waste repository, one is lead naturally to consider the impact of radiation on man and to define the radiotoxicity of the different isotopes. The toxicity of the materials stored in a repository is function of time and at a given time is the sum of the activities of each radionuclide multiplied by appropriate danger coefficients. This time dependent sum R, is a source of 'potential' radiotoxicity. It has been pointed out (in reference 1), that R does not measure 'risk', which has to take into account 'actual pathways and probability of radioactive release to the biosphere'. It is well understood that (e.g. in the case of spent PWR fuel) the main contributor to R are actinides, Pu being the main component (see table I). In the case of risk, the situation is by far more complex and dependent on the modeling of different geological environments. In the analysis made in reference 1 the predominant role of Tc-99, I-129 and Cs-135 has been pointed out. The same analysis also stresses that actinides will be by far less relevant with respect to the highly soluble and mobile fission products. (authors). 13 refs., 2 tabs., 2 figs

  19. Volume reduction and solidification of radioactive waste incineration ash with waste glass

    International Nuclear Information System (INIS)

    Koyama, Hidemi; Kobayashi, Masayuki

    2007-01-01

    The low-level radioactive waste generated from research institutions and hospitals etc. is packed into a container and is kept. The volume reduced state or the unprocessed state by incineration or compression processing are used because neither landfill sites nor disposal methods have been fixed. Especially, because the bulk density is low, and it is easy to disperse, the low-level radioactive waste incineration ash incinerated for the volume reduction is a big issue in security, safety, stability in the inventory location. A safe and appropriate disposal processing method is desired. When the low temperature sintering method in the use of the glass bottle cullet was examined, volume reduction and stabilization of low-level radioactive waste incineration ash were verified. The proposed method is useful for the easy treatment of the low-level radioactive waste incineration ash. (author)

  20. Incinerators for radioactive wastes in Japanese nuclear power stations

    International Nuclear Information System (INIS)

    Karita, Yoichi

    1983-01-01

    As the measures of treatment and disposal of radioactive wastes in nuclear power stations, the development of the techniques to decrease wastes, to reduce the volume of wastes, to treat wastes by solidification and to dispose wastes has been advanced energetically. In particular, efforts have been exerted on the volume reduction treatment from the viewpoint of the improvement of storage efficiency and the reduction of transport and disposal costs. Incineration as one of the volume reduction techniques has been regarded as the most effective method with large reduction ratio, but it was not included in waste treatment system. NGK Insulators Ltd. developed NGK type miscellaneous solid incinerators, and seven incinerators were installed in nuclear power stations. These incinerators have been operated smoothly, and the construction is in progress in six more plants. The necessity of incinerators in nuclear power stations and the problems in their adoption, the circumstance of the development of NGK type miscellaneous solid incinerators, the outline of the incinerator of Karlsruhe nuclear power station and the problems, the contents of the technical development in NGK, the outline of NGK type incinerators and the features, the outline of the pretreatment system, incinerator system, exhaust gas treatment system, ash taking out system and accessory equipment, the operational results and the performance are described. (Kako, I.)

  1. Nuclear waste management. Pioneering solutions from Finland

    International Nuclear Information System (INIS)

    Rasilainen, Kari

    2016-01-01

    Presentation outline: Background: Nuclear energy in Finland; Nuclear Waste Management (NWM) Experiences; Low and Intermediate Level Waste (LILW); High Level Waste - Deep Geological Repository (DGR); NWM cost estimate in Finland; Conclusions: World-leading expert services

  2. The correlation between composition, structure and properties of high-level waste solidification products

    International Nuclear Information System (INIS)

    Neumann, L.; Vojtech, O.; Santarova, M.; Stejskal, I.; Gulinskij, V.

    1977-01-01

    The final product of a high-level liquid waste solidification process must meet a number of quantitative criteria. The necessary data can be obtained by direct measurement of certain parameters of the product (leachability of important radionuclides from the basic matrix, total solubility of the final product, thermal conductivity, mechanical properties, the temperature dependence of viscosity, etc.). Some insight can also be obtained on the basis of a profound analysis of micro- and macrostructure of the solid product. Detailed knowledge of the structure makes it easier to evaluate the final product. In this paper an effort is made to find a relationship between composition and structure of the system and the properties of the product obtained under the specific conditions of the process. The results are demonstrated using a phosphate matrix in which fission products and corrosion products are included in a wide range of concentrations. For analysis of the structure properties, X-ray diffraction, microscopic and electron probe microanalysis (back-scattered electrons and characteristic X-radiation detection) have been used. Using standard methods, the hydrolytical resistance of the product and the selective leachability of caesium, strontium and rare-earth ions have been measured. The results obtained so far have confirmed the usefulness of structure analysis as a parallel method for product evaluation in the development of the process and probably also for large-scale application. (author)

  3. Thermosetting polymer for dynamic nuclear polarization: Solidification of an epoxy resin mixture including TEMPO

    Energy Technology Data Exchange (ETDEWEB)

    Noda, Yohei, E-mail: noda.yohei@jaea.go.jp [Quantum Beam Science Centre, Sector of Nuclear Science Research, Japan Atomic Energy Agency, Shirakata-Shirane, Tokai, Ibaraki 319-1195 (Japan); Kumada, Takayuki [Quantum Beam Science Centre, Sector of Nuclear Science Research, Kansai Photon Science Institute, Japan Atomic Energy Agency, Kizugawa, Kyoto 619-0215 (Japan); Yamaguchi, Daisuke; Shamoto, Shin-ichi [Quantum Beam Science Centre, Sector of Nuclear Science Research, Japan Atomic Energy Agency, Shirakata-Shirane, Tokai, Ibaraki 319-1195 (Japan)

    2015-03-11

    We investigated the dynamic nuclear polarization (DNP) of typical thermosetting polymers (two-component type epoxy resins; Araldite{sup ®} Standard or Araldite{sup ®} Rapid) doped with a (2,2,6,6-tetramethylpiperidine-1-yl)oxy (TEMPO) radical. The doping process was developed by carefully considering the decomposition of TEMPO during the solidification of the epoxy resin. The TEMPO electron spin in each two-component paste decayed slowly, which was favorable for our study. Furthermore, despite the dissolved TEMPO, the mixture of the two-component paste successfully solidified. With the resulting TEMPO-doped epoxy-resin samples, DNP experiments at 1.2 K and 3.35 T indicated a magnitude of a proton-spin polarization up to 39%. This polarization is similar to that (35%) obtained for TEMPO-doped polystyrene (PS), which is often used as a standard sample for DNP. To combine this solidification of TEMPO-including mixture with a resin-casting technique enables a creation of polymeric target materials with a precise and complex structure.

  4. Development of radioactive waste treatment system for nuclear power stations by Toshiba (III)

    International Nuclear Information System (INIS)

    Irie, H.; Takahara, T.; Matsuda, T.; Matsuura, H.; Yasumura, K.; Nakayama, Y.

    1989-01-01

    This paper describes a solidification process with thermosetting resin to satisfy both requirements of volume reduction and quality of solidified products. Volumes of solidified products in drums generated from spent resins and concentrated wastes were reduced respectively to 1/4 and less than 1/6 of those in the conventional cement solidification process. In plants using a simple demineralizing system for condensate polishing, a large amount of waste water with regenerant chemicals is generated from the condensate demineralizer. In general, radioactivity concentration of wastes from this type of nuclear power plant is comparatively high, so the dose rate at the surface of drums containing solidified wastes exceeds 200mR/h. A pelletizing system for radioactive wastes was developed to reduce their volumes and allow their interim storage until the radioactivity decays down to a level at which they can be handled easily

  5. Nuclear wastes; Dechets nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    Here is made a general survey of the situation relative to radioactive wastes. The different kinds of radioactive wastes and the different way to store them are detailed. A comparative evaluation of the situation in France and in the world is made. The case of transport of radioactive wastes is tackled. (N.C.)

  6. Contributions of the Nuclear Research Institute to the French-Czechoslovak seminar on the management of radioactive wastes held on 12-14 May, 1987

    International Nuclear Information System (INIS)

    1987-01-01

    Paper were submitted on the use of calcination in liquid radioactive waste solidification; experience with the operation of mobile lines of the MESA type which are tested at nuclear power plants; the treatment of low level liquid wastes from special laundries. Other papers described experience with the operation of the facility for processing low and intermediate level wastes run by UJV (Nuclear Research Institute) since 1962, and the conditions for a radioactive waste burial site in Czechoslovakia. (E.S.). 3 tabs

  7. Vitrification chemistry and nuclear waste

    International Nuclear Information System (INIS)

    Plodinec, M.J.

    1985-01-01

    The vitrification of nuclear waste offers unique challenges to the glass technologist. The waste contains 50 or 60 elements, and often varies widely in composition. Most of these elements are seldom encountered in processing commercial glasses. The melter to vitrify the waste must be able to tolerate these variations in composition, while producing a durable glass. This glass must be produced without releasing hazardous radionuclides to the environment during any step of the vitrification process. Construction of a facility to convert the nearly 30 million gallons of high-level nuclear waste at the Savannah River Plant into borosilicate glass began in late 1983. In developing the vitrification process, the Savannah River Laboratory has had to overcome all of these challenges to the glass technologist. Advances in understanding in three areas have been crucial to our success: oxidation-reduction phenomena during glass melting; the reaction between glass and natural wastes; and the causes of foaming during glass melting

  8. Problems with military nuclear waste

    International Nuclear Information System (INIS)

    Lawless, W.F.

    1985-01-01

    Spent fuel elements contain the largest amount of radioactivity, but commercial spent fuel is not presently being reprocessed in the US, so the wastes are left contained within spent fuel assemblies and are not immediately accessible to the environment. By reprocessing military spent fuel to separate plutonium and unspent uranium from the highly radioactive and high-heat fission product waste, known as high-level waste (99.5% fission products and about 0.5% plutonium and uranium), nuclear weapons manufacture produces more dangerous radioactive wastes than do current commercial processes. The Department of Energy standards should be subject to an environmental impact study. 27 references

  9. Nuclear waste management. Quarterly progress report, January-March, 1981

    Energy Technology Data Exchange (ETDEWEB)

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

    1981-06-01

    Reports and summaries are provided for the following programs: high-level waste process development; alternative waste forms; nuclear waste materials characterization center; TRU waste immobilization; TRU waste decontamination; krypton solidification; thermal outgassing; iodine-129 fixation; NWVP off-gas analysis; monitoring and physical characterization of unsaturated zone transport; well-logging instrumentation development; verification instrument development; mobility of organic complexes of radionuclide in soils; low-level waste generation reduction handbook; waste management system studies; assessment of effectiveness of geologic isolation systems; waste/rock interactions technology program; high-level waste form preparation; development of backfill materials; development of structural engineered barriers; disposal charge analysis; analysis of spent fuel policy implementation; spent fuel and pool component integrity program; analysis of postulated criticality events in a storage array of spent LWR fuel; asphalt emulsion sealing of uranium mill tailings; liner evaluation for uranium mill tailings; multilayer barriers for sealing of uranium tailings; application of long-term chemical biobarriers for uranium tailings; and revegetation of inactive uranium tailings sites.

  10. Public attitudes about nuclear waste

    International Nuclear Information System (INIS)

    Bisconti, A.S.

    1991-01-01

    There is general agreement that nuclear waste is an important national issue. It certainly is important to the industry. congress, too, gives high priority to nuclear waste disposal. In a recent pool by Reichman, Karten, Sword, 300 congressional staffers named nuclear waste disposal as the top nuclear energy-related legislative issue for Congress to address. In this paper most of the data the author discusses are from national polls that statistically represent the opinions of all American adults all across the country, as well as polls conducted in Nevada that statistically represent the opinions of all adults in that state. All the polls were by Cambridge Reports and have a margin of error of ± 3%

  11. Public and nuclear waste management

    International Nuclear Information System (INIS)

    Zinberg, D.

    1979-01-01

    Public concern on nuclear power is centered on the waste disposal problem. Some of the environmentalist and anti-nuclear movements are discussed, both in USA and abroad. The public is skeptical in part because of the secrecy legacy, although scientists are still largely trusted. However, the scientists are far from united in their viewpoints on the nuclear issue. The task for scientists are to put into perspective the limits to scientific knowledge and to interpret this knowledge to the public

  12. Encapsulation of nuclear wastes

    International Nuclear Information System (INIS)

    Arnold, J.L.; Boyle, R.W.

    1978-01-01

    Toxic waste materials are encapsulated by the method wherein the waste material in liquid or finely divided solid form is uniformly dispersed in a vinyl ester resin or an unsaturated polyester and the resin cured under conditions that the exotherm does not rise above the temperature at which the integrity of the encapsulating material is destroyed

  13. Mixed waste solidification testing on thermosetting polymer and cement based waste forms in support of Hanford's WRAP Module 2A Facility

    International Nuclear Information System (INIS)

    Burbank, D.A.; Weingardt, K.M.

    1993-01-01

    A testing program has been conducted by the Westinghouse Hanford Co. to confirm the baseline waste form selection for use in Waste Receiving and Processing (WRAP) Module 2A. WRAP Module 2A will provide treatment required to properly dispose of containerized contact-handled, mixed low-level waste at the US DOE Hanford Site in south-central Washington State. Solidification/stabilization has been chosen as the appropriate treatment for this waste. This work is intended to test cement-based and thermosetting polymer solidification media to confirm the baseline technologies selected for WRAP Module 2A. Screening tests were performed using the major chemical constituent of each waste type to measure the gross compatibility with the immobilization media and to determine formulations for more detailed testing. Surrogate wastes representing each of the eight waste types were prepared for testing. Surrogates for polymer testing were sent to a vendor commissioned for that portion of the test work. Surrogates for the grout testing were used in the Westinghouse Hanford Co. laboratory responsible for the grout performance testing. Detailed discussion of the lab. work and results are contained in this report

  14. Storage - Nuclear wastes are overflowing

    International Nuclear Information System (INIS)

    Dupin, Ludovic

    2016-01-01

    This article highlights that the dismantling of French nuclear installations will generate huge volumes of radioactive wastes and that France may lack space to store them. The Cigeo project (underground storage) only concerns 0.2 per cent of the nuclear waste volume produced by France in 50 years. If storage solutions exist for less active wastes, they will soon be insufficient, notably because of the quantity of wastes produced by the dismantling of existing reactors and fuel processing plants. Different assessments of these volumes are evoked. In order to store them, the ANDRA made a second call for innovating projects which would enable a reduction of this volume by 20 to 30 per cent. The article also evokes projects selected after the first call for projects. They mainly focus on nuclear waste characterization which will result in a finer management of wastes regarding their storage destination. Cost issues and the opposition of anti-nuclear NGOs are still obstacles to the development of new sites

  15. Waste management considerations in nuclear facility decommissioning

    International Nuclear Information System (INIS)

    Elder, H.K.; Murphy, E.S.

    1981-01-01

    Decommissioning of nuclear facilities involves the management of significant quantities of radioactive waste. This paper summarizes information on volumes of waste requiring disposal and waste management costs developed in a series of decommissioning studies performed for the U.S. Nuclear Regulatory Commission by the Pacific Northwest Laboratory. These studies indicate that waste management is an important cost factor in the decommissioning of nuclear facilities. Alternatives for managing decommissioning wastes are defined and recommendations are made for improvements in waste management practices

  16. Mobile calcination and cementation unit for solidification of concentrated radioactive wastes

    International Nuclear Information System (INIS)

    Napravnik, J.; Sazavsky, P.; Skaba, V.; Skvarenina, R.; Ditl, P.

    1985-01-01

    Mobile experimental unit MESA-1 was developed and manufactured for processing radioactive concentrates by direct cementation. The unit is mainly designed for processing low-level liquid wastes from nuclear power plants and other nuclear installations, in which the level of radioactivity does not exceed 10 10 Bq/m 3 , the salt content of liquid solutions does not exceed 500 kg/m 3 and the maximum amount of boric acid is 130 kg/m 3 . The equipment is built into three modules which may be assembled and dismantled in a short time and transported separately. The unit without the calciner module was tested in non-radioactive mode and in operation with actual radioactive wastes from the V-1 nuclear power plant. The course and results of the tests are described in detail. All project design values were achieved, a total of 18 dm 3 model solutions were processed and 1 m 3 of actual wastes with a salt content of 450 kg/m 3 . The test showed that with regard to the radiation level reached it will be necessary in the process of calcination to increase the shielding of certain exposed points. The calciner module is being assembled for completion. (Z.M.)

  17. Safe operation of existing radioactive waste management facilities at Dalat Nuclear Research Institute

    International Nuclear Information System (INIS)

    Pham Van Lam; Ong Van Ngoc; Nguyen Thi Nang

    2000-01-01

    The Dalat Nuclear Research Reactor was reconstructed from the former TRIGA MARK-II in 1982 and put into operation in March 1984. The combined technology for radioactive waste management was newly designed and put into operation in 1984. The system for radioactive waste management at the Dalat Nuclear Research Institute (DNRI) consists of radioactive liquid waste treatment station and disposal facilities. The treatment methods used for radioactive liquid waste are coagulation and precipitation, mechanical filtering and ion- exchange. Near-surface disposal of radioactive wastes is practiced at DNRI In the disposal facilities eight concrete pits are constructed for solidification and disposal of low level radioactive waste. Many types of waste generated in DNRI and in some Nuclear Medicine Departments in the South of Vietnam are stored in the disposal facilities. The solidification of sludge has been done by cementation. Hydraulic compactor has done volume reduction of compatible waste. This paper presents fifteen-years of safe operation of radioactive waste management facilities at DNRI. (author)

  18. Treating nuclear waste

    International Nuclear Information System (INIS)

    Marriott, R.; Henyey, F.S.; Hochstim, A.R.

    1984-01-01

    A method of decreasing the amount of relatively long-lived fission products in radioactive waste materials comprises the steps of: separating relatively short-lived radioactive nuclides and stable nuclides from the waste material and storing at least some of them, exposing the remaining waste to a neutron flux in order to induce transmutations, separating the relatively short-lived radioactive nuclides and stable nuclides from the exposed materials and storing at least some of them, and repeating the exposure and separation steps

  19. Glasses and nuclear waste vitrification

    International Nuclear Information System (INIS)

    Ojovan, Michael I.

    2012-01-01

    Glass is an amorphous solid material which behaves like an isotropic crystal. Atomic structure of glass lacks long-range order but possesses short and most probably medium range order. Compared to crystalline materials of the same composition glasses are metastable materials however crystallisation processes are kinetically impeded within times which typically exceed the age of universe. The physical and chemical durability of glasses combined with their high tolerance to compositional changes makes glasses irreplaceable when hazardous waste needs immobilisation for safe long-term storage, transportation and consequent disposal. Immobilisation of radioactive waste in glassy materials using vitrification has been used successfully for several decades. Nuclear waste vitrification is attractive because of its flexibility, the large number of elements which can be incorporated in the glass, its high corrosion durability and the reduced volume of the resulting wasteform. Vitrification involves melting of waste materials with glass-forming additives so that the final vitreous product incorporates the waste contaminants in its macro- and micro-structure. Hazardous waste constituents are immobilised either by direct incorporation into the glass structure or by encapsulation when the final glassy material can be in form of a glass composite material. Both borosilicate and phosphate glasses are currently used to immobilise nuclear wastes. In addition to relatively homogeneous glasses novel glass composite materials are used to immobilise problematic waste streams. (author)

  20. Glass and nuclear wastes

    International Nuclear Information System (INIS)

    Sombret, C.

    1982-10-01

    Glass shows interesting technical and economical properties for long term storage of solidified radioactive wastes by vitrification or embedding. Glass composition, vitrification processes, stability under irradiation, thermal stability and aqueous corrosion are studied [fr

  1. French people and nuclear wastes

    International Nuclear Information System (INIS)

    D'Iribarne, Ph.

    2005-01-01

    On March 21, 2005, the French minister of industry gave to the author of this document, the mission to shade a sociological light on the radioactive wastes perception by French people. The objective of this study was to supply an additional information before the laying down in 2006 of the decisions about the management of high-level and long-lived radioactive wastes. This inquiry, carried out between April 2004 and March 2005, stresses on the knowledge and doubts of the questioned people, on the vision they have of radioactive wastes and of their hazards, and on their opinion about the actors in concern (experts, nuclear companies, government, anti-nuclear groups, public). The last two parts of the report consider the different ways of waste management under study today, and the differences between the opinion of people living close to the Bure site and the opinion of people living in other regions. (J.S.)

  2. Equity and nuclear waste disposal

    International Nuclear Information System (INIS)

    Shrader-Frechette, K.

    1994-01-01

    Following the recommendations of the US National Academy of Sciences and the mandates of the 1987 Nuclear Waste Policy Amendments Act, the US Department of Energy has proposed Yucca Mountain, Nevada as the site of the world's first permanent repository for high-level nuclear waste. The main justification for permanent disposal (as opposed to above-ground storage) is that it guarantees safety by means of waste isolation. This essay argues, however, that considerations of equity (safer for whom?) undercut the safety rationale. The article surveys some prima facie arguments for equity in the distribution of radwaste risks and then evaluates four objections that are based, respectively, on practicality, compensation for risks, scepticism about duties to future generations, and the uranium criterion. The conclusion is that, at least under existing regulations and policies, permanent waste disposal is highly questionable, in part, because it fails to distribute risk equitably or to compensate, in full, for this inequity

  3. Nuclear waste and nimby

    Energy Technology Data Exchange (ETDEWEB)

    Marshall, W

    1986-06-01

    A report of the Tizard lecture by Lord Marshall, chairman of the UK CEGB, on the health risks associated with the disposal of radioactive wastes is given. The risks from inhalation and ingestion of various types of radioactive waste disposal are compared to the risks from radioactive material occurring naturally in the average garden soil in the UK occupying one tenth of an acre. The relative potential health risk from inhalation of coal ash is also contrasted.

