Programme and french realizations concerning alpha wastes

International Nuclear Information System (INIS)

Sousselier, Y.

1978-01-01

Water reactors and breeder spent fuels are reprocessed to recover plutonium, minimise wastes and decrease irradiation risks. Alloys formation, glass addition and vitrification or metallic matrix are studied to treat cladding hulls. Plutonium content is controlled by alpha spectrometry or prompt neutrons measurements or neutrons activation. Wastes are calcinated or crushed at low temperature to recover transuranium elements by solvent extraction or precipitation or ionic exchange or ultrafiltration. Wastes are calcinated or crushed at low temperature to recover transuranium elements by solvent extraction or precipitation or ionic exchange or ultrafiltration. Wastes are embedded into bitumen or thermosetting resins and long term storage in geologic formation is studied [fr

Institute for transuranium elements Karlsruhe Annual Report 1988

International Nuclear Information System (INIS)

1989-01-01

The present report summarizes the results of the work which has been performed in 1988 at the Institute for Transuranium Elements of the Joint Research Centre of the Commission of the European Communities. While, as in the past, major efforts were devoted to the Programme on Nuclear Fuels and Actinide Research, important contributions were made to other JRC Specific Programmes, i.e. Reactor Safety, Radioactive Waste Management, and Safeguards and Fissile Materials Control. In addition, The Institute has carried out analytical work for the EURATOM Safeguards Directorate and executed research tasks in the safeguards context, both, for the Commission of the European Communities and for the International Atomic Energy Agency in Vienna. Exploratory Research, finally, dealt with an investigation of possibilities of acoustic aerosol scavenging

Long-time safety aspects of ultimate storage of transuranium elements

International Nuclear Information System (INIS)

Storck, R.

1992-10-01

Based on the amounts of transuranium elements generated in nuclear reactors, the inventories of these elements in the repository are described for various ultimate disposal strategies. The data are used to give an outline description of accident-induced ingress of brines into the backfilled repository shaft during the post-closure period and the resulting mechanisms of a mobilization of the transuranium elements and their escape from the repository, and to calculate amounts released. The effects of the released transuranium elements on the biosphere and the different contributions of the various isotopes to the calculated radiation exposure are given as an estimate and are described in more detail by means of data determined by parameter variation. The effects of transuranium elements during the entire migration process are restricted to the production of daughter nuclides, especially of the uranium isotopes. They give no particular contribution to environmental radiation exposure because of their low mobility. With the only exception of Np-237 which, due to its long half-time and relatively good migration capacity, can reach the biosphere. The contributions of the transuranium elements to the dose maxima, caused by the daughter products, of the uranium isotopes or the neptunium are calculated to be about 50%. All publications to date presenting a safety analysis of the site of the Gorleben repository assume the dose maxima of all uranium isotopes together to be approx. 10%, and those of the neptunium isotope approx. 20%, referring to the most significant fission products. This indicates that uranium or neptunium are of secondary significance in the process, and the other transuranium elements are only third-rate. (orig./HP) [de

Ecological effects from transuranium elements in terrestrial environment

International Nuclear Information System (INIS)

Uiker, F