  4. Polymer Solidification Technology - Technical Issues and Challenges

    International Nuclear Information System (INIS)

    Jensen, Charles; Kim, Juyoul

    2010-01-01

    Many factors come into play, most of which are discovered and resolved only during full-scale solidification testing of each of the media commonly used in nuclear power plants. Each waste stream is unique, and must be addressed accordingly. This testing process is so difficult that Diversified's Vinyl Ester Styrene and Advanced Polymer Solidification are the only two approved processes in the United States today. This paper summarizes a few of the key obstacles that must be overcome to achieve a reliable, repeatable process for producing an approved Stable Class B and C waste form. Before other solidification and encapsulation technologies can be considered compliant with the requirements of a Stable waste form, the tests, calculations and reporting discussed above must be conducted for both the waste form and solidification process used to produce the waste form. Diversified's VERI TM and APS TM processes have gained acceptance in the UK. These processes have also been approved and gained acceptance in the U. S. because we have consistently overcome technical hurdles to produce a complaint product. Diversified Technologies processes are protected intellectual property. In specific instances, we have patents pending on key parts of our process technology

  5. Nuclear waste glass corrosion mechanisms

    International Nuclear Information System (INIS)

    Jantzen, C.M.

    1987-04-01

    Dissolution of nuclear waste glass occurs by corrosion mechanisms similar to those of other solids, e.g., metallurgical and mineralogic systems. Metallurgical phenomena such as active corrosion, passivation and immunity have been observed to be a function of the glass composition and the solution pH. Hydration thermodynamics was used to quantify the role of glass composition and its effect on the solution pH during dissolution. A wide compositional range of natural, lunar, medieval, and nuclear waste glasses, as well as some glass-ceramics were investigated. The factors observed to affect dissolution in deionized water are pertinent to the dissolution of glass in natural environments such as the groundwaters anticipated to interact with nuclear waste glass in a geologic repository. The effects of imposed pH and oxidation potential (Eh) conditions existing in natural environments on glass dissolution is described in the context of Pourbaix diagrams, pH potential diagrams, for glass

  6. Ethical aspects on Nuclear Waste

    International Nuclear Information System (INIS)

    Persson, Lars

    1989-01-01

    In an ethical assessment of how we shall deal with nuclear waste, one of the chief questions that arises is how to initiate action while at the same time taking into consideration uncertainties which are unavoidable seen from a long-term perspective. By means of different formulation and by proceeding from various starting-points, a two edged objective is established vis-a-vis repository facilities: safety in operation combined with reparability, with controls not necessary, but not impossible. Prerequisites for the realization of this objective are the continued advancement of knowledge and refinement of the qualifications required to deal with nuclear waste. The ethical considerations above could be the bases for the future legislation in the field of nuclear energy waste. (author)

  7. Nuclear power and radioactive waste

    International Nuclear Information System (INIS)

    Grimston, M.

    1991-03-01

    The gap between the relative perceptions in the area of nuclear waste is wide. The broad view of the industry is that the disposal of nuclear waste is not a serious technical problem, and that solutions are already available to provide safe disposal of all our waste. The broad view of those who oppose the industry is that radioactive waste is so unpleasant, and will remain lethal for so long, that no acceptable policy will ever be developed, and so production of such waste (except, oddly, the significant amounts arising from uses of radioactive materials in medicine, agriculture, industrial safety research, etc) should stop immediately. This booklet will not attempt to describe in great detail the technicalities of the United Kingdom nuclear industry's current approach to radioactive waste: such issues are described in detail in other publications, especially those by Nirex. It is our intention to outline some of the main issues involved, and to associate these issues with the divergence in perceptions of various parties. (author)

  8. Modern methods for evaluating the workability of cement used as a binder for the stabilization and solidification of toxic wastes

    Energy Technology Data Exchange (ETDEWEB)

    De Angelis, Giorgio [ENEA, Centro Ricerche Casaccia, Rome (Italy). Dipt. Ambiente

    1997-10-01

    The workability of cement pastes has a great influence on the final properties of the solidified products, like mechanical strength, stability density and durability. This is quite relevant in the field of stabilization / solidification of toxic and hazardous wastes. Hence considerable importance attaches to having reliable control over the fresh concrete properties, especially its early stiffening behaviour. This paper discussers measuring methods of the stiffening of two different types of cement pastes, prepared with different water / cement ratios, and examines the possible consequences of the early stiffening of cement pastes on their set times and bleeding.

  9. Comparison of costs for solidification of high-level radioactive waste solutions: glass monoliths vs metal matrices

    International Nuclear Information System (INIS)

    Jardine, L.J.; Carlton, R.E.; Steindler, M.J.

    1981-05-01

    A comparative economic analysis was made of four solidification processes for liquid high-level radioactive waste. Two processes produced borosilicate glass monoliths and two others produced metal matrix composites of lead and borosilicate glass beads and lead and supercalcine pellets. Within the uncertainties of the cost (1979 dollars) estimates, the cost of the four processes was about the same, with the major cost component being the cost of the primary building structure. Equipment costs and operating and maintenance costs formed only a small portion of the building structure costs for all processes

  10. Underground storage of nuclear waste

    International Nuclear Information System (INIS)

    Russell, J.E.

    1977-06-01

    The objective of the National Waste Terminal Storage (NWTS) Program is to provide facilities in various deep geologic formations at multiple locations in the United States which will safely dispose of commerical radioactive waste. The NWTS Program is being administered for the Energy Research and Development Administration (ERDA) by the Office of Waste Isolation (OWI), Union Carbide Corporation, Nuclear Division. OWI manages projects that will lead to the location, construction, and operation of repositories, including all surface and underground engineering and facility design projects and technical support projects. 7 refs., 5 figs

  11. Underground storage of nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Russell, J E

    1977-12-01

    The objective of the National Waste Terminal Storage (NWTS) Program is to provide facilities in various deep geologic formations at multiple locations in the United States which will safely dispose of commercial radioactive waste. The NWTS Program is being administered for the Energy Research and Development Administration (ERDA) by the Office of Waste Isolation (OWI), Union Carbide Corporation, Nuclear Division. OWI manages projects that will lead to the location, construction, and operation of repositories, including all surface and underground engineering and facility design projects and technical support projects.

  12. Sulfur polymer stabilization/solidification (SPSS) treatment of mixed waste mercury recovered from environmental restoration activities at BNL

    Energy Technology Data Exchange (ETDEWEB)

    Kalb, P.; Adams, J.; Milian, L.

    2001-01-29

    Over 1,140 yd{sup 3} of radioactively contaminated soil containing toxic mercury (Hg) and several liters of mixed-waste elemental mercury were generated during a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) removal action at Brookhaven National Laboratory (BNL). The US Department of Energy's (DOE) Office of Science and Technology Mixed Waste Focus Area (DOE MWFA) is sponsoring a comparison of several technologies that may be used to treat these wastes and similar wastes at BNL and other sites across the DOE complex. This report describes work conducted at BNL on the application and pilot-scale demonstration of the newly developed Sulfur Polymer Stabilization/Solidification (SPSS) process for treatment of contaminated mixed-waste soils containing high concentrations ({approximately} 5,000 mg/L) of mercury and liquid elemental mercury. BNL's SPSS (patent pending) process chemically stabilizes the mercury to reduce vapor pressure and leachability and physically encapsulates the waste in a solid matrix to eliminate dispersion and provide long-term durability. Two 55-gallon drums of mixed-waste soil containing high concentrations of mercury and about 62 kg of radioactive contaminated elemental mercury were successfully treated. Waste loadings of 60 wt% soil were achieved without resulting in any increase in waste volume, while elemental mercury was solidified at a waste loading of 33 wt% mercury. Toxicity Characteristic Leaching Procedure (TCLP) analyses indicate the final waste form products pass current Environmental Protection Agency (EPA) allowable TCLP concentrations as well as the more stringent proposed Universal Treatment Standards. Mass balance measurements show that 99.7% of the mercury treated was successfully retained within the waste form, while only 0.3% was captured in the off gas system.

  13. Sulfur polymer stabilization/solidification (SPSS) treatment of mixed waste mercury recovered from environmental restoration activities at BNL

    International Nuclear Information System (INIS)

    Kalb, P.; Adams, J.; Milian, L.

    2001-01-01

    Over 1,140 yd 3 of radioactively contaminated soil containing toxic mercury (Hg) and several liters of mixed-waste elemental mercury were generated during a Comprehensive Environmental Response, Compensation and Liability Act (CERCLA) removal action at Brookhaven National Laboratory (BNL). The US Department of Energy's (DOE) Office of Science and Technology Mixed Waste Focus Area (DOE MWFA) is sponsoring a comparison of several technologies that may be used to treat these wastes and similar wastes at BNL and other sites across the DOE complex. This report describes work conducted at BNL on the application and pilot-scale demonstration of the newly developed Sulfur Polymer Stabilization/Solidification (SPSS) process for treatment of contaminated mixed-waste soils containing high concentrations (approximately 5,000 mg/L) of mercury and liquid elemental mercury. BNL's SPSS (patent pending) process chemically stabilizes the mercury to reduce vapor pressure and leachability and physically encapsulates the waste in a solid matrix to eliminate dispersion and provide long-term durability. Two 55-gallon drums of mixed-waste soil containing high concentrations of mercury and about 62 kg of radioactive contaminated elemental mercury were successfully treated. Waste loadings of 60 wt% soil were achieved without resulting in any increase in waste volume, while elemental mercury was solidified at a waste loading of 33 wt% mercury. Toxicity Characteristic Leaching Procedure (TCLP) analyses indicate the final waste form products pass current Environmental Protection Agency (EPA) allowable TCLP concentrations as well as the more stringent proposed Universal Treatment Standards. Mass balance measurements show that 99.7% of the mercury treated was successfully retained within the waste form, while only 0.3% was captured in the off gas system

  14. Arctic Nuclear Waste Assessment Program

    International Nuclear Information System (INIS)

    Edson, R.

    1995-01-01

    The Arctic Nuclear Waste Assessment Program (ANWAP) was initiated in 1993 as a result of US congressional concern over the disposal of nuclear materials by the former Soviet Union into the Arctic marine environment. The program is comprised of appr. 70 different projects. To date appr. ten percent of the funds has gone to Russian institutions for research and logistical support. The collaboration also include the IAEA International Arctic Seas Assessment Program. The major conclusion from the research to date is that the largest signals for region-wide radionuclide contamination in the Arctic marine environment appear to arise from the following: 1) atmospheric testing of nuclear weapons, a practice that has been discontinued; 2) nuclear fuel reprocessing wastes carried in the Arctic from reprocessing facilities in Western Europe, and 3) accidents such as Chernobyl and the 1957 explosion at Chelyabinsk-65

  15. Nuclear waste transmutation

    International Nuclear Information System (INIS)

    Leray, S.

    1995-01-01

    Accelerators can play a role in the disposal of long-lived radioactive waste: an alternative to the storage in deep underground repositories might transmuting long-lived elements into stable or short-lived ones in subcritical systems driven by spallation neutrons. These neutrons would be produced by a high intensity, intermediate energy proton accelerator irradiating a heavy target. Similar systems have also been proposed to produce energy with a minimized waste inventory. Since a good knowledge of the spallation process is essential for designing and optimizing the target-blanket assembly, new programmes aimed at studying spallation reactions are in progress. (author). 6 figs

  16. The emergency avoidance solidification campaign of liquid low-level waste at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Myrick, T.E.; Helms, R.E.; Scanlan, T.F.; Schultz, R.M.; Scott, C.B.; Williams, L.C.; Homan, F.J.; Keigan, M.V.; Monk, T.H.; Morrow, R.W.; Van Hoesen, S.D.; du Mont, S.P.

    1992-01-01

    Since the beginning of nuclear research and development activities at the Oak Ridge National Laboratory (ORNL) in 1943, the generation, collection, treatment, storage, and disposal of the liquid low-level waste (LLLW) stream has been an integral part of ORNL's waste management operations. This waste stream, consisting principally of a high nitrate (4.5 molar), high pH (pH 13--14) mixture of reactor, hot cell, and research laboratory liquid radioactive wastes (<5 Ci/gal), has been treated and disposed of in a variety of ways over the years. Most recently, the hydrofracture technology had been used for deep-well disposal of a grout mix of LLLW, cement, fly ash, and other additives. In 1984, this disposal technique was discontinued due to regulatory permitting issues and the need for extensive facility modifications for future operations. With loss of this disposal capability and the continued generation of LLLW by ORNL research activities, the limited tank storage capacity was rapidly being depleted

  17. Regulating nuclear fuel waste

    International Nuclear Information System (INIS)

    1995-01-01

    When Parliament passed the Atomic Energy Control Act in 1946, it erected the framework for nuclear safety in Canada. Under the Act, the government created the Atomic Energy Control Board and gave it the authority to make and enforce regulations governing every aspect of nuclear power production and use in this country. The Act gives the Control Board the flexibility to amend its regulations to adapt to changes in technology, health and safety standards, co-operative agreements with provincial agencies and policy regarding trade in nuclear materials. This flexibility has allowed the Control Board to successfully regulate the nuclear industry for more than 40 years. Its mission statement 'to ensure that the use of nuclear energy in Canada does not pose undue risk to health, safety, security and the environment' concisely states the Control Board's primary objective. The Atomic Energy Control Board regulates all aspects of nuclear energy in Canada to ensure there is no undue risk to health, safety, security or the environment. It does this through a multi-stage licensing process

  18. Design and construction of solidification and dewatering facility at Alabama Power Company's Farley Nuclear Plant

    International Nuclear Information System (INIS)

    Farnsworth, P.

    1988-01-01

    The approximate total cost of the structure and supporting piping systems is estimated to be 4.1 million dollars. Total dose savings per year could be as high as 70 man Rem for resin processing alone. The ability to store refueling equipment, process contaminated oils, load and unload trucks and containers regardless of weather conditions and support repair work on equipment greatly enhances the cost effectiveness of the project. It will take at least one year of operation of the facility to accurately assess the true cost savings to Alabama Power Company. The morale factor for the Waste and Decon Group has escalated measurably due to the dose reduction to our personnel. Plant and company management are well pleased due to the possibility of a spill or release to the environment has been eliminated which was on intangible cost. Facility construction has been completed as of this date and resin transfer anticipated within the next few days. Some of the problems encountered in planning and constructing this solidification and dewatering facility are presented. A safety evaluation for the facility is included in the appendix

  19. The solidification of high-level liquid wastes in glass and ceramics

    International Nuclear Information System (INIS)

    Krause, H.

    1989-01-01

    In spent nuclear fuel reprocessing a highly radioactive waste solution is produced. It must be converted into a solid product, which binds the radionuclides, be hydrolytic as well as radiation and temperature resistant. Borosilicate glasses fulfil these requirements and, jointly with the barriers of a repository, they prevent inadmissible amounts of radionuclides from escaping into the biocycle. Two techniques were developed for industrial-scale vitrification: a rotary kiln calciner combined with an induction heated metallic melter and the electrode heated ceramic melters. Both techniques were already demonstrated on an industrial scale and under radioactive conditions. (AVM, Marcoule and PAMELA, Mol). (orig./MM) [de

  20. Study of stabilization/solidification processes (of solid porous wastes) based on hydraulic or bituminous binders; Etude des procedes de stabilisation/solidification (des dechets solides poreux) a base de liants hydrauliques ou de liants bitumineux

    Energy Technology Data Exchange (ETDEWEB)

    Sing-Teniere, Ch.

    1998-02-01

    The first part of this thesis presents the regulatory framework and the technical context linked with the study of stabilized/solidified wastes and with the evaluation of stabilization/solidification processes. A presentation of the two type of ultimate wastes under study (a used catalyst and an activated charcoal) and an analysis of the processes is given. The second part is devoted to the experimental characterization of both types of porous wastes. The third part deals with the processing of such wastes using an hydraulic binder. The study stresses on both on the stabilization/solidification efficiency of the process and on the conditions of its implementation. The same work is made for a process that uses a bituminous binder. Some choice criteria for the selection of the better process are deduced from the examination of the overall data collected. The waste characterization methodology is applied six times: two times for the raw wastes, two times for the same wastes processed with an hydraulic binder, and two times for the same wastes processed with a bituminous binder. (J.S.)

  1. Scientific basis for nuclear waste management XX

    International Nuclear Information System (INIS)

    Gray, W.J.; Triay, I.R.

    1997-01-01

    The proceedings are divided into the following topical sections: Glass formulations and properties; Glass/water interactions; Cements in radioactive waste management; Ceramic and crystalline waste forms; Spent nuclear fuel; Waste processing and treatment; Radiation effects in ceramics, glasses, and nuclear waste materials; Waste package materials; Radionuclide solubility and speciation; Radionuclide sorption; Radionuclide transport; Repository backfill; Performance assessment; Natural analogues; Excess plutonium dispositioning; and Chernobyl-related waste disposal issues. Papers within scope have been processed separately for inclusion on the data base

  2. The Geopolitics of Nuclear Waste.

    Science.gov (United States)

    Marshall, Eliot

    1991-01-01

    The controversy surrounding the potential storage of nuclear waste at Yucca Mountain, Nevada, is discussed. Arguments about the stability of the site and the groundwater situation are summarized. The role of the U.S. Department of Energy and other political considerations are described. (CW)

  3. Review of nuclear waste isolation

    International Nuclear Information System (INIS)

    Richard, B.H.

    1978-06-01

    On Jun 22 and 23, 1978, Rockwell Hanford Operations assembled a committee of their personnel, subcontractors, and representatives of other waste isolation programs for a review of nuclear waste isolation. Appendix A lists the participants and their affiliations; Appendix B indicates the agenda. The purpose of the review was to gather experts in the areas pertaining to isolation of nuclear waste to discuss three basic issues that must be addressed in isolation studies. These were: the paths of transport to the biosphere; the barriers needed for containment; and the isolation time necessary for each radioactive isotope. In that these issues are media dependent, the basalt medium was emphasized. Conclusions of the review are described

  4. Microwave solidification project overview

    Energy Technology Data Exchange (ETDEWEB)

    Sprenger, G.

    1993-01-01

    The Rocky Flats Plant Microwave Solidification Project has application potential to the Mixed Waste Treatment Project and the The Mixed Waste Integrated Program. The technical areas being addressed include (1) waste destruction and stabilization; (2) final waste form; and (3) front-end waste handling and feed preparation. This document covers need for such a program; technology description; significance; regulatory requirements; and accomplishments to date. A list of significant reports published under this project is included.

  5. Microwave solidification project overview

    International Nuclear Information System (INIS)

    Sprenger, G.

    1993-01-01

    The Rocky Flats Plant Microwave Solidification Project has application potential to the Mixed Waste Treatment Project and the The Mixed Waste Integrated Program. The technical areas being addressed include (1) waste destruction and stabilization; (2) final waste form; and (3) front-end waste handling and feed preparation. This document covers need for such a program; technology description; significance; regulatory requirements; and accomplishments to date. A list of significant reports published under this project is included

  6. Keynote address at the international conference on nuclear waste transmutation

    International Nuclear Information System (INIS)

    Steinberg, M.

    1980-07-01

    Most of the US research effort on radioactive waste management is concentrated on its solidification and storage in geologic formations. Transmutation is an alternative. It can be applied to weapons plutonium as well to spent fuel

  7. Experience with radioactive waste incineration at Chalk River Nuclear Laboratories

    International Nuclear Information System (INIS)

    Le, V.T.; Beamer, N.V.; Buckley, L.P.

    1988-06-01

    Chalk River Nuclear Laboratories is a nuclear research centre operated by Atomic Energy of Canada Limited. A full-scale waste treatment centre has been constructed to process low- and intermediate-level radioactive wastes generated on-site. A batch-loaded, two-stage, starved-air incinerator for solid combustible waste is one of the processes installed in this facility. The incinerator has been operating since 1982. It has consistently reduced combustible wastes to an inert ash product, with an average volume reduction factor of about 150:1. The incinerator ash is stored in 200 L drums awaiting solidification in bitumen. The incinerator and a 50-ton hydraulic baler have provided treatment for a combined volume of about 1300 m 3 /a of solid low-level radioactive waste. This paper presents a review of the performance of the incinerator during its six years of operation. In addition to presenting operational experience, an assessment of the starved-air incineration technique will also be discussed

  8. Liquid waste management at nuclear power plant with WWER

    International Nuclear Information System (INIS)

    Sabouni, Zahra.

    1995-07-01

    Management of radioactive wastes have become an area of ever increasing important in nuclear power plants. This is due to the fact that national and international regulations will only allow activity release to the environment based on ALARA principles. Radioactive liquids in the nuclear power plant originate as leakage from equipment, as drains from reactor and auxiliary systems, from decontamination and cleaning operations, from active laundry and from personnel showers. They will collected through the controlled zone of the plant in sumps and automatically pumped to large tanks and then to treatment system. The radioactive wastes are separated and categorized according to their main physical and chemical properties. Methods most frequently applied for low and intermediate level; liquid wastes are: chemical treatment (precipitation), ion exchange, and evaporation, and the decontamination ors are a few hundred, 10 2 -10 4 and 10 3 -10 6 , respectively. As a result of the treatment of radioactive liquids by mentioned methods a concentration of activity takes place in filter media, ion exchange resins, and evaporator concentrates. Before the semi-solid wastes shipped for storage, it has to be solidified in order to handle and transport in easier way. The solidification of wastes can take place by different methods. The general methods are: cementation, and bituminization processes. The selection of each process will depend on many factors which should be considered during the design phase. (author)

  9. Boesmanland gains from nuclear wastes

    International Nuclear Information System (INIS)

    Smit, I.

    1984-01-01

    It is being claimed that the geobotany of the Boesmanland will gain from the use of the farm Vaalputs for radioactive waste disposal from the Koeberg nuclear power station. Only 1 km 2 of the 10 000 ha that was bought for the purpose will be used for the disposal of low-level radioactive wastes and 2 m 3 to 3 m 3 per year will be used for the storage of high-level radioactive wastes. The rest of the area, Nucor plans to develop as a nature reserve, restoring the natural botany and ecology. Before Vaalputs was selected as site for radioactive waste disposal, a regional analysis was done. According to this there is more or less 500 people staying within a radius of 25km from the farm. Geological surveys showed no mineral deposits of economic value. During the past 100 million years the area was also free from seismic activity

  10. WWER nuclear waste management regulatory experience in Finland

    International Nuclear Information System (INIS)

    Varjoranta, Tero

    2000-01-01

    About 30% of all electricity produced in Finland is generated by nuclear power. Four reactors, with a total capacity of 2 656 MW e (net), are currently in operation. At Loviisa, there are two 488 MW e WWER units (recently upgraded 440-units) and at Olkiluoto two 840 MW e BWR units. At the Loviisa plant conditioning, storage and final disposal of low-and intermediate-level wastes from reactor operation will take place at the NPP sites. Intermediate level ion exchange resins and evaporation concentrates are currently stored in tanks. However, a license application for constructing a solidification plant based on cementation is currently under STUKs regulatory review. The construction of the final repository for I/LLW at the Loviisa site was started in 1993 and the Government granted the operating license in 1998. The nuclear legislation requires disposal of spent fuel into the Finnish bedrock. (Authors)

  11. Geopolitics of nuclear waste

    International Nuclear Information System (INIS)

    Marshall, E.

    1991-01-01

    More debate has begun over questions related to the safety of high-level waste disposal at the Yucca Mountain site in the Nevada desert. An engineering geologists, Jerry Szymanski, one of the Department of Energy's (DOE) own staffers in Las Vegas, has proposed that the $15-billion repository would sit on top of an intensely active structure that, if altered by an earthquake, would send a slug of ground water up from deep within the mountain into the waste storage area. This theory has already been slammed in two formal reviews and has virtually no support among geologists. However, enough doubt has been raised that much more geological testing will be necessary to prove or disprove Szymanski's theory. Nevada state officials are also using all methods to thwart or block the project. The question of the origin of a series of calcium carbonate and opal veins exposed in an exploratory pit, trench 14, near the top of the mountain is also far from answered. The DOE and US Geological Survey may have to collect much more information on the quantity, size, and location of carbonate sites in the area at a high financial outlay to the US government before a complete case on the origin of the material in trench 14 can be made

  12. Nuclear waste: Status of DOE's nuclear waste site characterization activities

    International Nuclear Information System (INIS)

    1987-01-01

    Three potential nuclear waste repository sites have been selected to carry out characterization activities-the detailed geological testing to determine the suitability of each site as a repository. The sites are Hanford in south-central Washington State, Yucca Mountain in southern Nevada, and Deaf Smith in the Texas Panhandle. Two key issues affecting the total program are the estimations of the site characterization completion data and costs and DOE's relationship with the Nuclear Regulatory Commission which has been limited and its relations with affected states and Indian tribes which continue to be difficult

  13. Nuclear wastes and public trust

    International Nuclear Information System (INIS)

    Flynn, J.; Slovic, P.

    1993-01-01

    Citing public fear and mistrust, strong opposition to the proposed Yucca Mountain repository site, and less-than-exemplary performance by the Department of Energy (DOE), two private researchers believe present high-level radioactive waste-disposal plans may have to be scrapped. Government and the nuclear industry may have to start over. Policy makers should seek to develop new relationships with communities and states where suitable disposal sites exist. These relationships may require that citizen groups and local institutions be given unprecedented authority in locating and operating such facilities. Contrary to popular impressions, there is still time to take a new approach. The US Nuclear Regulatory Commission says present on-site storage arrangements offer a safe alternative for 100 years or more. The sense of immediate crisis and cries for immediate solutions should be calmed and a more considered strategy brought to the public debate. For starters, the researchers propose that the problems of defense waste be separated from the problems of commercial waste. They also suggest that DOE be assigned responsibility for defense waste and a new agency be created to handle high-level commercial waste

  14. Waste from nuclear power plants

    International Nuclear Information System (INIS)

    1980-01-01

    The report presents proposals for organizing and financing of the treatment and deposition of spent fuel and radioactive waste. Decommissioning of plants is taken into consideration. The proposals refer to a program of twelve reactors. A relatively complete model for the handling of radioactive waste in Sweden is at hand. The cost for the years 1980 to 2000 is estimated at approx 1040 million SKr. Also the expense to dispose of the rest of the waste is calculated up to the year 2060, when the waste is planned to be put into final deposit. The state must have substantial influence over the organization which should be closely connected to the nuclear industry. Three different types of organization are discussed, namely (i) a company along with a newly created authority, (ii) a company along with the existing Nuclear Power Inspectorate or (iii) a company along with a board of experts. The proposals for financing the cost of handling nuclear waste are given in chief outlines. The nuclear industry should reserve means to special funds. The allocations are calculated to 1.4 oere per delivered kWh up to and including the year 1980. The accumulated allocations for 1979 should thus amount to 1310 million SKr. The charge for supervision and for certain research and development is recommended to be 0.1 oere per kWh which corresponds to approx 23 million SKr for 1980. The funds should be assured by binding agreements which must be approved by the state. The amounts are given in the monetary value of the year 1979. (G.B.)

  15. Nuclear waste and hazardous waste in the public perception

    Energy Technology Data Exchange (ETDEWEB)

    Kruetli, Pius; Seidl, Roman; Stauffacher, Michael [ETH Zurich (Switzerland). Inst. for Environmental Decisions

    2015-07-01

    The disposal of nuclear waste has gained attention of the public for decades. Accordingly, nuclear waste has been a prominent issue in natural, engineer and social science for many years. Although bearing risks for todays and future generations hazardous waste in contrast is much less an issue of public concern. In 2011, we conducted a postal survey among Swiss Germans (N = 3.082) to learn more about, how nuclear waste is perceived against hazardous waste. We created a questionnaire with two versions, nuclear waste and hazardous waste, respectively. Each version included an identical part with well-known explanatory factors for risk perception on each of the waste types separately and additional questions directly comparing the two waste types. Results show that basically both waste types are perceived similarly in terms of risk/benefit, emotion, trust, knowledge and responsibility. However, in the direct comparison of the two waste types a complete different pattern can be observed: Respondents perceive nuclear waste as more long-living, more dangerous, less controllable and it, furthermore, creates more negative emotions. On the other hand, respondents feel more responsible for hazardous waste and indicate to have more knowledge about this waste type. Moreover, nuclear waste is perceived as more carefully managed. We conclude that mechanisms driving risk perception are similar for both waste types but an overarching negative image of nuclear waste prevails. We propose that hazardous waste should be given more attention in the public as well as in science which may have implications on further management strategies of hazardous waste.

  16. Nuclear waste and hazardous waste in the public perception

    International Nuclear Information System (INIS)

    Kruetli, Pius; Seidl, Roman; Stauffacher, Michael

    2015-01-01

    The disposal of nuclear waste has gained attention of the public for decades. Accordingly, nuclear waste has been a prominent issue in natural, engineer and social science for many years. Although bearing risks for todays and future generations hazardous waste in contrast is much less an issue of public concern. In 2011, we conducted a postal survey among Swiss Germans (N = 3.082) to learn more about, how nuclear waste is perceived against hazardous waste. We created a questionnaire with two versions, nuclear waste and hazardous waste, respectively. Each version included an identical part with well-known explanatory factors for risk perception on each of the waste types separately and additional questions directly comparing the two waste types. Results show that basically both waste types are perceived similarly in terms of risk/benefit, emotion, trust, knowledge and responsibility. However, in the direct comparison of the two waste types a complete different pattern can be observed: Respondents perceive nuclear waste as more long-living, more dangerous, less controllable and it, furthermore, creates more negative emotions. On the other hand, respondents feel more responsible for hazardous waste and indicate to have more knowledge about this waste type. Moreover, nuclear waste is perceived as more carefully managed. We conclude that mechanisms driving risk perception are similar for both waste types but an overarching negative image of nuclear waste prevails. We propose that hazardous waste should be given more attention in the public as well as in science which may have implications on further management strategies of hazardous waste.

  17. The influence of radioactive waste solidification methods and storage conditions on the migration and dispersion of radionuclides in the terrestrial environment

    International Nuclear Information System (INIS)

    Golinski, M.; Ferenc, M.; Tomczak, W.; Cholerzynski, A.

    1979-01-01

    In the first part of the paper a survey of literature data on the methods and apparatus used for solidification of low- and intermediate-level radioactive wastes is done and the methods for the determination of the solidification product properties are discussed. The second part of the paper contains the experimental leachability data for 60 Co, 90 Sr and 137 Cs from simulated radioactive waste solidification products obtained with the help of bitumen, cement and urea formaldehyde resin. The leachability of radionuclides from the bituminization products decreases in the following order: 137 Cs 90 Sr 60 Co while that form concrete and the urea formaldehyde resin blocks as follows: 137 Cs 60 Co 90 Sr. A very good resistance of bitumen blocks against changeable atmospheric conditions and saline has been observed. The results obtained show that bitumen is the best binder while urea formaldehyde resin is the worst. (author)

  18. Nuclear waste disposal site

    International Nuclear Information System (INIS)

    Mallory, C.W.; Watts, R.E.; Sanner, W.S. Jr.; Paladino, J.B.; Lilley, A.W.; Winston, S.J.; Stricklin, B.C.; Razor, J.E.

    1988-01-01

    This patent describes a disposal site for the disposal of toxic or radioactive waste, comprising: (a) a trench in the earth having a substantially flat bottom lined with a layer of solid, fluent, coarse, granular material having a high hydraulic conductivity for obstructing any capillary-type flow of ground water to the interior of the trench; (b) a non-rigid, radiation-blocking cap formed from a first layer of alluvium, a second layer of solid, fluent, coarse, granular material having a high hydraulic conductivity for blocking any capillary-type flow of water between the layer of alluvium and the rest of the cap, a layer of water-shedding silt for directing surface water away from the trench, and a layer of rip-rap over the silt layer for protecting the silt layer from erosion and for providing a radiation barrier; (c) a solidly-packed array of abutting modules of uniform size and shape disposed in the trench and under the cap for both encapsulating the wastes from water and for structurally supporting the cap, wherein each module in the array is slidable movable in the vertical direction in order to allow the array of modules to flexibly conform to variations in the shape of the flat trench bottom caused by seismic disturbances and to facilitate the recoverability of the modules; (d) a layer of solid, fluent, coarse, granular materials having a high hydraulic conductivity in the space between the side of the modules and the walls of the trench for obstructing any capillary-type flow of ground water to the interior of the trench; and (e) a drain and wherein the layer of silt is sloped to direct surface water flowing over the cap into the drain

  19. Ethical aspects of nuclear waste

    International Nuclear Information System (INIS)

    Persson, L.

    1988-01-01

    The reasoning made by us leads to a double conclusion: a repository should be constructed so that controls and corrective measures are unnecessary, while at the same time not making them impossible. In other words, our generation should neither put the entire responsibility for maintenance of repositories in future generations' hands; nor should we deny future generations the possibility of taking control. By means of different formulations and by proceeding from various basic ideas, a dual objective is established about repository facilities: safety in operation combined with ease of service ability without mandatory but executable control. Prerequisities are the continued advancement of knowledge and refinement of the qualifications required to deal with nuclear waste. The ethical considerations should be included in the bases for future legislation on radioactive waste. Nuclear scientists should consider these points before they can form a foundation to the legislation process

  20. Nuclear waste forms for actinides

    Science.gov (United States)

    Ewing, Rodney C.

    1999-01-01

    The disposition of actinides, most recently 239Pu from dismantled nuclear weapons, requires effective containment of waste generated by the nuclear fuel cycle. Because actinides (e.g., 239Pu and 237Np) are long-lived, they have a major impact on risk assessments of geologic repositories. Thus, demonstrable, long-term chemical and mechanical durability are essential properties of waste forms for the immobilization of actinides. Mineralogic and geologic studies provide excellent candidate phases for immobilization and a unique database that cannot be duplicated by a purely materials science approach. The “mineralogic approach” is illustrated by a discussion of zircon as a phase for the immobilization of excess weapons plutonium. PMID:10097054

  1. Nuclear waste - where to go?

    International Nuclear Information System (INIS)

    Dornsiepen, Ulrich

    2015-01-01

    The question of the final di9sposal of nuclear waste is a problem of international importance. The solution of the problem is of increasing urgency; the discussion is controversial and implies a lot of emotions. In Germany there is consensus that the nuclear wastes have to be disposed within the country in deep geological formations. This kind of final disposal is predominantly a geological problem and has to be solved from the geological point of view. The geologist Ulrich Dornsiepen presents the problems of the final disposal in an objective way without ideology and generally understandable. Such a presentation is necessary since the public information and participation is demanded but the open geological questions and their scientific solutions are never explained for the public. [de

  2. Nuclear waste: A cancer cure?

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    In a marriage of strange bedfellows, scientists at one of the country's most contaminated nuclear waste sites are collaborating with medical researchers to turn nuclear waste into an experimental therapy for cancer. Patients with Hodgkin's disease and brain, ovarian, and breast cancers may be able to receive the new radiatio-based treatments in the next five to ten years. Recently, scientists at the Hanford site found a way to chemically extract a pure form of the radioisotope yttrium-90 from strontium-90, a by-product of plutonium production. Yttrium-90 is being tested in clinical trials at medical centers around the country as a treatment for various types of cancers, and the initial results are encouraging. The advantage of yttrium-90 over other radioisotopes is its short half-life

  3. Selection of a mineral binder for the stabilization - solidification of waste containing aluminum metal

    International Nuclear Information System (INIS)

    Lahalle, H.; Cau Dit Counes, C.; Lambertin, D.; Antonucci, P.; Delpech, S.

    2015-01-01

    The dismantling of nuclear facilities produces radioactive waste materials, some of which may contain aluminum metal. In a strongly alkaline medium, such as that encountered in conventional cementitious materials based on Portland cement, aluminum metal becomes corroded, with a continued production of dihydrogen. In order to develop a mineral matrix having enhanced compatibility with aluminum, a literature review was first undertaken to identify binders capable of reducing the pore solution pH compared with Portland cement. An experimental study was then carried out to measure the hydrogen production resulting from corrosion of aluminum metal rods encapsulated in the different selected cement pastes. The best results were achieved with magnesium phosphate cement, which released very little hydrogen over the duration of the study. This production could be reduced further by adding a corrosion inhibitor (lithium nitrate) to the mixing solution

  4. Statement of research in the field of solidification of high level radioactive wastes in France

    International Nuclear Information System (INIS)

    Bonniaud, R.; Sombret, C.

    1975-01-01

    Researches undertaken in France on the solidification of fission products are presented. Examples of glass compositions suitable for several types of fuels are given. The irradiation effects, crystallization, leaching and effects of α emitters have been studied. Two processes, one discontinuous, the other continuous have been studied and developed. In Marcoule, a continuous vitrification plant is under building and an experimental air-cooling storage is carried out [fr

  5. Feasibility study of solidification for low-level liquid waste generated by sulfuric acid elution treatment of spent ion exchange resin

    International Nuclear Information System (INIS)

    Asano, Takashi; Kawasaki, Tooru; Higuchi, Natsuko; Horikawa, Yoshihiko

    2008-01-01

    We studied cement-like solidification process for low-level liquid waste with relatively high levels of radioactivity that contains a high concentration of sodium sulfate. For this type waste, it is important that the sulfate ion should not dissolve from the solid waste because it forms ettringite on reaction with minerals in the concrete of the planned repository, and this leads to cracking during repository storage. It is also preferable that the pH of the pore water of the solid waste be low, because the bentonite of the repository changes in quality on exposure to alkaline solution. Therefore, the present solidification process has two procedures: conversion into insoluble sulfate from sodium sulfate (CIS) and formation of low pH cement-like solid (FLS). In the CIS procedure, BaSO 4 precipitation occurs with addition of Ba(OH) 2 ·8H 2 O to the liquid waste. In the FLS procedure, silica fume and blast furnace slag are added to the liquid waste containing BaSO 4 precipitate. We show the range of appropriate Ba/SO 4 molar ratio is from 1.1 to 1.5 in the present solidification process by leaching tests for some kinds of solid waste samples. The CIS reaction yield is over 98% at a typical CIS condition, i.e. Ba/SO 4 molar ratio=1.3, reaction temperature=60 deg C, and time=3 hr. (author)

  6. Nuclear waste management. Quarterly progress report, April-June 1979

    Energy Technology Data Exchange (ETDEWEB)

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

    1979-09-01

    Progress is reported on: decontamination and densification of chop-leach cladding residues; monitoring methods for particulate and gaseous effluents from waste solidification process; TRU waste immobilization; krypton solidification; /sup 14/C and /sup 129/I fixation; waste management system and safety studies; waste isolation safety assessment; well logging instrumentation development for shallow land burial; monitoring and physical characterization of unsaturated zone transport; detection and characterization of mobile organic complexes of fission products; and electropolishing for surface decontamination of metals. 9 figures, 14 tables. (DLC)

  7. Plasma filtering techniques for nuclear waste remediation.

    Science.gov (United States)

    Gueroult, Renaud; Hobbs, David T; Fisch, Nathaniel J

    2015-10-30

    Nuclear waste cleanup is challenged by the handling of feed stocks that are both unknown and complex. Plasma filtering, operating on dissociated elements, offers advantages over chemical methods in processing such wastes. The costs incurred by plasma mass filtering for nuclear waste pretreatment, before ultimate disposal, are similar to those for chemical pretreatment. However, significant savings might be achieved in minimizing the waste mass. This advantage may be realized over a large range of chemical waste compositions, thereby addressing the heterogeneity of legacy nuclear waste. Copyright © 2015 Elsevier B.V. All rights reserved.

  8. Nuclear waste management. Quarterly progress report, July-September 1980

    Energy Technology Data Exchange (ETDEWEB)

    Chikalla, T.D.

    1980-11-01

    Research is reported on: high-level waste immobilization, alternative waste forms, TRU waste immobilization and decontamination, krypton solidification, thermal outgassing, /sup 129/I fixation, unsaturated zone transport, well-logging instrumentation, waste management system and safety studies, effectiveness of geologic isolation systems, waste/rock interactions, engineered barriers, backfill material, spent fuel storage (criticality), barrier sealing and liners for U mill tailings, and revegetation of inactive U tailings sites. (DLC)

  9. Management of radioactive wastes from the nuclear fuel cycle

    International Nuclear Information System (INIS)

    1976-01-01

    The increased emphasis in many countries on the development and utilization of nuclear power is leading to an expansion of all sectors of the nuclear fuel cycle, giving rise to important policy issues and radioactive-waste management requirements. Consequently, the IAEA and the Nuclear Energy Agency of OECD felt that it would be timely to review latest technology for the management of the radioactive wastes arising from nuclear fuel cycle facilities, to identify where important advances have been made, and to indicate those areas where further technological development is needed. Beginning in 1959, the IAEA, either by itself or jointly with OECD/NEA has held seven international symposia on the management of radioactive wastes. The last symposium, on the management of radioactive wastes from fuel reprocessing, was held jointly by the IAEA and OECD/NEA in Paris in November 1972. An objective of the 1976 symposium was to update the information presented at the previous symposia with the latest technological developments and thinking regarding the management and disposal of all categories of radioactive wastes. Consequently, although the scope of the symposium was rather broad, attention was focussed on operational experience and progress in unresolved areas of radioactive waste management. The programme dealt primarily with the solidification of liquid radioactive wastes and disposal of the products, especially the high-level fission products and actinide-containing waste from fuel reprocessing. Other topics covered policy and planning, treatment of hulls and solvent, management of plutonium-contaminated waste, and removal of gaseous radionuclides. The major topic of interest was the current state of the technology for the reduction and incorporation of the high-level radioactive liquid from fuel reprocessing into solid forms, such as calcines, glasses or ceramics, for safe interim storage and eventual disposal. The approaches to vitrification ranged from two stage

  10. Nuclear waste transmutation

    International Nuclear Information System (INIS)

    Salvatores, M.; Girard, C.; Delpech, M.; Slessarev, I.; Tommasi, J.

    1994-01-01

    Waste management strategies foresee the use of a deep geological repository either for final disposal of irradiated fuel or, after reprocessing and reuse of U and Pu for final disposal of long-lived radio-active materials. In the second case, partitioning and transmutation of these materials can be considered to reduce the impact of radiation on man due to the storage. On the basis of the SPIN programme developed by CEA in this field, the main features of transmutation is presented. The goal to achieve and the criteria to use are quite difficult to establish. The rights para-meters to characterize the risk are the potential radiotoxicity in the the repository and the residual radiotoxicity at the outlet. Transmutation studies in CEA used the potential radiotoxicity which is based on well-known parameters and less precise hazardous factors. The second point to appreciate the trans- mutation interest is to dispose of a criteria for the radio-radiotoxicity reduction. As there is no general agreement, we try to have a toxicity as low as possible within reasonable technical limits. To reduce the long term radio- toxicity, Pu, minor actinides and some long-lived fission products have to be transmuted. To assess the feasibility of such trans-mutation in reactors or advanced systems, one has to consider constraints on neutronic balance, safety, fuel cycle, technology , economy. Taking in account the main conclusions of this analysis, parametric studies of homogeneous and heterogenous transmutation permit a choice of promising solutions. Goals are to use every long-lived element with a minimized production of other long- lived elements in order to obtain an appreciable radiotoxicity reduction. It implies multi recycling of Pu which favours fast neutron reactors and different strategies of multi recycling for Np, Am, Cm. Multi recycling makes the results strongly dependant of losses. Researches to obtain the high partitioning efficiency needed are in progress. Calculations

  11. The role of wastes from nuclear power plants in the overall management of radioactive wastes

    International Nuclear Information System (INIS)

    Krause, H.

    1983-01-01

    The wastes arising from nuclear power plants (NPP) are rather low in activity and the radionuclides contained therein have a low radiotoxicity and short half-life as a rule. However, NPPs are the largest in number among all nuclear facilities and produce the greatest amount of radioactive wastes. All NPPs have been able to keep the radiation doses in the environment below the permissible values, in most cases at 1 mrem/a or even lower. The methods applied for the treatment of liquid radioactive effluents have reached a high degree of effectivity and reliability. For the solidification of the residues several appropriate methods are available. However, some improvements are still desirable. Although methods exist for incineration, cutting and baling of solid wastes, only the last method is employed at NPPs as a rule. Central treatment facilities could improve this situation. The exhaust air treatment has reached a state that satisfies high standards during normal operation and in design base accidents. Improvements seem indicated regarding the in situ-inspection of HEPA-filters and the protection of filters against excess humidity and droplets. The partial and total decommissioning of NPPs has already been demonstrated. The problems caused by the wastes arising from such actions are in the same range as those from routine operation and maintenance of NPPs. Large amounts of radioactive wastes have already been disposed of by shallow land burial, disposal into deep geological formations or dumping into the deep sea. Specific standards could probably facilitate the disposal of wastes from NPPs. The present management of radioactive wastes from NPPs satisfies all actual needs. Therefore, spectacular new developments are neither required nor to be expected. However, by the continuous improvement of details and by optimization of the whole system progress can still be achieved and useful contributions to the further development of nuclear energy be made. (author)

  12. Nuclear wastes: fission

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    Progress is reported on investigations of transuranics in soils and plants that have demonstrated the importance of valence state, complexation, competing elements, migration down the soil profile, and weathering cycles in governing transuranic, 129 I and 99 Tc availability to plants and, in the case of Pu, to the consuming animals. In the latter case, it was demonstrated, for the first time, that ingestion of plant tissues containing Pu may result in greater transfer across the gut compared to gavaging animals with inorganic Pu solutions, underscoring the importance of detailed studies of the soil, plant, and animal factors influencing uptake by the ingestion pathway. Further evidence of the importance of the ingestion pathway was provided in studies of foliar interception of airborne transuranic elements in which it was shown that Pu in particles in the respiratory size range were effectively intercepted and retained by plants, and significant quantities of intercepted Pu were transported to roots and seeds. Similar studies on the terrestrial ingestion pathway have been initiated with other actinides including, U, Am, Cm, and Np. Radioecological field studies were directed toward establishment of pertinent ingestion pathways and exposure levels through description of habitat types, population densities, and, in several instances, dosimetry, for major insects, reptiles, birds, and mammalian species. These studies were extended to agricultural ecosystems through definition of the uptake of long-lived nuclides and digestibility in cattle of several forage species. In studies on a pond ecosystem at the nuclear fuel reprocessing plant, Pu and Am uptake rates were studied for major biotic components including organic floc, algae, fish, and ducks. The results indicated that assimilation of transuranics by the biota and export from the pond system were low compared to the total inventory

  13. Final disposal of nuclear waste

    Energy Technology Data Exchange (ETDEWEB)

    Anon,

    1995-10-01

    The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK).

  14. Final disposal of nuclear waste

    International Nuclear Information System (INIS)

    Anon.

    1995-01-01

    The nuclear industry argues that high level radioactive waste can be safely disposed of in deep underground repositories. As yet, however, no such repositories are in use and the amount of spent nuclear fuel in ponds and dry storage is steadily increasing. Although the nuclear industry further argues that storage is a safe option for up to 50 years and has the merit of allowing the radioactivity of the fuel to decay to a more manageable level, the situation seems to be far from ideal. The real reasons for procrastination over deep disposal seem to have as much to do with politics as safe technology. The progress of different countries in finding a solution to the final disposal of high level waste is examined. In some, notably the countries of the former Soviet Union, cost is a barrier; in others, the problem has not yet been faced. In these countries undertaking serious research into deep disposal there has been a tendency, in the face of opposition from environmental groups, to retreat to sites close to existing nuclear installations and to set up rock laboratories to characterize them. These sites are not necessarily the best geologically, but the laboratories may end up being converted into actual repositories because of the considerable financial investment they represent. (UK)

  15. Organic diagenesis in commercial nuclear wastes

    International Nuclear Information System (INIS)

    Toste, A.P.; Lechner-Fish, T.J.

    1988-01-01

    The nuclear industry currently faces numerous challenges. Large volumes of already existing wastes must be permanently disposed using environmentally acceptable technologies. Numerous criteria must be addressed before wastes can be permanently disposed. Waste characterization is certainly one of the key criteria for proper waste management. some wastes are complex melting pots of inorganics, radiochemicals, and, occasionally, organics. It is clear, for example, that organics have been used extensively in nuclear operations, such as waste reprocessing, and continue to be used widely as solvents, decontamination agents, etc. The authors have analyzed the organic content of many kinds of nuclear wastes, ranging from commercial to defense wastes. In this paper, the finale analyses are described of three commercial wastes: one waste from a pressurized water reactor (PWR) and two wastes from a boiling water reactor (BWR). The PWR waste is a boric acid concentrate waste. The two BWR wastes, BWR wastes Nos. 1 and 2, are evaporator concentrates of liquid wastes produced during the regeneration of ion-exchange resins used to purify reactor process water. In preliminary analyses, which were reported previously, a few know organics and myriad unknowns were detected. Recent reexamination of mass-spectral data, coupled with reanalysis of the wastes, has resulted in the firm identification of the unknowns. Most of the compounds, over thirty distinct organics, are derived from the degradation, or diagenesis, of source-term organics, revealing, for the first time, that organic diagenesis in commercial wastes is both vigorous and varied

  16. Waste management in the nuclear engineering curriculum

    International Nuclear Information System (INIS)

    Tulenko, J.S.

    1989-01-01

    One of the most significant challenges facing the nuclear industry is to successfully close the nuclear fuel cycle and effectively demonstrate to the public that nuclear wastes do not present a health risk. This issue is currently viewed by many as the most important issue affecting public acceptance of nuclear power, and it is imperative that nuclear engineers be able to effectively address the question of nuclear waste from both a generation and disposal standpoint. To address the issue, the area of nuclear waste management has been made one of the fields of specialized study in the Department of Nuclear Engineering Sciences at the University of Florida. The study of radioactive waste management at the University of Florida is designed both for background for the general nuclear engineering student and for those wishing to specialize in it as a multidiscipline study area involving the Departments of Nuclear Engineering Sciences, Environmental Sciences, Material Science and Engineering, Geology, Civil Engineering, and Industrial Engineering

  17. Attitudes of the public about nuclear wastes

    International Nuclear Information System (INIS)

    Rankin, W.L.; Nealey, S.M.

    1978-01-01

    The disposal of nuclear wastes has become an important public issue in the past few years. In 1960, only a very small percentage of the American public questioned the safety of waste disposal methods, and no one opposed nuclear power for waste disposal reasons. By 1974, however, a slight majority of the public believed that the disposal of nuclear wastes was a serious problem associated with nuclear power, and from 1975 on, a small percentage of the public has opposed nuclear power for waste disposal reasons. More individuals believe that the technology is not available for acceptable waste management compared to the number of individuals who believe that the technology does exist. However, a majority of the public believe that modern technology can solve the waste disposal problem. Finally, nuclear technologists evaluate waste disposal problems differently from other groups. For instance, nuclear technologists believe that short-term safety is more important than long-term safety regarding waste disposal, while other groups, especially environmentalists, believe that long-term safety is more important than short-term safety. Nuclear technologists are willing to accept a higher level of waste management-related risk than other groups and evaluate waste disposal problems as being less severe than other societal problems

  18. Ceramic process and plant design for high-level nuclear waste immobilization

    International Nuclear Information System (INIS)

    Grantham, L.F.; McKisson, R.L.; De Wames, R.E.; Guon, J.; Flintoff, J.F.; McKenzie, D.E.

    1983-01-01

    In the last 3 years, significant advances in ceramic technology for high-level nuclear waste solidification have been made. Product quality in terms of leach-resistance, compositional uniformity, structural integrity, and thermal stability promises to be superior to borosilicate glass. This paper addresses the process effectiveness and preliminary designs for glass and ceramic immobilization plants. The reference two-step ceramic process utilizes fluid-bed calcination (FBC) and hot isostatic press (HIP) consolidation. Full-scale demonstration of these well-developed processing steps has been established at DOE and/or commercial facilities for processing radioactive materials. Based on Savannah River-type waste, our model predicts that the capital and operating cost for the solidification of high-level nuclear waste is about the same for the ceramic and glass options. However, when repository costs are included, the ceramic option potentially offers significantly better economics due to its high waste loading and volume reduction. Volume reduction impacts several figures of merit in addition to cost such as system logistics, storage, transportation, and risk. The study concludes that the ceramic product/process has many potential advantages, and rapid deployment of the technology could be realized due to full-scale demonstrations of FBC and HIP technology in radioactive environments. Based on our finding and those of others, the ceramic innovation not only offers a viable backup to the glass reference process but promises to be a viable future option for new high-level nuclear waste management opportunities

  19. Chemical risks from nuclear waste repositories

    International Nuclear Information System (INIS)

    Persson, L.

    1988-01-01

    Studies concerning the chemical risks of nuclear waste are reviewed. The radiological toxicity of the material is of primary concern but the potential nonradiological toxicity should not be overlooked as the chemotoxic substances may reach the biosphere from a nuclear waste repository. In the report is concluded that the possible chemotoxic effects of a repository for nuclear waste should be studied as a part of the formal risk assessment of the disposal concept. (author)

  20. Sedimentary modelling and nuclear-waste disposal

    International Nuclear Information System (INIS)

    Van Loon, A.J.

    1982-01-01

    Nuclear energy is an important source of energy. Recently a slow down is experienced in its growth rate, due to the following factors: a) the supposed shortage of uranium; b) the fear for the consequences of nuclear accident, and c) the problem of nuclear wastes. Two types of waste are distinguished: a) fission products and actinides, and b) operational waste. The United States have started a program that must lead in 1989 to the first final storage of such waste in salt. Open-pit mines and oil-well drilling are discussed as possible solutions for operational waste storage

  1. Transmutation of nuclear waste in nuclear reactors

    International Nuclear Information System (INIS)

    Abrahams, K.; Kloosterman, J.L.; Pilate, S.; Wehmann, U.K.

    1996-03-01

    The objective of this joint study of ECN, Belgonucleaire, and Siemens is to investigate possibilities for transmutation of nuclear waste in regular nuclear reactors or in special transmutation devices. Studies of possibilities included the limits and technological development steps which would be needed. Burning plutonium in fast reactors, gas-cooled high-temperature reactors and light water reactors (LWR) have been considered. For minor actinides the transmutation rate mainly depends on the content of the minor actinides in the reactor and to a much less degree on the fact whether one uses a homogeneous system (with the actinides mixed into the fuel) or a heterogeneous system. If one wishes to stabilise the amount of actinides from the present LWRs, about 20% of all nuclear power would have to be generated in special burner reactors. It turned out that reactor transmutation of fission products would require considerable recycling efforts and that the time needed for a substantial transmutation would be rather long for the presently available levels of the neutron flux. If one would like to design burner systems which can serve more light water reactors, a large effort would be needed and other burners (possibly driven by accelerators) should be considered. (orig.)

  2. Low-level radwaste solidification

    International Nuclear Information System (INIS)

    Naughton, M.D.; Miller, C.C.; Nelson, R.A.; Tucker, R.F.

    1983-01-01

    This paper reports on a study of ''Advanced Low-Level Radioactive Waste Treatment Systems'' conducted under an EPRI contract. The object of the study is to identify advanced lowlevel radwaste treatment systems that are commercially available or are expected to be in the near future. The current state-ofthe-art in radwaste solidification technology is presented. Related processing technologies, such as the compaction of dry active waste (DAW), containers available for radwaste disposal, and the regulatory aspects of radwaste transportation and solidification, are described. The chemical and physical properties of the currently acceptable solidification agents, as identified in the Barnwell radwaste burial site license, are examined. The solidification agents investigated are hydraulic cements, thermoplastic polymers, and thermosetting polymers. It is concluded that solidification processes are complex and depend not only on the chemical and physical properties of the binder material and the waste, but also on how these materials are mixed

  3. SRTC criticality safety technical review: Nuclear criticality safety evaluation 94-02, uranium solidification facility pencil tank module spacing

    International Nuclear Information System (INIS)

    Rathbun, R.

    1994-01-01

    Review of NMP-NCS-94-0087, ''Nuclear Criticality Safety Evaluation 94-02: Uranium Solidification Facility Pencil Tank Module Spacing (U), April 18, 1994,'' was requested of the SRTC Applied Physics Group. The NCSE is a criticality assessment to show that the USF process module spacing, as given in Non-Conformance Report SHM-0045, remains safe for operation. The NCSE under review concludes that the module spacing as given in Non-Conformance Report SHM-0045 remains in a critically safe configuration for all normal and single credible abnormal conditions. After a thorough review of the NCSE, this reviewer agrees with that conclusion

  4. Global Nuclear Energy Partnership Waste Treatment Baseline

    International Nuclear Information System (INIS)

    Gombert, Dirk; Ebert, William; Marra, James; Jubin, Robert; Vienna, John

    2008-01-01

    The Global Nuclear Energy Partnership (GNEP) program is designed to demonstrate that a proliferation-resistant and sustainable integrated nuclear fuel cycle can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline set of waste forms was recommended for the safe disposition of waste streams. Specific waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and expected performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms. (authors)

  5. Global Nuclear Energy Partnership Waste Treatment Baseline

    Energy Technology Data Exchange (ETDEWEB)

    Gombert, Dirk; Ebert, William; Marra, James; Jubin, Robert; Vienna, John [Idaho National laboratory, 2525 Fremont Ave., Idaho Falls, ID 83402 (United States)

    2008-07-01

    The Global Nuclear Energy Partnership (GNEP) program is designed to demonstrate that a proliferation-resistant and sustainable integrated nuclear fuel cycle can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline set of waste forms was recommended for the safe disposition of waste streams. Specific waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and expected performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms. (authors)

  6. Global Nuclear Energy Partnership Waste Treatment Baseline

    Energy Technology Data Exchange (ETDEWEB)

    Dirk Gombert; William Ebert; James Marra; Robert Jubin; John Vienna

    2008-05-01

    The Global Nuclear Energy Partnership program (GNEP) is designed to demonstrate a proliferation-resistant and sustainable integrated nuclear fuel cycle that can be commercialized and used internationally. Alternative stabilization concepts for byproducts and waste streams generated by fuel recycling processes were evaluated and a baseline of waste forms was recommended for the safe disposition of waste streams. Waste forms are recommended based on the demonstrated or expected commercial practicability and technical maturity of the processes needed to make the waste forms, and performance of the waste form materials when disposed. Significant issues remain in developing technologies to process some of the wastes into the recommended waste forms, and a detailed analysis of technology readiness and availability may lead to the choice of a different waste form than what is recommended herein. Evolving regulations could also affect the selection of waste forms.

  7. Radioactive waste management in nuclear power plants with WWER-type reactors

    Energy Technology Data Exchange (ETDEWEB)

    Dlouhy, Z; Napravnik, J; Safar, O

    1975-05-01

    The possibilities of radioactive waste solidification in nuclear power plants with LWR reactors (of the WWER type) and the problems of their safe storage in Czechoslovakia are discussed. The most suitable method for the treatment of emitted sorbents and concentrates seems to be their incorporation in bitumen or concrete. In the disposal of solidified blocks all requirements should be met including the selection of suitable sites and of convenient methods of transportation. A preliminary economic estimate shows that the storage of bitumen-incorporated wastes in trenches seems to be less expensive from the point of view of exploitation of the storage facility as well as from the point of view of investment.

  8. Polymer solidification national program

    International Nuclear Information System (INIS)

    Kalb, P.D.; Colombo, P.

    1993-04-01

    Brookhaven National Laboratory (BNL) has developed several new and innovative polymer processes for the solidification of low-level radioactive, hazardous and mixed wastes streams. Polyethylene and modified sulfur cement solidification technologies have undergone steady, gradual development at BNL over the past nine years. During this time they have progressed through each of the stages necessary for logical technology maturation: from process conception, parameter optimization, waste form testing, evaluation of long-term durability, economic analysis, and scale-up feasibility. This technology development represents a significant investment which can potentially provide DOE with both short- and long-term savings

  9. Nuclear waste management, reactor decommisioning, nuclear liability and public attitudes

    International Nuclear Information System (INIS)

    Green, R.E.

    1982-01-01

    This paper deals with several issues that are frequently raised by the public in any discussion of nuclear energy, and explores some aspects of public attitudes towards nuclear-related activities. The characteristics of the three types of waste associated with the nuclear fuel cycle, i.e. mine/mill tailings, reactor wastes and nuclear fuel wastes, are defined, and the methods currently being proposed for their safe handling and disposal are outlined. The activities associated with reactor decommissioning are also described, as well as the Canadian approach to nuclear liability. The costs associated with nuclear waste management, reactor decommissioning and nuclear liability are also discussed. Finally, the issue of public attitudes towards nuclear energy is addressed. It is concluded that a simple and comprehensive information program is needed to overcome many of the misconceptions that exist about nuclear energy and to provide the public with a more balanced information base on which to make decisions

  10. Small hazardous waste generators in developing countries: use of stabilization/solidification process as an economic tool for metal wastewater treatment and appropriate sludge disposal.

    Science.gov (United States)

    Silva, Marcos A R; Mater, Luciana; Souza-Sierra, Maria M; Corrêa, Albertina X R; Sperb, Rafael; Radetski, Claudemir M

    2007-08-25

    The aim of this study was to propose a profitable destination for an industrial sludge that can cover the wastewater treatment costs of small waste generators. Optimized stabilization/solidification technology was used to treat hazardous waste from an electroplating industry that is currently released untreated to the environment. The stabilized/solidified (S/S) waste product was used as a raw material to build concrete blocks, to be sold as pavement blocks or used in roadbeds and/or parking lots. The quality of the blocks containing a mixture of cement, lime, clay and waste was evaluated by means of leaching and solubility tests according to the current Brazilian waste regulations. Results showed very low metal leachability and solubility of the block constituents, indicating a low environmental impact. Concerning economic benefits from the S/S process and reuse of the resultant product, the cost of untreated heavy metal-containing sludge disposal to landfill is usually on the order of US$ 150-200 per tonne of waste, while 1tonne of concrete roadbed blocks (with 25% of S/S waste constitution) has a value of around US$ 100. The results of this work showed that the cement, clay and lime-based process of stabilization/solidification of hazardous waste sludge is sufficiently effective and economically viable to stimulate the treatment of wastewater from small industrial waste generators.

  11. Nuclear energy from radioactive waste

    International Nuclear Information System (INIS)

    Schwarzenberg, M.

    1998-01-01

    The global energy demand is increasing. Sound forecasts indicate that by the year 2020 almost eight thousand million people will be living on our planet, and generating their demand for energy will require conversion of about 20 thousand million tonnes of coal equivalents a year. Against this background scenario, a new concept for energy generation elaborated by nuclear scientists at CERN attracts particular interest. The concept describing a new nuclear energy source and technology intends to meet the following principal requirements: create a new energy source that can be exploited in compliance with extremely stringent safety requirements; reduce the amount of long-lived radioactive waste; substantially reduce the size of required radwaste repositories; use easily available natural fuels that will not need isotopic separation; prevent the risk of proliferation of radioactive materials; process and reduce unwanted actinides as are generated by the operation of current breeder reactors; achieve high efficiency both in terms of technology and economics. (orig./CB) [de

  12. Questioning nuclear waste substitution: a case study.

    Science.gov (United States)

    Marshall, Alan

    2007-03-01

    This article looks at the ethical quandaries, and their social and political context, which emerge as a result of international nuclear waste substitution. In particular it addresses the dilemmas inherent within the proposed return of nuclear waste owned by Japanese nuclear companies and currently stored in the United Kingdom. The UK company responsible for this waste, British Nuclear Fuels Limited (BNFL), wish to substitute this high volume intermediate-level Japanese-owned radioactive waste for a much lower volume of much more highly radioactive waste. Special focus is given to ethical problems that they, and the UK government, have not wished to address as they move forward with waste substitution. The conclusion is that waste substitution can only be considered an ethical practice if a set of moderating conditions are observed by all parties. These conditions are listed and, as of yet, they are not being observed.

  13. Nuclear waste disposal: Gambling on Yucca Mountain

    International Nuclear Information System (INIS)

    Ginsburg, S.

    1995-01-01

    This document describes the historical aspects of nuclear energy ,nuclear weapons usage, and development of the nuclear bureaucracy in the United States, and discusses the selection and siting of Yucca Mountain, Nevada for a federal nuclear waste repository. Litigation regarding the site selection and resulting battles in the political arena and in the Nevada State Legislature are also presented. Alternative radioactive waste disposal options, risk assessments of the Yucca Mountain site, and logistics regarding the transportation and storage of nuclear waste are also presented. This document also contains an extensive bibliography

  14. Cementation and solidification of miscellaneous mixed wastes at the Rocky Flats Environmental Technology Site

    International Nuclear Information System (INIS)

    Phillips, J.A.; Semones, G.B.

    1995-01-01

    The Rocky Flats Environmental Technology Site produces a variety of wastes which are amenable to micro-encapsulation in cement Portland cement is an inexpensive and readily available material for this application. The Waste Projects (WP) group at Rocky Flats evaluated cementation to determine its effectiveness in encapsulating several wastes. These included waste analytical laboratory solutions, incinerator ash, hydroxide precipitation sludge, and an acidic solution from the Delphi process (a chemical oxidation technology being evaluated as an alternative to incineration). WP prepared surrogate wastes and conducted designed experiments to optimize the cement formulation for the waste streams. These experiments used a Taguchi or factorial experimental design, interactions between the variables were also considered in the testing. Surrogate waste samples were spiked with various levels of each of six Resource Conservation and Recovery Act (RCRA) listed metals (Cd, Cr, Ba, Pb, Ni, and Ag), cemented using the optimized formulation, and analyzed for leach resistance using the Toxicity Characteristic Leaching Procedure (TCLP). The metal spike levels chosen were based on characterization data, and also based on an estimate of the highest levels of contaminants suspected in the waste. This paper includes laboratory test results for each waste studied. These include qualitative observations as well as quantitative data from TCLP analyses and environmental cycling studies. The results from these experiments show that cement stabilization of the different wastes can produce final waste forms which meet the current RCRA Land Disposal Restriction (LDR) requirements. Formulations that resulted in LDR compliant waste forms are provided. The volume increases associated with cementation are also lower than anticipated. Future work will include verification studies with actual mixed radioactive waste as well as additional formulation development studies on other waste streams

  15. Development of comprehensive waste acceptance criteria for commercial nuclear waste

    International Nuclear Information System (INIS)

    O'Hara, F.A.; Miller, N.E.; Ausmus, B.S.; Yates, K.R.; Means, J.L.; Christensen, R.N.; Kulacki, F.A.

    1979-01-01

    A detailed methodology is presented for the identification of the characteristics of commercial nuclear waste which may require criteria. This methodology is analyzed as a six-step process which begins with identification of waste operations and proceeds until the waste characteristics affecting the potential release of radionuclides are determined. All waste types and operations were analyzed using the methodology presented. Several illustrative example are included. It is found that thirty-three characteristics can be identified as possibly requiring criteria

  16. Cementitions materials in nuclear waste management

    International Nuclear Information System (INIS)

    Roy, D.M.

    1990-01-01

    Cementitious materials have been investigated extensively to establish their role, and enable a prediction of their performance, when used for radioactive waste isolation. A number of applications have been addressed, ranging from those in high-level waste management, where their prime roles would be physical such as in sealing an underground waste repository, mechanical to serve as a protective cask for transport, or under certain conditions, both chemical and physical in the solidification of high-level waste. Cements also have been explored for their use in forming primary casks for containment of spent fuel assemblies. For the disposal of low-level (and in some countries, intermediate-level) waste, a cementitious matrix may be used to encapsulate the waste, thereby generating an integral waste form. In addition, concretes will be required to perform special structural roles, used to construct trenches, vaults, and other disposal units. Also, there are numerous applications where grouts are used for sealing purposes. This paper addresses each of these areas

  17. Nuclear waste repository simulation experiments

    International Nuclear Information System (INIS)

    Rothfuchs, T.; Wieczorek, K.; Feddersen, H.K.; Staupendahl, G.; Coyle, A.J.; Kalia, H.; Eckert, J.

    1986-12-01

    This document is the third joint annual report on the Cooperative German-American 'Brine Migration Tests' that are in progress at the Asse salt mine in the Federal Republic of Germany (FRG). This Government supported mine serves as an underground test facility for research and development (R and D)-work in the field of nuclear waste repository research and simulation experiments. The tests are designed to simulate a nuclear waste repository to measure the effects of heat and gamma radiation on brine migration, salt decrepitation, disassociation of brine, and gases collected. The thermal mechanical behavior of salt, such as room closure, stresses and changes of the properties of salt are measured and compared with predicted behavior. This document covers the following sections: Issues and test objectives: This section presents issues that are investigated by the Brine Migration Test, and the test objectives derived from these issues; test site: This section describes the test site location and geology in the Asse mine; test description: A description of the test configuration, procedures, equipment, and instrumentation is given in this section; actual test chronology: The actual history of the test, in terms of the dates at which major activities occured, is presented in this section. Test results: This section presents the test results observed to data and the planned future work that is needed to complete the test; conclusions and recommendations: This section summarizes the conclusions derived to date regarding the Brine Migration Test. Additional work that would be useful to resolve the issues is discussed. (orig.)

  18. Organic analyses of mixed nuclear wastes

    International Nuclear Information System (INIS)

    Toste, A.P.; Lucke, R.B.; Lechner-Fish, T.J.; Hendren, D.J.; Myers, R.B.

    1987-04-01

    Analytical methods are being developed for the organic analysis of nuclear wastes. Our laboratory analyzed the organic content of three commercial wastes and an organic-rich, complex concentrate waste. The commercial wastes contained a variety of hydrophobic and hydrophilic organics, at concentrations ranging from nanomolar to micromolar. Alkyl phenols, chelating and complexing agents, as well as their degradation products, and carboxylic acids were detected in the commercial wastes. The complex concentrate waste contained chelating and complexing agents, as well as numerous degradation products, at millimolar concentrations. 75.1% of the complex concentrate waste's total organic carbon content has been identified. The presence of chelator fragments in all of the wastes analyzed, occasionally at elevated concentrations, indicates that organic diagenesis, or degradation, in nuclear wastes is both widespread and quite vigorous. 23 refs., 3 tabs

  19. Transport and nuclear waste disposal

    International Nuclear Information System (INIS)

    Wild, E.

    1999-01-01

    The author assesses both past and future of nuclear waste disposal in Germany. The failure of the disposal concept is, he believes, mainly the fault of the Federal Government. On the basis of the Nuclear Energy Act, the government is obliged to ensure that ultimate-storage sites are established and operated. Up to the present, however, the government has failed - apart from the episode in Asse and Morsleben and espite existing feasible proposals in Konrad and Gorleben - to achieve this objective. This negative development is particularly evident from the projects which have had to be prematurely abandoned. The costs of such 'investment follies' meanwhile amount to several billion DM. At least 92% of the capacity in the intermediate-storage sites are at present unused. Following the closure of the ultimate-storage site in Morsleben, action must be taken to change over to long-term intermediate-storage of operational waste. The government has extensive intermediate-storage capacity at the intermediate-storage site Nord in Greifswald. There, the wate originally planned for storage in Morsleben could be intermediately stored at ERAM-rates. Nuclear waste transportation, too, could long ago have been resumed, in the author's view. For the purpose of improving the transport organisation, a new company was founded which represents exclusively the interests of the reprocessing firms at the nuclear power stations. The author's conclusion: The EVU have done their homework properly and implemented all necessary measures in order to be able to resume transport of fuel elements as soon as possible. The generating station operators favour a solution based upon agreement with the Federal Government. The EVU have already declared their willingness - in the event of unanimous agreement - to set up intermediate-storage sites near the power stations. The ponds in the generating stations, however, are unsuitable for use as intermediate-storage areas. If intermediate-storage areas for

  20. State of nuclear waste management of German nuclear power stations

    International Nuclear Information System (INIS)

    1983-01-01

    The waste management of nuclear power plants in the Federal Republic of Germany is today prevailing in the public discussion. Objections raised in this connection, e.g. that the nuclear waste management has been omitted from the development of peaceful utilization of nuclear energy or remained insolved, are frequently accepted without examination, and partly spread as facts. This is, however, not the truth: From the outset in 1955 the development of nuclear technology in the Federal Republic of Germany has included investigations of the problems of reprocessing and non-detrimental disposal of radioactive products, and the results have been compiled in a national nuclear waste management concept. (orig.) [de

  1. Proposal of Solidification/Stabilisation Process of Chosen Hazardous Waste by Cementation

    OpenAIRE

    Bozena Dohnalkova

    2015-01-01

    This paper presents a part of the project solving which is dedicated to the identification of the hazardous waste with the most critical production within the Czech Republic with the aim to study and find the optimal composition of the cement matrix that will ensure maximum content disposal of chosen hazardous waste. In the first stage of project solving – which represents this paper – a specific hazardous waste was chosen, its properties were identified and suitable soli...

  2. Nuclear waste in public acceptance

    International Nuclear Information System (INIS)

    Vastchenko, Svetlana V.

    2003-01-01

    The existing problem on a faithful acceptance of nuclear information by population is connected, to a considerable extent, with a bad nuclear 'reputation' because of a great amount of misrepresented and false information from 'the greens'. In contrast to a bare style of professionals often neglecting an emotional perception, a loud voice of 'the greens' appeals both to the head, and to the heart of the audience. People pattern their behaviour weakly on problems of safe application of different irradiation sources in industry, conditions of life, medicine and everyday life. Radiation danger of some sources is often exaggerated (computers, nuclear technologies, radiation treatment) and the danger of the others is, on the contrary, underestimated (nuclear and roentgen methods of diagnostics and medical treatment). The majority of our citizens do not know which level of radiation is normal and safe, which ways radioactive substances intake into the organism of a human being and how to diminish the dose load on the organism by simple measures. Only specialists can be orientated themselves in a great number of radiation units. Low level of knowledge of the population and false conceptions are connected with the fact that they are mainly informed about nuclear technologies from mass media, where the voice of 'Greenpeace' is loudly sounded, but they often give misrepresented and false information doing it in the very emotional form. In contrast to them, scientists-professionals often ignore a sensitive part of apprehending of information and do not attach importance to it. As a rule, the style of specialists is of a serious academician character when they meet with the public. People preconception to nuclear waste and distrust to a positive information concerning nuclear technologies are explained, to a considerable extent, by a bivalent type of thinking when people operate by two opposite conceptions only, such as 'there is' or 'there is not' (there is or there is not

  3. Nuclear waste in public acceptance

    Energy Technology Data Exchange (ETDEWEB)

    Vastchenko, Svetlana V. [Joint Institute for Power and Nuclear Research - Sosny / National Academy of Science, A.K.Krasin Str., 99, Minsk 220109 (Belarus)

    2003-07-01

    The existing problem on a faithful acceptance of nuclear information by population is connected, to a considerable extent, with a bad nuclear 'reputation' because of a great amount of misrepresented and false information from 'the greens'. In contrast to a bare style of professionals often neglecting an emotional perception, a loud voice of 'the greens' appeals both to the head, and to the heart of the audience. People pattern their behaviour weakly on problems of safe application of different irradiation sources in industry, conditions of life, medicine and everyday life. Radiation danger of some sources is often exaggerated (computers, nuclear technologies, radiation treatment) and the danger of the others is, on the contrary, underestimated (nuclear and roentgen methods of diagnostics and medical treatment). The majority of our citizens do not know which level of radiation is normal and safe, which ways radioactive substances intake into the organism of a human being and how to diminish the dose load on the organism by simple measures. Only specialists can be orientated themselves in a great number of radiation units. Low level of knowledge of the population and false conceptions are connected with the fact that they are mainly informed about nuclear technologies from mass media, where the voice of 'Greenpeace' is loudly sounded, but they often give misrepresented and false information doing it in the very emotional form. In contrast to them, scientists-professionals often ignore a sensitive part of apprehending of information and do not attach importance to it. As a rule, the style of specialists is of a serious academician character when they meet with the public. People preconception to nuclear waste and distrust to a positive information concerning nuclear technologies are explained, to a considerable extent, by a bivalent type of thinking when people operate by two opposite conceptions only, such as 'there is

  4. Nuclear waste and nuclear ethics. Societal and ethical aspects of retrievable storage of nuclear waste

    International Nuclear Information System (INIS)

    Damveld, H.; Van den Berg, R.J.

    2000-01-01

    The aim of the literature study on the title subject is to provide information to researchers, engineers, decision makers, administrators, and the public in the Netherlands on the subject of retrievable storage of nuclear waste, mainly from nuclear power plants. Conclusions and recommendations are formulated with respect to retrievability and ethics, sustainability, risk assessment, information transfer, environmental impacts, and discussions on radioactive waste storage. 170 refs

  5. The politics of nuclear-waste disposal

    International Nuclear Information System (INIS)

    Tarricone, P.

    1994-01-01

    After 72 days of public hearings and testimony from more than 100 witnesses, the first commission of its kind in the US found that politics--not science and engineering--led to the selection of Martinsville, Ill. as the host site for a nuclear-waste-disposal facility. This article examines how the plan to dispose of nuclear waste in Martinsville ultimately unraveled

  6. Waste management and the nuclear fuel cycle

    International Nuclear Information System (INIS)

    Molinari, J.

    1982-01-01

    The present lecture deals with energy needs and nuclear power, the importance of waste and its relative place in the fuel cycle, the games of controversies over nuclear waste in the strategies of energy and finally with missions and functions of the IAEA for privileging the rational approach and facilitating the transfer of technology. (RW)

  7. Concept for Underground Disposal of Nuclear Waste

    Science.gov (United States)

    Bowyer, J. M.

    1987-01-01

    Packaged waste placed in empty oil-shale mines. Concept for disposal of nuclear waste economically synergistic with earlier proposal concerning backfilling of oil-shale mines. New disposal concept superior to earlier schemes for disposal in hard-rock and salt mines because less uncertainty about ability of oil-shale mine to contain waste safely for millenium.

  8. An introduction to nuclear waste immobilisation

    International Nuclear Information System (INIS)

    Ojovan, M.I.; Lee, W.E.

    2005-08-01

    Safety and environmental impact is of uppermost concern when dealing with the movement and storage of nuclear waste. The 20 chapters in this book cover all important aspects of immobilisation, from nuclear decay, to regulations, to new technologies and methods. Significant focus is given to the analysis of the various matrices used in transport: cement, bitumen and glass, with the greatest attention being given to glass. The last chapter concentrates on the performance assessment of each matrix, and on new developments of ceramics and glass composite materials, thermochemical methods and in-situ metal matrix immobilisation. The book thoroughly covers all issues surrounding nuclear waste: from where to locate nuclear waste in the environment, through nuclear waste generation and sources, treatment schemes and technologies, immobilisation technologies and waste forms, disposal and long term behaviour. Particular attention is paid to internationally approved and worldwide-applied approaches and technologies

  9. The political challenges of nuclear waste

    International Nuclear Information System (INIS)

    Andren, Mats; Strandberg, Urban

    2005-01-01

    This anthology is made up of nine essays on the nuclear waste issue, both its political, social and technical aspects, with the aim to create a platform for debate and planning of research. The contributions are titled: 'From clean energy to dangerous waste - the regulatory management of nuclear power in the Swedish welfare society. An economic-historic review , 'The course of the high-level waste into the national political arena', 'The technical principles behind the Swedish repository for spent fuels', 'Waste, legitimacy and local citizenship', 'Nuclear issues in societal planning', 'Usefulness or riddance - transmutation or just disposal?', 'National nuclear fuel policy in an European Union?', 'Conclusion - the challenges of the nuclear waste issue', 'Final words - about the need for critical debate and multi-disciplinary research'

  10. 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.)

  11. Safety Aspects of Nuclear Waste Treatment

    International Nuclear Information System (INIS)

    Glubrecht, H.

    1986-01-01

    In the nuclear fuel cycle - like in most other industrial processes - some waste is produced which can be harmful to the environment and has to be stored safely and isolated from the Biosphere. This radioactive waste can be compared with toxic chemical waste under many aspects, but it has some special features, some of which make its handling more difficult, others make it easier. The difficulties are that radioactive waste does not only affect living organisms after incorporation, but also from some distance through its radiation. Therefore this waste has not only to be encapsuled, but also shielded. At higher concentrations radioactive waste produces heat and this has to be continuously derived from the storage area. On the other hand the control of even extremely small amounts of radioactive waste is very much easier than that of toxic chemical waste due to the high sensitivity of radiation detection methods. Furthermore radioactive waste is not persistent like most of the chemical waste. Of course some components will decay only after millennia, but a high percentage of radioactive waste becomes inactive after days, weeks or years. An important feature of safety aspects related to nuclear waste is the fact that problems of its treatment and storage have been discussed from the very beginning of Nuclear Energy Technology - what has not been the case in relation to most other industrial wastes

  12. Nuclear waste management policy in France

    International Nuclear Information System (INIS)

    Lefevre, J.F.

    1983-01-01

    The object of the nuclear waste management policy in France has always been to protect the worker and the public from unacceptable risks. The means and the structures developed to reach this objective, however, have evolved with time. One fact has come out ever more clearly over the years: Nuclear waste problems cannot be considered in a piecemeal fashion. The French nuclear waste management structure and policy aim at just this global approach. Responsibilities have been distributed between the main partners: the waste producers and conditioners, the research teams, the safety authorities, and the long-term waste manager, National Radioactive Waste Management Agency. The main technical options adopted for waste forms are embedding in hydraulic binders, bitumen, or thermosetting resins for low-level waste (LLW) and medium-level waste (MLW), and vitrification for high-level, liquid wastes. One shallow land disposal site for LLW and MLW has been in operation since 1969, the Centre of La Manche. Alpha-bearing and high-level waste will be disposed of by deep geological storage, possibly in granite formations. Further RandD aims mainly at improving present-day practices, developing more durable, long-term, alpha-bearing waste for all solid waste forms and going into all aspects of deep geological disposal characterization

  13. EXAMPLE OF A RISK-BASED DISPOSAL APPROVAL: SOLIDIFICATION OF HANFORD SITE TRANSURANIC (TRU) WASTE

    International Nuclear Information System (INIS)

    PRIGNANO AL

    2007-01-01

    The Hanford Site requested, and the U.S. Environmental Protection Agency (EPA) Region 10 approved, a Toxic Substances Control Act of 1976 (TSCA) risk-based disposal approval (RBDA) for solidifying approximately four cubic meters of waste from a specific area of one of the K East Basin: the North Loadout Pit (NLOP). The NLOP waste is a highly radioactive sludge that contained polychlorinated biphenyls (PCBs) regulated under TSCA. The prescribed disposal method for liquid PCB waste under TSCA regulations is either thermal treatment or decontamination. Due to the radioactive nature of the waste, however, neither thermal treatment nor decontamination was a viable option. As a result, the proposed treatment consisted of solidifying the material to comply with waste acceptance criteria at the Waste Isolation Pilot Plant (WPP) in Carlsbad, New Mexico, or possibly the Environmental Restoration Disposal Facility at the Hanford Site, depending on the resulting transuranic (TRU) content of the stabilized waste. The RBDA evaluated environmental risks associated with potential airborne PCBs. In addition, the RBDA made use of waste management controls already in place at the treatment unit. The treatment unit, the T Plant Complex, is a Resource Conservation and Recovery Act of 1976 (RCRA)-permitted facility used for storing and treating radioactive waste. The EPA found that the proposed activities did not pose an unreasonable risk to human health or the environment. Treatment took place from October 26,2005 to June 9,2006, and 332 208-liter (55-gallon) containers of solidified waste were produced. All treated drums assayed to date are TRU and will be disposed at WIPP

  14. Solid waste and chemical sludges: Stabilization/solidification processes and qualification of related products. Rifiuti solidi e fanghi: Processi di stabilizzazione/solidificazione e qualificazione dei prodotti ottenuti

    Energy Technology Data Exchange (ETDEWEB)

    Balzamo, S.; De Angelis, G. (ENEA, Casaccia (Italy). Area Energia Ambiente e Salute)

    A wide programme on cementation of radioactive and/or toxic wastes is being conducted at ENEA (Italian Agency for Energy, New Technologies and the Environment) laboratories. The main goal of the research work is to achieve solidified products which are reliable for transport and final disposal, as well as, to study possible reuse for civil purposes. Several characterization tests are made aiming at the optimization of process parameters and the verification of the quality of the final waste forms. Particular attention is being devoted to the problems related to the waste-matrix interaction, because no waste can be considered 'inert' from this point of view. It is therefore necessary to investigate the nature and the amount of such interactions through an accurate study of the chemical behaviour of the main waste components. That should allow researchers to get useful information to prevent the embedded wastes from causing deleterious effects to the solidification matrix.

  15. OCRWM International Cooperation in Nuclear Waste Management

    International Nuclear Information System (INIS)

    Jackson, R.; Levich, R.; Strahl, J.

    2002-01-01

    With the implementation of nuclear power as a major energy source, the United States is increasingly faced with the challenges of safely managing its inventory of spent nuclear materials. In 2002, with 438 nuclear power facilities generating electrical energy in 31 nations around the world, the management of radioactive material including spent nuclear fuel and high-level radioactive waste, is an international concern. Most of the world's nuclear nations maintain radioactive waste management programs and have generally accepted deep geologic repositories as the long-term solution for disposal of spent nuclear fuel and high-level radioactive waste. Similarly, the United States is evaluating the feasibility of deep geologic disposal at Yucca Mountain, Nevada. This project is directed by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management (OCRWM), which has responsibility for managing the disposition of spent nuclear fuel produced by commercial nuclear power facilities along with U.S. government-owned spent nuclear fuel and high-level radioactive waste. Much of the world class science conducted through the OCRWM program was enhanced through collaboration with other nations and international organizations focused on resolving issues associated with the disposition of spent nuclear fuel and high-level radioactive waste

  16. The IAEA project on nuclear and non-nuclear wastes

    International Nuclear Information System (INIS)

    Seitz, Roger

    1998-01-01

    Radioactive and chemotoxic agents are common in electricity generation waste. Data and assessments illustrate that nuclear and non-nuclear fuel chains result in waste posing potential long-term hazards. Efforts are focussed on filling data gaps and approaches for comparing impacts of radioactive and chemotoxic agents

  17. Review of the nuclear waste disposal problem

    International Nuclear Information System (INIS)

    Poch, L.A.; Wolsko, T.D.

    1979-10-01

    Regardless of future nuclear policy, a nuclear waste disposal problem does exist and must be dealt with. Even a moratorium on new nuclear plants leaves us with the wastes already in existence and wastes yet to be generated by reactors in operation. Thus, technologies to effectively dispose of our current waste problem must be researched and identified and, then, disposal facilities built. The magnitude of the waste disposal problem is a function of future nuclear policy. There are some waste disposal technologies that are suitable for both forms of HLW (spent fuel and reprocessing wastes), whereas others can be used with only reprocessed wastes. Therefore, the sooner a decision on the future of nuclear power is made the more accurately the magnitude of the waste problem will be known, thereby identifying those technologies that deserve more attention and funding. It is shown that there are risks associated with every disposal technology. One technology may afford a higher isolation potential at the expense of increased transportation risks in comparison to a second technology. Establishing the types of risks we are willing to live with must be resolved before any waste disposal technology can be instituted for widespread commercial use

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1985-06-01

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

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

    International Nuclear Information System (INIS)

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

    1985-06-01

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

  20. Materials aspects of nuclear waste isolation

    International Nuclear Information System (INIS)

    Bennett, J.W.

    1984-01-01

    This paper is intended to provide an overview of the nuclear waste repository performance requirements and the roles which we expect materials to play in meeting these requirements. The objective of the U.S. Dept. of Energy's (DOE) program is to provide for the safe, permanent isolation of high-level radioactive wastes from the public. The Nuclear Waste Policy Act of 1982 (the Act) provides the mandate to accomplish this objective by establishing a program timetable, a schedule of procedures to be followed, and program funding (1 mil/kwhr for all nuclear generated electricity). The centerpiece of this plan is the design and operation of a mined geologic repository system for the permanent isolation of radioactive wastes. A nuclear waste repository contains several thousand acres of tunnels and drifts into which the nuclear waste will be emplaced, and several hundred acres for the facilities on the surface in which the waste is received, handled, and prepared for movement underground. With the exception of the nuclear material-related facilities, a repository is similar to a standard mining operation. The difference comes in what a repository is supposed to do - to contain an isolate nuclear waste from man and the environment

  1. Managing nuclear waste from power plants

    International Nuclear Information System (INIS)

    Keeney, R.L.; Winterfeldt, D. von

    1994-01-01

    National strategies to manage nuclear waste from commercial nuclear power plants are analyzed and compared. The current strategy is to try to operate a repository at Yucca Mountain, Nevada, to dispose storage at a centralized facility or next to nuclear power plants. If either of these is pursued now, the analysis assumes that a repository will be built in 2100 for waste not subsequently put to use. The analysis treats various uncertainties: whether a repository at Yucca Mountain would be licensed, possible theft and misuse of the waste, innovations in repository design and waste management, the potential availability of a cancer cure by 2100, and possible future uses of nuclear waste. The objectives used to compare alternatives include concerns for health and safety, environmental and socioeconomic impacts, and direct economic costs, as well as equity concerns (geographical, intergenerational, and procedural), indirect economic costs, as well as equity concerns (geographical, intergenerational, and procedural), indirect economic costs to electricity ratepayers, federal government responsibility to manage nuclear waste, and implications of theft and misuse of nuclear waste. The analysis shows that currently building an underground repository at Yucca Mountain is inferior to other available strategies by the equivalent of $10,000 million to $50,000 million. This strongly suggests that this policy should be reconsidered. A more detailed analysis using the framework presented would help to define a new national policy to manage nuclear waste. 36 refs., 3 figs., 17 tabs

  2. Radioactive waste from nuclear power stations and other nuclear facilities

    International Nuclear Information System (INIS)

    Jelinek-Fink, P.

    1976-01-01

    After estimating the amounts of liquid and solid radioactive wastes that will be produced in nuclear power plants, reprocessing plants, by the fuel cycle industry, and in the nuclear research centers in the FRG until 1990, it is reported on the state of technology and on the tendencies in the development of processing radioactive waste. The paper also describes, how waste disposal is managed by those producing radioactive waste (see above), and discusses the future development of the complex of waste disposal from the industry's point of view. (HR/LN) [de

  3. Nuclear waste disposal educational forum

    International Nuclear Information System (INIS)

    1982-01-01

    In keeping with a mandate from the US Congress to provide opportunities for consumer education and information and to seek consumer input on national issues, the Department of Energy's Office of Consumer Affairs held a three-hour educational forum on the proposed nuclear waste disposal legislation. Nearly one hundred representatives of consumer, public interest, civic and environmental organizations were invited to attend. Consumer affairs professionals of utility companies across the country were also invited to attend the forum. The following six papers were presented: historical perspectives; status of legislation (Senate); status of legislation (House of Representatives); impact on the legislation on electric utilities; impact of the legislation on consumers; implementing the legislation. All six papers have been abstracted and indexed for the Energy Data Base

  4. Chemistry of nuclear waste disposal

    International Nuclear Information System (INIS)

    Zimmer, E.

    1981-01-01

    In extractive purification of the low-enriched uranium fuel element (UO 2 -particle fuel element with SiC coating) no problems arise in the PUREX-process which have not already been solved when reprocessing LWR-type reactor and breeder fuel elements. Concerning the HTR-type reactor fuel elements containing thorium, there are two process cycles behind the head end; the pure U-235 is reprocessed in the same manner as the low-enriched uranium fuel, and the thorium, which is the bigger fraction, is reprocessed together with U-233 in the same manner as the mixed oxides. Only the CO 2 -off gas system, which contains krypton and carbon 14, leads to difficulties in nuclear waste disposal. (DG) [de

  5. A global nuclear waste repository

    Science.gov (United States)

    Lin, Wunan

    As a concerned scientist, I think that having a global nuclear waste repository is a reachable goal for human beings. Maybe through this common goal, mankind can begin to treat each other as brothers and sisters. So far, most human activities are framed by national boundaries, which are purely arbitrary. Breaking through these national boundaries will be very beneficial to human beings.Formation of the International Geosphere-Biosphere Program in 1986 indicates a growing awareness on the part of scientists regarding Earth as a system. The Apollo missions gave us a chance to look back at Earth from space. That perspective emphasized that our Earth is just one system: our only home. It is in deed a lonely boat in the high sea of dark space. We must take good care of our “boat.”

  6. Arisings and management of nuclear wastes

    International Nuclear Information System (INIS)

    Dejonghe, P.; Heremans, R.; Proost, J.; Voorde, N. van de

    1978-01-01

    The paper contains a brief description of volumes and composition of radioactive wastes expected to occur in Belgium, taking into account the present nuclear program. Various conditioning and management techniques are described and discussed. Some discussion is paid to disposal of conditioned radioactive wastes either into the ocean (low level) or in geologic formations (long lived or high level wastes). Some ideas are given as to the structure optimization in radioactive waste management and the associated R and D. (author)

  7. Managing nuclear waste: the underground perspective

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    A simplified, very-general overview of the history of nuclear waste management is presented. The sources of different wastes of different levels of radioactivity are discussed. The current governmental program, including three DOE programs currently studying the problems of isolating waste in geological repositories, is discussed briefly. The general thrust of ensuing articles in the same magazine dealing with different facets of the waste-management program is outlined. (BLM)

  8. Waste processing system for nuclear power plant

    International Nuclear Information System (INIS)

    Higashinakagawa, Emiko; Tezuka, Fuminobu; Maesawa, Yukishige; Irie, Hiromitsu; Daibu, Etsuji.

    1996-01-01

    The present invention concerns a waste processing system of a nuclear power plant, which can reduce the volume of a large amount of plastics without burying them. Among burnable wastes and plastic wastes to be discarded in the power plant located on the sea side, the plastic wastes are heated and converted into oils, and the burnable wastes are burnt using the oils as a fuel. The system is based on the finding that the presence of Na 2 O, K 2 O contained in the wastes catalytically improves the efficiency of thermal decomposition in a heating atmosphere, in the method of heating plastics and converting them into oils. (T.M.)

  9. International Nuclear Waste Management Fact Book

    International Nuclear Information System (INIS)

    Leigh, I.W.

    1994-05-01

    International Nuclear Waste Management Fact Book has been compiled in an effort to provide current data concerning fuel cycle and waste management facilities, R ampersand D programs, and key personnel in 24 countries, including the US, four multinational agencies and 21 nuclear societies. This publication succeeds the previously issued International Nuclear Fuel Cycle Fact Book (PNL-3594), which appeared annually for 13 years. While the title is different, there are no substantial changes in the content

  10. Nuclear fuel waste policy in Canada

    International Nuclear Information System (INIS)

    Brown, P.A.; Letourneau, C.

    1999-01-01

    The 1996 Policy Framework for Radioactive Waste established the approach in Canada for dealing with all radioactive waste, and defined the respective roles of Government and waste producers and owners. The Policy Framework sets the stage for the development of institutional and financial arrangements to implement long-term waste management solutions in a safe, environmentally sound, comprehensive, cost-effective and integrated manner. For nuclear fuel waste, a 10-year environmental review of the concept to bury nuclear fuel waste bundles at a depth of 500 m to 1000 m in stable rock of the Canadian Shield was completed in March 1998. The Review Panel found that while the concept was technically safe, it did not have the required level of public acceptability to be adopted at this time as Canada's approach for managing its nuclear fuel waste. The Panel recommended that a Waste Management Organization be established at arm's length from the nuclear industry, entirely funded by the waste producers and owners, and that it be subject to oversight by the Government. In its December 1998 Response to the Review Panel, the Government of Canada provided policy direction for the next steps towards developing Canada's approach for the long-term management of nuclear fuel waste. The Government chose to maintain the responsibility for long-term management of nuclear fuel waste close with the producers and owners of the waste. This is consistent with its 1996 Policy Framework for Radioactive Waste. This approach is also consistent with experience in many countries. In addition, the federal government identified the need for credible federal oversight. Cabinet directed the Minister of NRCan to consult with stakeholders, including the public, and return to ministers within 12 months with recommendations on means to implement federal oversight. (author)

  11. Nuclear waste problem: does new Europe need new nuclear energy?

    International Nuclear Information System (INIS)

    Alekseev, P.; Dudnikov, A.; Subbotin, S.

    2003-01-01

    Nuclear Energy for New Europe - what does it mean? New Europe - it means in first order joined Europe. And it is quite clear that also efforts in nuclear energy must be joined. What can be proposed as a target of joint efforts. Improvement of existing plants, technologies, materials? - Certainly, but it is performed already by designers and industry themselves. There exists a problem, which each state using nuclear energy faces alone. It is nuclear waste problem. Nowadays nuclear waste problem is not completely solved in any country. It seems reasonable for joining Europe to join efforts in solving this problem. A satisfactory solution would reduce a risk connected with nuclear waste. In addition to final disposal problem solution it is necessary to reduce total amount of nuclear waste, that means: reducing the rates of accumulation of long-lived dangerous radionuclides; reducing the existing amounts of these radionuclides by transmutation. These conditions can be satisfied in reasonable time by burning of minor actinides and, if possible, by transmutation of long-lived fission products. However we can use this strategy effectively if we will design and construct nuclear energy as a system of which components are united by nuclear fuel cycle as a system-forming factor. The existing structures and approaches may become insufficient for new Europe. Therefore among the initial steps in considering nuclear waste problem must be considering possible promising fuel cycles for European nuclear energy. So, does new Europe need new nuclear energy? It seems, yes. (author)

  12. Environmental aspects of stabilization and solidification of hazardous and radioactive wastes

    International Nuclear Information System (INIS)

    Cote, P.; Gilliam, M.

    1989-01-01

    This book contains papers presented at the Fourth International Hazardous Waste Symposium. It is organized under the following headings: processes, regulatory aspects and testing methods, laboratory evaluation and large-scale evaluation or demonstrations

  13. Nuclear chemistry research for the safe disposal of nuclear waste

    International Nuclear Information System (INIS)

    Fanghaenel, Thomas

    2011-01-01

    The safe disposal of high-level nuclear waste and spent nuclear fuel is of key importance for the future sustainable development of nuclear energy. Concepts foresee the isolation of the nuclear waste in deep geological formations. The long-term radiotoxicity of nuclear waste is dominated by plutonium and the minor actinides. Hence it is essential for the performance assessment of a nuclear waste disposal to understand the chemical behaviour of actinides in a repository system. The aqueous chemistry and thermodynamics of actinides is rather complex in particular due to their very rich redox chemistry. Recent results of our detailed study of the Plutonium and Neptunium redox - and complexation behaviour are presented and discussed. (author)

  14. Science, Society, and America's Nuclear Waste: Nuclear Waste, Unit 1. Teacher Guide. Second Edition.

    Science.gov (United States)

    Department of Energy, Washington, DC. Office of Civilian Radioactive Waste Management, Washington, DC.

    This guide is Unit 1 of the four-part series Science, Society, and America's Nuclear Waste produced by the U.S. Department of Energy's Office of Civilian Radioactive Waste Management. The goal of this unit is to help students establish the relevance of the topic of nuclear waste to their everyday lives and activities. Particular attention is…

  15. Prospects of nuclear waste management and radioactive waste management

    International Nuclear Information System (INIS)

    Koprda, V.

    2015-01-01

    The policy of radioactive waste management in the Slovak Republic is based on the principles defined by law on the National Nuclear Fund (NJF) and sets basic objectives: 1 Safe and reliable nuclear decommissioning; 2 The minimization of radioactive waste; 3. Selection of a suitable fuel cycle; 4 Safe storage of radioactive waste (RAW) 5 Security chain management of radioactive waste and spent nuclear fuel (SNF); 6 Nuclear safety; 7 The application of a graduated approach; 8 Respect of the principle 'a polluter pays'; 9 Objective decision-making process; 10 Responsibility. In connection with the above objectives, it appears necessary to build required facilities that are listed in this article.

  16. Plasma Mass Filters For Nuclear Waste Reprocessing

    International Nuclear Information System (INIS)

    Fetterman, Abraham J.; Fisch, Nathaniel J.

    2011-01-01

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

  17. The present situation of nuclear wastes

    International Nuclear Information System (INIS)

    Courtois, Charles

    2012-01-01

    This Power Point presentation contains graphs, tables and comments on different aspects of nuclear wastes: origin in France (fuel composition, long-life and short life wastes), definition of the different types of wastes (with respect to their life and their activity level), fuel cycle (processing of the different wastes, actors in France, waste management), waste characterization (controls, tests), laws on wastes published in 1991 (objectives with respect to separation and transmutation technologies, to storage possibilities, to conditioning and long term storage) and in 2006 (which defines a national plan for radioactive material and waste management, and a research program), the French national inventory, low activity wastes (production and storage), the transmutation technology (notably the Astrid project), the geological storage (the Cigeo project for a geological storage), and the situation in other countries

  18. Crystallization behavior of nuclear waste forms

    International Nuclear Information System (INIS)

    Rusin, J.M.; Lokken, R.O.; May, R.P.; Wald, J.W.

    1981-09-01

    Several waste form options have been or are being developed for the immobilization of high-level wastes. The final selection of a waste form must take into consideration both waste form product as well as process factors. Crystallization behavior has an important role in nuclear waste form technology. For glass or vitreous waste forms, crystallization is generally controlled to a minimum by appropriate glass formulation and heat treatment schedules. With glass ceramic waste forms, crystallization is essential to convert glass products to highly crystalline waste forms with a minimum residual glass content. In the case of ceramic waste forms, additives and controlled sintering schedules are used to contain the radionuclides in specific tailored crystalline phases

  19. Acceptance and tracking of waste packages from nuclear power plants at the Centre de l'Aube

    International Nuclear Information System (INIS)

    Errera, J.; Tison, J.L.

    2001-01-01

    For 30 years, the French National Agency for Radioactive Waste Management (ANDRA) is in charge of the radioactive waste management and acquired a good knowledge relating to the control of low and intermediate level waste produced by nuclear power plants (NPP), the waste characteristics and the waste conditioning. The integrated waste management system for low-level radioactive waste in France implemented by ANDRA covers all stages from waste generation to final disposal at the Centre de I'Aube near surface facility. ANDRA defined a quality assurance program for waste management that specifies the level of quality to be achieved by solidification and packaging processes, defines quality control requirements and defines waste tracking requirements, from waste generation through final disposal. Verification of quality of waste packages is implemented at three levels of the waste management system. The first one consists of inspections of waste packages at the generator's premises and audits of the quality assurance organization of the waste generator. The second level of verification consists of the waste tracking system. It allows identifying and tracking each waste package from the step it is fabricated to its final disposal at the ANDRA site. The third level of verification is obtained by mean of non-destructive and destructive assays of waste packages. These assays allow to verify generator compliance with ANDRA's technical specifications and to investigate the accuracy of physical and radioactive characteristics reported to ANDRA by the generator. (author)

  20. Spray Calciner/In-Can Melter high-level waste solidification technical manual

    International Nuclear Information System (INIS)

    Larson, D.E.

    1980-09-01

    This technical manual summarizes process and equipment technology developed at Pacific Northwest Laboratory over the last 20 years for vitrification of high-level liquid waste by the Spray Calciner/In-Can Melter process. Pacific Northwest Laboratory experience includes process development and demonstration in laboratory-, pilot-, and full-scale equipment using nonradioactive synthetic wastes. Also, laboratory- and pilot-scale process demonstrations have been conducted using actual high-level radioactive wastes. In the course of process development, more than 26 tonnes of borosilicate glass have been produced in 75 canisters. Four of these canisters contained radioactive waste glass. The associated process and glass chemistry is discussed. Technology areas described include calciner feed treatment and techniques, calcination, vitrification, off-gas treatment, glass containment (the canister), and waste glass chemistry. Areas of optimization and site-specific development that would be needed to adapt this base technology for specific plant application are indicated. A conceptual Spray Calciner/In-Can Melter system design and analyses are provided in the manual to assist prospective users in evaluating the process for plant application, to provide equipment design information, and to supply information for safety analyses and environmental reports. The base (generic) technology for the Spray Calciner/In-Can Melter process has been developed to a point at which it is ready for plant application

  1. Nuclear waste management: A review of issues

    International Nuclear Information System (INIS)

    Angino, E.E.

    1985-01-01

    The subject of radioactive waste management and burial is a subject that raises strong emotional and political issues and generates sharp technical differences of opinion. The overall problem can be subdivided into the three major categories of (1) credibility and emotionalism, (2) technology, and (3) nuclear waste isolation and containment. An area of concern desperately in need of attention is that of proper public education on all aspects of the high-level radioactive-waste (rad-waste) burial problem. A major problem related to the rad-waste issue is the apparent lack of an official, all-encompassing U.S. policy for nuclear waste management, burial, isolation, and regulation. It is clear from all past technical reports that disposal of rad wastes in an appropriate geologic horizon is the best ultimate solution to the waste problem. After 25 y of dealing with the high-level radioactive waste problem, the difficulty is that no proposed plan has to date been tested properly. It is this indecision and reaction that has contributed in no small way to the public perception of inability to solve the problem. One major change that has occurred in the last few years was the enactment of the Nuclear Waste Policy Act of 1982. This act mandates deadlines, guidelines, and state involvement. It is time that strong differences of opinions be reconciled. One must get on with the difficult job of selecting the best means of isolating and burying these wastes before the task becomes impossible

  2. Effect of borate concentration on solidification of radioactive wastes by different cements

    International Nuclear Information System (INIS)

    Sun Qina; Li Junfeng; Wang Jianlong

    2011-01-01

    Highlights: → The effect of borate on cementation of radioactive borate evaporator concentrates by sulfoaluminate cement (SAC) and Portland cement (PC) was compared. → The X-ray diffraction (XRD) revealed that borate did not interfere with the formation of main hydration products of SAC and PC. → Borate, in the form of B(OH) 4- , incorporated in ettringite as solid solution phase. - Abstract: To investigate the effect of borate on the cementation of radioactive evaporator concentrates, and to provide more data for solidification formula optimization, the simulated borate evaporator concentrates with different borate concentrations (as B) and Na/B ratio (molar ratio) were solidified by sulfoaluminate cement (SAC) and Portland cement (PC), with addition of Ca(OH) 2 , zeolite and accelerator or water reducer. The hydration products of solidified matrices were characterized by X-ray diffraction (XRD). The experimental results showed that borate retarded the cement setting for both SAC and PC formulas, and the final setting time prolonged with decrease of Na/B ratio. Borate could enhance the fluidity of the cement mixture. The 28 d compressive strengths of the solidified matrices for both SAC and PC formulas decreased with increase of borate concentration. The XRD patterns suggested that, in the matrices maintained for 28 d, borate did not interfere with the formation of main hydration products of SAC and PC. Borate, in the form of B(OH) 4- , incorporated in ettringite (3CaO.Al 2 O 3 .3CaSO 4 .32H 2 O) as solid solution phase. The formula of SAC and PC developed in this study was effective for cementation of the simulated borate evaporator concentrates. However further optimization was required to reduce retarding effect of higher borate concentrations and to extend the practical feasibility for actual evaporator concentrates.

  3. Dossier: management of nuclear wastes. Research, results

    International Nuclear Information System (INIS)

    Anon.

    2001-01-01

    The researches carried out since many years on nuclear wastes have led to two main ways of management: the long-term conditioning of radio-elements and their advanced separation. The French atomic energy commission (CEA) has chosen to take up also the transmutation challenge, a way to transform long-living radioactive wastes into short-living radioactive wastes or stable compounds. The transmutation programs are based both on simulation and experiments with a huge international collaboration. This dossier presents in a digest way the research activity carried out on nuclear wastes processing and management at the CEA. (J.S.)

  4. The Canadian nuclear fuel waste management program

    International Nuclear Information System (INIS)

    Dixon, R.S.

    1984-12-01

    The Canadian Nuclear Fuel Waste Management Program involves research into the storage and transportation of used nuclear fuel, immobilization of fuel waste, and deep geological disposal of the immobilized waste. The program is now in the fourth year of a ten-year generic research and development phase. The objective of this phase of the program is to assess the safety and environmental aspects of the deep underground disposal of immobilized fuel waste in plutonic rock. The objectives of the research for each component of the program and the progress made to the end of 1983 are described in this report

  5. Nuclear waste repository design and construction

    International Nuclear Information System (INIS)

    Bohlke, B.M.; Monsees, J.E.

    1987-01-01

    Extensive underground excavation will be required for construction of a mined geologic repository for nuclear waste. Hundreds of thousands of feet of drift will be required based on the conceptual layout design for each candidate nuclear waste repository. Comparison of boring and blasting excavation methods are discussed, as are special design and construction requirements (e.g., quality assurance procedures and performance assessment) for the nuclear waste repository. Comparisons are made between boring and blasting construction methods for the repository designs proposed for salt, volcanic tuff, and basalt

  6. Survey on non-nuclear radioactive waste

    International Nuclear Information System (INIS)

    2003-11-01

    On request from the Swedish Radiation Protection Authority, the Swedish government has in May 2002 set up a non-standing committee for non-nuclear radioactive waste. The objective was to elaborate proposals for a national system for the management of all types of non-nuclear radioactive wastes with special consideration of inter alia the polluter pays principle and the responsibility of the producers. The committee will deliver its proposals to the government 1 December 2003. SSI has assisted the committee to the necessary extent to fulfill the investigation. This report is a summery of SSI's background material concerning non-nuclear radioactive waste in Sweden

  7. Solidification of aqueous radioactive waste using insoluble compounds of magnesium oxide

    International Nuclear Information System (INIS)

    Carlson, J.E.

    1986-01-01

    A process is described for the treatment of radioactive waste which comprises: (a) first adding, under continuous agitation, a sufficient amount of a powdered magnesium oxide or magnesium hydroxide to an aqueous radioactive waste solution containing boric acid, the temperature of the water solution being 55-95 degrees C. to produce a magnesium borate derivative; (b) adding cement, under continuous agitation, to the magnesium borate derivative; and (c) then adding, under continuous agitation, after the cement has been dispersed, a sufficient amount of a compound selected from the group consisting of calcium oxide and calcium hydroxide to (b) to produce a gel matrix structure

  8. Method of storing solidification products

    International Nuclear Information System (INIS)

    Tani, Yutaro.

    1985-01-01

    Purpose: To enable to efficiently and satisfactorily cool and store solidification products of liquid wastes generated from the reactor spent fuel reprocessing process by a simple facility. Method: Liquid wastes generated from the reactor spent fuel reprocessing process are caused to flow from the upper opening to the inside of a spherical canistor. The opening of the spherical canistor is welded with a lid by a remote control and the liquid wastes are tightly sealed within the spherical canistor as glass solidification products. Spherical canistors having the solidification products tightly sealed therein are sent into and stored in a hopper by the remote control. Further, a blower is driven upon storing to suck cooling air from the cooling air intake port to the inside of the hopper to absorb the decay heat of radioactive materials in the solidification products and the air is discharged from the duct and through the stack to the atmosphere. (Kawakami, Y.)

  9. Proceedings of the symposium on the on-site management of power reactor wastes

    International Nuclear Information System (INIS)

    Anon.

    1979-01-01

    This symposium represents a synthesis of some current practices and research and development work in the field of radioactive waste management at nuclear power plants. It includes the following sessions: radioactive waste management practices at nuclear power plants; waste production and operating experiences; coolant and liquid waste processing; solidification methods; volume reduction methods; solid waste containment

  10. MANAGING ARSENIC CONTAMINATED SOIL, SEDIMENT, AND INDUSTRIAL WASTE WITH SOLIDIFICATION/STABILIZATION TREATMENT

    Science.gov (United States)

    Arsenic contamination of soil, sediment and groundwater is a widespread problem in certain areas and has caused great public concern due to increased awareness of the health risks. Often the contamination is naturally occurring, but it can also be a result of waste generated from...

  11. High-silica glass matrix process for high-level waste solidification

    International Nuclear Information System (INIS)

    Simmons, J.H.; Macedo, P.B.

    1981-01-01

    In the search for an optimum glass matrix composition, we have determined that chemical durability and thermal stability are maximized, and that stress development is minimized for glass compositions containing large concentrations of glass-forming oxides, of which silica is the major component (80 mol%). These properties and characteristics were recently demonstrated to belong to very old geological glasses known as tektites (ages of 750,000 to 34 million years.) The barrier to simulating tektite compositions for the waste glasses was the high melting temperature (1600 to 1800 0 C) needed for these glasses. Such temperatures greatly complicate furnace design and maintenance and lead to an intolerable vaporization of many of the radioisotopes into the off-gas system. Research conducted at our laboratory led to the development of a porous high-silica waste glass material with approximately 80% SiO 2 by mole and 30% waste loading by weight. The process can handle a wide variety of compositions, and yields long, elliptical, monolithic samples, which consist of a loaded high-silica core completely enveloped in a high-silica glass tube, which has collapsed upon the core and sealed it from the outside. The outer glass layer is totally free of waste isotopes and provides an integral multibarrier protection system

  12. Solidification/stabilization of ash from medical waste incineration into geopolymers.

    Science.gov (United States)

    Tzanakos, Konstantinos; Mimilidou, Aliki; Anastasiadou, Kalliopi; Stratakis, Antonis; Gidarakos, Evangelos

    2014-10-01

    In the present work, bottom and fly ash, generated from incinerated medical waste, was used as a raw material for the production of geopolymers. The stabilization (S/S) process studied in this paper has been evaluated by means of the leaching and mechanical properties of the S/S solids obtained. Hospital waste ash, sodium hydroxide, sodium silicate solution and metakaolin were mixed. Geopolymers were cured at 50°C for 24h. After a certain aging time of 7 and 28 days, the strength of the geopolymer specimens, the leachability of heavy metals and the mineralogical phase of the produced geopolymers were studied. The effects of the additions of fly ash and calcium compounds were also investigated. The results showed that hospital waste ash can be utilized as source material for the production of geopolymers. The addition of fly ash and calcium compounds considerably improves the strength of the geopolymer specimens (2-8 MPa). Finally, the solidified matrices indicated that geopolymerization process is able to reduce the amount of the heavy metals found in the leachate of the hospital waste ash. Copyright © 2014 Elsevier Ltd. All rights reserved.

  13. Solidification Tests Conducted on Transuranic Mixed Oil Waste (TRUM) at the Rocky Flats Environmental Technology Site (RFETS)

    International Nuclear Information System (INIS)

    Brunkow, W. G.; Campbell, D.; Geimer, R.; Gilbreath, C.; Rivera, M.

    2002-01-01

    Rocky Flats Environmental Technology Site (RFETS) near Golden, Colorado is the first major nuclear weapons site within the DOE complex that has been declared a full closure site. RFETS has been given the challenge of closing the site by 2006. Key to meeting this challenge is the removal of all waste from the site followed by site restoration. Crucial to meeting this challenge is Kaiser-Hill's (RFETS Operating Contractor) ability to dispose of significant quantities of ''orphan'' wastes. Orphan wastes are those with no current disposition for treatment or disposal. Once such waste stream, generically referred to as Transuranic oils, poses a significant threat to meeting the closure schedule. Historically, this waste stream, which consist of a variety of oil contaminated with a range of organic solvents were treated by simply mixing with Environstone. This treatment method rendered a solidified waste form, but unfortunately not a TRUPACT-II transportable waste. So for the last ten years, RFETS has been accumulating these TRU oils while searching for a non-controversial treatment option

  14. Nuclear, energy, environment, wastes, society - NEEDS

    International Nuclear Information System (INIS)

    2013-01-01

    This document presents the seven projects based on partnerships between several bodies, companies and agencies (CNRS, CEA, Areva, EDF, IRSN, ANDRA, BRGM) on research programmes on nuclear systems and scenarios, on resources (mines, processes, economy), on the processing and packaging of radioactive wastes, on the behaviour of materials for storage, on the impact of nuclear activities on the environment, on the relationship between nuclear, risks and society, and on materials for nuclear energy

  15. 10 CFR 1.18 - Advisory Committee on Nuclear Waste.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Advisory Committee on Nuclear Waste. 1.18 Section 1.18... Panels, Boards, and Committees § 1.18 Advisory Committee on Nuclear Waste. The Advisory Committee on Nuclear Waste (ACNW) provides advice to the Commission on all aspects of nuclear waste management, as...

  16. Science, society, and America's nuclear waste: Unit 3, The Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    1992-01-01

    This teachers guide is unit 3, the nuclear waste policy act, in a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear power plants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  17. Science, society, and America's nuclear waste: Unit 3, The Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    1992-01-01

    This is the 3rd unit, (The Nuclear Waste Policy Act) a four-unit secondary curriculum. It is intended to provide information about scientific and societal issues related to the management of spent nuclear fuel from generation of electricity at nuclear powerplants and high-level radioactive waste from US national defense activities. The curriculum, supporting classroom activities, and teaching materials present a brief discussion of energy and electricity generation, including that produced at nuclear powerplants; information on sources, amounts, location, and characteristics of spent nuclear fuel and high-level radioactive waste; sources, types and effects of radiation; US policy for managing and disposing of spent nuclear fuel and high-level radioactive waste and what other countries are doing; and the components of the nuclear waste management system

  18. Credible nuclear waste management: a legislative perspective

    International Nuclear Information System (INIS)

    Jeffords, J.M.

    1978-01-01

    The past credibility of the AEC, ERDA, and NRC, along with the present credibility of DOE and NRC, are questioned. The results of voter responses to a moratorium on expansion of nuclear power are linked to the question of past credibility of these Federal agencies. It is proposed that the future of nuclear power be linked directly to the Executive Branch of the government via a new bureaucracy, a Waste Management Authority. This new bureaucracy would be completely separated from the construction or licensing phase of nuclear power, except it would have final say over any nuclear power expansion pending an acceptable solution to the waste reprocessing question

  19. Tergiversating the price of nuclear waste storage

    International Nuclear Information System (INIS)

    Mills, R.L.

    1984-01-01

    Tergiversation, the evasion of straightforward action of clearcut statement of position, was a characteristic of high-level nuclear waste disposal until the US Congress passed the Nuclear Waste Policy Act of 1982. How the price of waste storage is administered will affect the design requirements of monitored retrievable storage (MRS) facilities as well as repositories. Those decisions, in part, are internal to the Department of Energy. From the utility's viewpoint, the options are few but clearer. Reprocessing, as performed in Europe, is not a perfect substitute for MRS. The European reprocess-repository sequence will not yield the same nuclear resource base as the American MRS-repository scheme. For the future price of the energy resource represented by nuclear waste, the author notes that tergiversation continues. 3 references

  20. Public policy issues in nuclear waste management

    International Nuclear Information System (INIS)

    Nealey, S.M.; Radford, L.M.

    1978-10-01

    This document aims to raise issues and to analyze them, not resolve them. The issues were: temporal equity, geographic and socioeconomic equity, implementation of a nuclear waste management system, and public involvement

  1. Nuclear Waste Disposal: Alternatives to Yucca Mountain

    National Research Council Canada - National Science Library

    Holt, Mark

    2009-01-01

    Congress designated Yucca Mountain, NV, as the nation's sole candidate site for a permanent high-level nuclear waste repository in 1987, following years of controversy over the site-selection process...

  2. Towards a strategy on nuclear waste

    International Nuclear Information System (INIS)

    Church, C.

    1984-01-01

    An account is given of campaigns to stop various aspects of nuclear power, particularly those concerned with the management of radioactive wastes. Some proposals are made for further specific campaigns. (U.K.)

  3. Transport packages for nuclear material and waste

    International Nuclear Information System (INIS)

    1997-01-01

    The regulations and responsibilities concerning the transport packages of nuclear materials and waste are given in the guide. The approval procedure, control of manufacturing, commissioning of the packaging and the control of use are specified. (13 refs.)

  4. Waste from decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Nielsen, P.O.

    1992-05-01

    This report is based on the assumption that all twelve nuclear power plants will be shut down no later than A.D. 2010, as was decided by the parliament after the referendum on the future of nuclear power in Sweden. The recent 'Party agreement on the energy policy' of January 15, 1991 does, indeed, leave the door open for an extension of the operational period for the nuclear reactors. This will, however, not change the recommendations and conclusions drawn in this report. The report consists of two parts. Part 1 discusses classification of waste from decommissioning and makes comparisons with the waste arising from reactor operation. Part 2 discusses the documentation required for decommissioning waste. Also this part of the report draws parallels with the documentation required by the authorities for the radioactive waste arising from operation of the nuclear power plants. To some extent these subjects depend on the future use of the nuclear power plant sites after decommissioning of the plants. The options for future site use are briefly discussed in an appendix to the report. There are many similarities between the waste from reactor operations and the waste arising from dismantling and removal of decommissioned nuclear power plants. Hence it seems natural to apply the same criteria and recommendations to decommissioning waste as those presently applicable to reactor waste. This is certainly true also with respect to documentation, and it is strongly recommended that the documentation requirements on decommissioning waste are made identical, or at least similar, to the documentation requirements for reactor waste in force today. (au)

  5. Radioactive waste management policy for nuclear power

    International Nuclear Information System (INIS)

    Andrei, V.; Glodeanu, F.; Simionov, V.

    1998-01-01

    Nuclear power is part of energy future as a clean and environmental friendly source of energy. For the case of nuclear power, two specific aspects come more often in front of public attention: how much does it cost and what happens with radioactive waste. The competitiveness of nuclear power vs other sources of energy is already proved in many developed and developing countries. As concerns the radioactive wastes treatment and disposal, industrial technologies are available. Even final solutions for disposal of high level radioactive waste, including spent fuel, are now fully developed and ready for large scale implementation. Policies and waste management strategies are established by all countries having nuclear programs. Once, the first nuclear power reactor was commissioned in Romania, and based on the national legal provisions, our company prepared the first issue of a general strategy for radioactive waste management. The general objective of the strategy is to dispose the waste according to adequate safety standards protecting the man and the environment, without undue burden on future generations. Two target objectives were established for long term: an interim spent fuel dry storage facility and a low and intermediate level waste repository. A solution for spent fuel disposal will be implemented in the next decade, based on international experience. Principles for radioactive waste management, recommended by IAEA are closely followed in the activities of our company. The continuity of responsibilities is considered to be very important. The radioactive waste management cost will be supported by the company. A tax on unit price of electricity will be applied. The implementation of radioactive waste management strategy includes as a major component the public information. A special attention will be paid by the company to an information program addressed to different categories of public in order to have a better acceptance of our nuclear power projects

  6. Risk decisions and nuclear waste

    International Nuclear Information System (INIS)

    Hansson, S.O.

    1987-11-01

    The risk concept is multidimensional, and much of its contents is lost in the conventional reduction to a unidimensional and quantifiable term. Eight major dimensions of the risk concept are discussed, among them the time factor and the lack-of-knowledge factor. The requirements of a rational discourse are discussed, in general and in relation to risk issues. It is concluded that no single method for the comparison and assessment of risks can be seen as the only rational method. Different methods can all be rational, although based on different values. Risk evaluations cannot be performed as expert assessments, divorced from the political decision process. Instead, risk evaluation must be seen as an essentially political process. Public participation is necessary in democratic decision-making on risks as well as on other issues. Important conclusions can be drawn for the management of nuclear waste, concerning specifications for the technical solution, the need for research on risk concepts, and the decision-making process. (orig.)

  7. Transmutation of radioactive nuclear waste

    International Nuclear Information System (INIS)

    Toor, A; Buck, R

    2000-01-01

    Lack of a safe disposal method for radioactive nuclear waste (RNW) is a problem of staggering proportion and impact. A typical LWR fission reactor will produce the following RNW in one year: minor actinides (i.e. 237 Np, 242-243 Am, 243-245 Cm) ∼40 kg, long-lived fission products (i.e, 99 Tc, 93 Zr, 129 I, 135 Cs) ∼80 kg, short lived fission products (e.g. 137 Cs, 90 Sr) ∼50kg and plutonium ∼280 kg. The total RNW produced by France and Canada amounts to hundreds of metric tonnes per year. Obtaining a uniform policy dealing with RNW has been blocked by the desire on one hand to harvest the energy stored in plutonium to benefit society and on the other hand the need to assure that the stockpile of plutonium will not be channeled into future nuclear weapons. In the meantime, the quantity and handling of these materials represents a potential health hazard to the world's population and particularly to people in the vicinity of temporary storage facilities. In the U.S., societal awareness of the hazards associated with RNW has effectively delayed development of U.S. nuclear fission reactors during the past decade. As a result the U.S. does not benefit from the large investment of resources in this industry. Reluctance to employ nuclear energy has compelled our society to rely increasingly on non-reusable alternative energy sources; coal, oil, and natural gas. That decision has compounded other unresolved global problems such as air pollution, acid rain, and global warming. Relying on these energy sources to meet our increasing energy demands has led the U.S. to increase its reliance on foreign oil; a policy that is disadvantageous to our economy and our national security. RNW can be simplistically thought of as being composed of two principal components: (1) actinides with half lives up to 10 6 years and (2) the broad class of fission fragments with typical half lives of a few hundred years. One approach to the RNW storage problem has been to transmute the

  8. Nuclear waste: A problem of perspective

    International Nuclear Information System (INIS)

    Williams, I.G.K.

    1979-01-01

    In the light of the suspicion to be felt in the public towards the problem of nuclear waste management, the author in his article attempts to correct the impression created by somewhat sensational reports in the daily press by giving a more accurate description of nuclear waste management. He points out that responsible and fruitful research work has been done and should be made known to the public. (RB) [de

  9. Federalist strategy for nuclear waste management

    International Nuclear Information System (INIS)

    Lee, K.N.

    1980-01-01

    The federal government plans to rely on a policy of consultation and concurrence with state governments in developing nuclear waste repositories. The weaknesses of the concurrence approach are analyzed, and an alternative institutional framework for locating a waste repository is proposed: a siting jury that provides representation for state and local interests, while maintaining a high level of technical review. The proposal could be tested in the siting of away-from-reactor storage facilities for spent nuclear fuel. 1 table

  10. Status of technology for nuclear waste management

    International Nuclear Information System (INIS)

    Lieberman, J.A.

    1984-01-01

    In the area of low- and intermediate-level radioactive wastes the successful development and application of specific management technologies have been demonstrated over the years. The major area in which technology remains to be effectively implemented is in the management of high-level wastes from the nuclear fuel cycle. Research and development specifically directed at the management of high-level radioactive wastes in the USA and other countries is briefly reviewed in the article introduced

  11. Waste management in Canadian nuclear programs

    International Nuclear Information System (INIS)

    Dyne, P.J.

    1975-08-01

    The report describes the wide-ranging program of engineering developments and applications to provide the Canadian nuclear industry with the knowledge and expertise it needs to conduct its waste management program. The need for interim dry storage of spent fuel, and the storage and ultimate disposal of waste from fuel reprocessing are examined. The role of geologic storage in AECL's current waste management program is also considered. (R.A.)

  12. New Mexicans debate nuclear waste disposal

    International Nuclear Information System (INIS)

    Lepkowski, W.

    1979-01-01

    A brief survey of the background of the Waste Isolation Plant (WIPP) at Carlsbad, New Mexico and the forces at play around WIPP is presented. DOE has plans to establish by 1988 an underground repository for nuclear wastes in the salt formations near Carlsbad. Views of New Mexicans, both pro and con, are reviewed. It is concluded that DOE will have to practice public persuasion to receive approval for the burial of wastes in New Mexico

  13. Overview assessment of nuclear-waste management

    International Nuclear Information System (INIS)

    Burton, B.W.; Gutschick, V.P.; Perkins, B.A.

    1982-08-01

    After reviewing the environmental control technologies associated with Department of Energy nuclear waste management programs, we have identified the most urgent problems requiring further action or follow-up. They are in order of decreasing importance: (1) shallow land disposal technology development; (2) active uranium mill tailings piles; (3) uranium mine dewatering; (4) site decommissioning; (5) exhumation/treatment of transuranic waste at Idaho National Engineering Laboratory; (6) uranium mine spoils; and (7) medical/institutional wastes. 7 figures, 33 tables

  14. Civil engineering challenge with nuclear waste

    International Nuclear Information System (INIS)

    Day, D.

    1985-01-01

    The civil engineer can help to solve the problems in disposing of nuclear waste in a deep geologic formation. The site for a nuclear waste repository must be carefully selected so that the geology provides the natural barrier between the waste and the accessible environment specified by the NRC and the EPA. This engineer is familiar with the needed structure and conditions of the host and surrounding rocks, and also the hydraulic mechanisms for limiting the migration of water in the rocks. To dispose of the nuclear waste underground requires stable and long-lasting shafts and tunnels such as civil engineers have designed and constructed for many other uses. The planning, design and construction of the ground surface facilities for a nuclear waste repository involves civil engineering in many ways. The transporation of heavy, metal shielded casks requires special attention to the system of highways and railroads accessing the repository. Structures for handling the shipping casks and transferring the waste onsite and into the deep geologic formation need special considerations. The structures must provide the NRC required containment, including hot cells for remote handling. Therefore, structural design strives for buildings, ventilation structures, shaft headframes, etc., to be earthquake and tornado-proof. These important design bases and considerations for the civil engineer working on a nuclear waste repository are discussed in this paper

  15. Radioactive waste management from nuclear facilities

    International Nuclear Information System (INIS)

    2005-06-01

    This report has been published as a NSA (Nuclear Systems Association, Japan) commentary series, No. 13, and documents the present status on management of radioactive wastes produced from nuclear facilities in Japan and other countries as well. Risks for radiation accidents coming from radioactive waste disposal and storage together with risks for reactor accidents from nuclear power plants are now causing public anxiety. This commentary concerns among all high-level radioactive waste management from nuclear fuel cycle facilities, with including radioactive wastes from research institutes or hospitals. Also included is wastes produced from reactor decommissioning. For low-level radioactive wastes, the wastes is reduced in volume, solidified, and removed to the sites of storage depending on their radioactivities. For high-level radioactive wastes, some ten thousand years must be necessary before the radioactivity decays to the natural level and protection against seismic or volcanic activities, and terrorist attacks is unavoidable for final disposals. This inevitably results in underground disposal at least 300 m below the ground. Various proposals for the disposal and management for this and their evaluation techniques are described in the present document. (S. Ohno)

  16. Nuclear Waste Primer: A Handbook for Citizens.

    Science.gov (United States)

    Weber, Isabelle P.; Wiltshire, Susan D.

    This publication was developed with the intention of offering the nonexpert a concise, balanced introduction to nuclear waste. It outlines the dimensions of the problem, discussing the types and quantities of waste. Included are the sources, types, and hazards of radiation, and some of the history, major legislation, and current status of both…

  17. A plan for Soviet nuclear waste

    International Nuclear Information System (INIS)

    Stone, R.

    1992-01-01

    If environmentalist forces are successful, the Russian government may soon establish the country's first comprehensive program for dealing with nuclear waste. Later this month the Russian parliament, back from its summer recess, is expected to begin considering a bill on this topic. A draft copy indicates that Russia is starting with the basics: It orders the government to develop a means of insulting waste from the environment, to form a national waste processing program, and to create a registry for tracking where spent atomic fuel is stored or buried. The bill comes on the heels of a November 1991 decree by Russian President Boris Yeltsin to step up efforts to deal with nuclear waste issues and to create a government registry of nuclear waste disposal sites by 1 January 1993. The former Soviet Union has come under fire from environmentalists for dumping low- and intermediate-level nuclear wastes in the Arctic Ocean and for improperly storing waste at sites in the southern Urals and Belarus. Adding to the bill's urgency is the fact that Russia is considering sites for underground repositories for high-level waste at Tomsk, Krasnoyarsk, Chelyabinsk, and on the Kola Peninsula

  18. Nuclear waste management: storage and disposal aspects

    International Nuclear Information System (INIS)

    Patterson, B.D.; Dave, S.A.; O'Connell, W.J.

    1980-01-01

    Long-term disposal of nuclear wastes must resolve difficulties arising chiefly from the potential for contamination of the environment and the risk of misuse. Alternatives available for storage and disposal of wastes are examined in this overview paper. Guidelines and criteria which may govern in the development of methods of disposal are discussed

  19. Disposal of high-activity nuclear wastes

    International Nuclear Information System (INIS)

    Hamilton, E.I.

    1983-01-01

    A discussion is presented on the deep sea ocean disposal for high-activity nuclear wastes. The following topics are covered: effect of ionizing radiation on marine ecosystems; pathways by which radionuclides are transferred to man from the marine environment; information about releases of radioactivity to the sea; radiological protection; storage and disposal of radioactive wastes and information needs. (U.K.)

  20. Safety in depth for nuclear waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Ringwood, T [Australian National Univ., Canberra. Research School of Earth Sciences

    1980-11-27

    A nuclear waste disposal strategy is described in which the radionuclides are immobilised in widely-dispersed drill holes in an extremely stable and leach resistant titanate ceramic form (SYNROC) at depths of 1500 to 4000 metres. The advantages of this method over that of burying such wastes in large centralised mined repositories at 500 to 700 metres in suitable geological strata are examined.

  1. The management of nuclear waste

    International Nuclear Information System (INIS)

    1982-01-01

    This film explains how radioactive wastes arise and how they are treated so as to minimise effect on man and the environment. The nature of the wastes, whether solid, liquid or gas, and their classification as low, intermediate or high, depending on their type and the degree of radioactivity, and with the treatment, disposal, containment and dispersal of wastes are described. (author)

  2. The nuclear waste in France

    International Nuclear Information System (INIS)

    Anon.

    2006-01-01

    French people are expecting from authorities that it become possible to recycle the radioactive wastes in order to make them disappear or to transform them in ordinary wastes without radioactivity, and in waiting for this time we can be organised to monitor these waste in order to react without delay if for any reason they become dangerous. (N.C.)

  3. Legal aspects of nuclear waste management

    International Nuclear Information System (INIS)

    Hofmann, H.

    1981-01-01

    The result of the study is that the nuclear waste management defined by sect. 9a of the Atomic Energy Law cannot be realized without violating the constitution or other relevant laws. This evaluation of the nuclear waste management concept is based on an in-depth discussion of technological difficulties involved in nuclear waste management, and on the examination of all existing rules and regulations (Radiation Protection Ordinance, intermediate storage and burial, and reprocessing) at home and abroad, which lead to legal aspects of nuclear waste management which, according to established German law, are to be characterized as being 'unclear'. The author demonstrates especially the lack of precision in law of the term 'radioactive waste'. He points out that a sufficient regulation on the dismantlement of nuclear reactors is missing and he sets forth uncertainties relating to administrative law which are involved in bringing in private companies for burial as it is provided by law. The concluding constitutional assessment of the nuclear waste management regulation of the Atomic Energy Law shows that sect. 9a of the Atomic Energy Law does not meet completely constitutional requirements. (orig./HP) [de

  4. The legal system of nuclear waste disposal

    International Nuclear Information System (INIS)

    Dauk, W.

    1983-01-01

    This doctoral thesis presents solutions to some of the legal problems encountered in the interpretation of the various laws and regulations governing nuclear waste disposal, and reveals the legal system supporting the variety of individual regulations. Proposals are made relating to modifications of problematic or not well defined provisions, in order to contribute to improved juridical security, or inambiguity in terms of law. The author also discusses the question of the constitutionality of the laws for nuclear waste disposal. Apart from the responsibility of private enterprise to contribute to safe treatment or recycling, within the framework of the integrated waste management concept, and apart from the Government's responsibility for interim or final storage of radioactive waste, there is a third possibility included in the legal system for waste management, namely voluntary measures taken by private enterprise for radioactive waste disposal. The licence to be applied for in accordance with section 3, sub-section (1) of the Radiation Protection Ordinance is interpreted to pertain to all measures of radioactive waste disposal, thus including final storage of radioactive waste by private companies. Although the terminology and systematic concept of nuclear waste disposal are difficult to understand, there is a functionable system of legal provisions contained therein. This system fits into the overall concept of laws governing technical safety and safety engineering. (orig./HSCH) [de

  5. The risk evaluation of a model of a high-level waste solidification plant

    International Nuclear Information System (INIS)

    Bruecher, H.

    1977-02-01

    In this report the risk associated with the operation of a plant for vitrification of high-level liquid waste is evaluated. Considerung risk assessment it turns out that the important accidents occur during off-gas cleaning. On the other hand effects of explosions in the process equipment don't contribute very much to the overall risk. These data are compared with the risk resulting from routine discharge of the plant. It is of the same magnitude as or greater than the most important accident risks. (orig.) [de

  6. Immobilization of strontium and cesium in intermediate-level liquid wastes by solidification in cements

    International Nuclear Information System (INIS)

    Rudolph, G.; Koester, R.

    1979-01-01

    An accelerated leach test at elevated temperature has been developed which gives intercomparable results within one day. It is very useful for product quality control at large throughputs. Using this test, it has been shown that cesium leachabilities from cement products containing a simulated waste typical of fuel reprocessing plants can be reduced by addition of a bentonite. Addition of barium silicate hydrate retards strontium leaching in these cements. Leach rates in tap water and in salt brine are lower than in distilled water and sodium chloride solution

  7. Nuclear Waste Disposal Program 2016

    International Nuclear Information System (INIS)

    2016-12-01

    This comprehensive brochure published by the Swiss National Cooperative for the Disposal of Radioactive Waste (NAGRA) discusses the many important steps in the management of radioactive waste that have already been implemented in Switzerland. The handling and packaging of waste, its characterisation and inventorying, as well as its interim storage and transport are examined. The many important steps in Swiss management of radioactive waste already implemented and wide experience gained in carrying out the associated activities are discussed. The legal framework and organisational measures that will allow the selection of repository sites are looked at. The various aspects examined include the origin, type and volume of radioactive wastes, along with concepts and designs for deep geological repositories and the types of waste to be stored therein. Also, an implementation plan for the deep geological repositories, the required capacities and the financing of waste management activities are discussed as is NAGRA’s information concept. Several diagrams and tables illustrate the program

  8. Radiation Effects in Nuclear Waste Materials

    International Nuclear Information System (INIS)

    Weber, William J.

    2005-01-01

    The objective of this project is to develop a fundamental understanding of radiation effects in glasses and ceramics, as well as the influence of solid-state radiation effects on aqueous dissolution kinetics, which may impact the performance of nuclear waste forms and stabilized nuclear materials. This work provides the underpinning science to develop improved glass and ceramic waste forms for the immobilization and disposition of high-level tank waste, excess plutonium, plutonium residues and scrap, other actinides, and other nuclear waste streams. Furthermore, this work is developing develop predictive models for the performance of nuclear waste forms and stabilized nuclear materials. Thus, the research performed under this project has significant implications for the immobilization of High-Level Waste (HLW) and Nuclear Materials, two mission areas within the Office of Environmental Management (EM). With regard to the HLW mission, this research will lead to improved understanding of radiation-induced degradation mechanisms and their effects on dissolution kinetics, as well as development of predictive models for waste form performance. In the Nuclear Materials mission, this research will lead to improvements in the understanding of radiation effects on the chemical and structural properties of materials for the stabilization and long-term storage of plutonium, highly-enriched uranium, and other actinides. The research uses plutonium incorporation, ion-beam irradiation, and electron-beam irradiation to simulate the effects of alpha decay and beta decay on relevant glasses and ceramics. The research under this project has the potential to result in improved glass and ceramic materials for the stabilization and immobilization of high-level tank waste, plutonium residues and scraps, surplus weapons plutonium, highly-enriched uranium, other actinides, and other radioactive materials

  9. Natural analogues of nuclear waste glass corrosion

    International Nuclear Information System (INIS)

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

    1999-01-01

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

  10. Radiation Effects in Nuclear Waste Materials

    International Nuclear Information System (INIS)

    Weber, William J.; Wang, Lumin; Hess, Nancy J.; Icenhower, Jonathan P.; Thevuthasan, Suntharampillai

    2003-01-01

    The objective of this project is to develop a fundamental understanding of radiation effects in glasses and ceramics, as well as the influence of solid-state radiation effects on aqueous dissolution kinetics, which may impact the performance of nuclear waste forms and stabilized nuclear materials. This work provides the underpinning science to develop improved glass and ceramic waste forms for the immobilization and disposition of high-level tank waste, excess plutonium, plutonium residues and scrap, other actinides, and other nuclear waste streams. Furthermore, this work is developing develop predictive models for the performance of nuclear waste forms and stabilized nuclear materials. Thus, the research performed under this project has significant implications for the immobilization of High-Level Waste (HLW) and Nuclear Materials, two mission areas within the Office of Environmental Management (EM). With regard to the HLW mission, this research will lead to improved understanding of radiation-induced degradation mechanisms and their effects on dissolution kinetics, as well as development of predictive models for waste form performance. In the Nuclear Materials mission, this research will lead to improvements in the understanding of radiation effects on the chemical and structural properties of materials for the stabilization and long-term storage of plutonium, highly-enriched uranium, and other actinides. The research uses plutonium incorporation, ion-beam irradiation, and electron-beam irradiation to simulate the effects of alpha decay and beta decay on relevant glasses and ceramics. The research under this project has the potential to result in improved glass and ceramic materials for the stabilization and immobilization of high-level tank waste, plutonium residues and scraps, surplus weapons plutonium, highly-enriched uranium, other actinides, and other radioactive materials

  11. Natural analogues of nuclear waste glass corrosion.

    Energy Technology Data Exchange (ETDEWEB)

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

    1999-01-06

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

  12. A disposal centre for immobilized nuclear waste

    International Nuclear Information System (INIS)

    1980-02-01

    This report describes a conceptual design of a disposal centre for immobilized nuclear waste. The surface facilities consist of plants for the preparation of steel cylinders containing nuclear waste immobilized in glass, shaft headframe buildings and all necessary support facilities. The underground disposal vault is located on one level at a depth of 1000 m. The waste cylinders are emplaced into boreholes in the tunnel floors. All surface and subsurface facilities are described, operations and schedules are summarized, and cost estimates and manpower requirements are given. (auth)

  13. Social dimensions of nuclear waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Grunwald, Armin [Karlsruhe Institute of Technology, Karlsruhe (Germany). Inst. for Technology Assessment and Systems Analysis

    2015-07-01

    Nuclear waste disposal is a two-faceted challenge: a scientific and technological endeavour, on the one hand, and confronted with social dimensions, on the other. In this paper I will sketch the respective social dimensions and will give a plea for interdisciplinary research approaches. Relevant social dimensions of nuclear waste disposal are concerning safety standards, the disposal 'philosophy', the process of determining the disposal site, and the operation of a waste disposal facility. Overall, cross-cutting issues of justice, responsibility, and fairness are of major importance in all of these fields.

  14. Social dimensions of nuclear waste disposal

    International Nuclear Information System (INIS)

    Grunwald, Armin

    2015-01-01

    Nuclear waste disposal is a two-faceted challenge: a scientific and technological endeavour, on the one hand, and confronted with social dimensions, on the other. In this paper I will sketch the respective social dimensions and will give a plea for interdisciplinary research approaches. Relevant social dimensions of nuclear waste disposal are concerning safety standards, the disposal 'philosophy', the process of determining the disposal site, and the operation of a waste disposal facility. Overall, cross-cutting issues of justice, responsibility, and fairness are of major importance in all of these fields.

  15. World Nuclear Association position statement: Safe management of nuclear waste and used nuclear fuel

    International Nuclear Information System (INIS)

    Saint-Pierre, Sylvain

    2006-01-01

    This WNA Position Statement summarises the worldwide nuclear industry's record, progress and plans in safely managing nuclear waste and used nuclear fuel. The global industry's safe waste management practices cover the entire nuclear fuel-cycle, from the mining of uranium to the long-term disposal of end products from nuclear power reactors. The Statement's aim is to provide, in clear and accurate terms, the nuclear industry's 'story' on a crucially important subject often clouded by misinformation. Inevitably, each country and each company employs a management strategy appropriate to a specific national and technical context. This Position Statement reflects a confident industry consensus that a common dedication to sound practices throughout the nuclear industry worldwide is continuing to enhance an already robust global record of safe management of nuclear waste and used nuclear fuel. This text focuses solely on modern civil programmes of nuclear-electricity generation. It does not deal with the substantial quantities of waste from military or early civil nuclear programmes. These wastes fall into the category of 'legacy activities' and are generally accepted as a responsibility of national governments. The clean-up of wastes resulting from 'legacy activities' should not be confused with the limited volume of end products that are routinely produced and safely managed by today's nuclear energy industry. On the significant subject of 'Decommissioning of Nuclear Facilities', which is integral to modern civil nuclear power programmes, the WNA will offer a separate Position Statement covering the industry's safe management of nuclear waste in this context. The paper's conclusion is that the safe management of nuclear waste and used nuclear fuel is a widespread, well-demonstrated reality. This strong safety record reflects a high degree of nuclear industry expertise and of industry responsibility toward the well-being of current and future generations. Accumulating

  16. Thermodynamic evaluation of the solidification phase of molten core–concrete under estimated Fukushima Daiichi nuclear power plant accident conditions

    Energy Technology Data Exchange (ETDEWEB)

    Kitagaki, Toru, E-mail: kitagaki.toru@jaea.go.jp; Yano, Kimihiko; Ogino, Hideki; Washiya, Tadahiro

    2017-04-01

    The solidification phases of molten core–concrete under the estimated molten core–concrete interaction (MCCI) conditions in the Fukushima Daiichi Nuclear Power Plant Unit 1 were predicted using the thermodynamic equilibrium calculation tool, FactSage 6.2, and the NUCLEA database in order to contribute toward the 1F decommissioning work and to understand the accident progression via the analytical results for the 1F MCCI products. We showed that most of the U and Zr in the molten core–concrete forms (U,Zr)O{sub 2} and (Zr,U)SiO{sub 4}, and the formation of other phases with these elements is limited. However, the formation of (Zr,U)SiO{sub 4} requires a relatively long time because it involves a change in the crystal structure from fcc-(U,Zr)O{sub 2} to tet-(U,Zr)O{sub 2}, followed by the formation of (Zr,U)SiO{sub 4} by reaction with SiO{sub 2}. Therefore, the formation of (Zr,U)SiO{sub 4} is limited under quenching conditions. Other common phases are the oxide phases, CaAl{sub 2}Si{sub 2}O{sub 8}, SiO{sub 2}, and CaSiO{sub 3}, and the metallic phases of the Fe–Si and Fe–Ni alloys. The solidification phenomenon of the crust under quenching conditions and that of the molten pool under thermodynamic equilibrium conditions in the 1F MCCI progression are discussed.

  17. Corrosion of simulated nuclear waste glass

    International Nuclear Information System (INIS)

    Music, S.; Ristic, M.; Gotic, M.; Foric, J.

    1988-01-01

    In this study the preparation and characterization of borosilicate glasses of different chemical composition were investigated. Borosilicate glasses were doped with simulated nuclear waste oxides. The chemical corrosion in water of these glasses was followed by measuring the leach rates as a function of time. It was found that a simulated nuclear waste glass with the chemical composition (weight %), 15.61% Na 2 O, 10.39% B 2 O 3 , 45.31% SiO 2 , 13.42% ZnO, 6.61% TiO 2 and 8.66% waste oxides, is characterized by low melting temperature and with good corrosion resistance in water. Influence of passive layers on the leaching behaviour of nuclear waste glasses is discussed. (author) 20 refs.; 7 figs.; 4 tabs

  18. Sulfur polymer cement, a solidification and stabilization agent for radioactive and hazardous wastes

    International Nuclear Information System (INIS)

    Darnell, R.G.

    1993-01-01

    Sulfur polymer cement (SPC) is made by reacting 95% sulfur with 2.5 % dicyclopentadiene and 2.5% cyclopentadiene oligomers, to produce a product that is much better than unmodified sulfur. SPC is being tested as a solidifying and stabilizing agent for low-level radioactive and hazardous wastes. Heavy loadings (5 wt%) of eight toxic metals were combined individually with SPC and 7 wt% sodium sulfide nonahydrate. The leach rates for mercury, lead, chromium and silver oxides were reduced by six orders of magnitude, while those of arsenic and barium were reduced by four. SPC is good for stabilizing incinerator ash. Ion-exchange resins can be stabilized with SPC after heat treatment with asbestos or diatomite at 220-250 deg C. 19 refs

  19. Nuclear waste package fabricated from concrete

    International Nuclear Information System (INIS)

    Pfeiffer, P.A.; Kennedy, J.M.

    1987-03-01

    After the United States enacted the Nuclear Waste Policy Act in 1983, the Department of Energy must design, site, build and operate permanent geologic repositories for high-level nuclear waste. The Department of Energy has recently selected three sites, one being the Hanford Site in the state of Washington. At this particular site, the repository will be located in basalt at a depth of approximately 3000 feet deep. The main concern of this site, is contamination of the groundwater by release of radionuclides from the waste package. The waste package basically has three components: the containment barrier (metal or concrete container, in this study concrete will be considered), the waste form, and other materials (such as packing material, emplacement hole liners, etc.). The containment barriers are the primary waste container structural materials and are intended to provide containment of the nuclear waste up to a thousand years after emplacement. After the containment barriers are breached by groundwater, the packing material (expanding sodium bentonite clay) is expected to provide the primary control of release of radionuclide into the immediate repository environment. The loading conditions on the concrete container (from emplacement to approximately 1000 years), will be twofold; (1) internal heat of the high-level waste which could be up to 400 0 C; (2) external hydrostatic pressure up to 1300 psi after the seepage of groundwater has occurred in the emplacement tunnel. A suggested container is a hollow plain concrete cylinder with both ends capped. 7 refs

  20. Solidification and Biotoxicity Assessment of Thermally Treated Municipal Solid Waste Incineration (MSWI) Fly Ash.

    Science.gov (United States)

    Gong, Bing; Deng, Yi; Yang, Yuanyi; Tan, Swee Ngin; Liu, Qianni; Yang, Weizhong

    2017-06-10

    In the present work, thermal treatment was used to stabilize municipal solid waste incineration (MSWI) fly ash, which was considered hazardous waste. Toxicity characteristic leaching procedure (TCLP) results indicated that, after the thermal process, the leaching concentrations of Pb, Cu, and Zn decreased from 8.08 to 0.16 mg/L, 0.12 to 0.017 mg/L and 0.39 to 0.1 mg/L, respectively, which well met the limits in GB5085.3-2007 and GB16689-2008. Thermal treatment showed a negative effect on the leachability of Cr with concentrations increasing from 0.1 to 1.28 mg/L; nevertheless, it was still under the limitations. XRD analysis suggested that, after thermal treatments, CaO was newly generated. CaO was a main contribution to higher Cr leaching concentrations owing to the formation of Cr (VI)-compounds such as CaCrO₄. SEM/EDS tests revealed that particle adhesion, agglomeration, and grain growth happened during the thermal process and thus diminished the leachability of Pb, Cu, and Zn, but these processes had no significant influence on the leaching of Cr. A microbial assay demonstrated that all thermally treated samples yet possessed strong bactericidal activity according to optical density (OD) test results. Among all samples, the OD value of raw fly ash (RFA) was lowest followed by FA700-10, FA900-10, and FA1100-10 in an increasing order, which indicated that the sequence of the biotoxicity for these samples was RFA > FA700-10 > FA900-10 > FA1100-10. This preliminary study indicated that, apart from TCLP criteria, the biotoxicity assessment was indispensable for evaluating the effect of thermal treatment for MSWI fly ash.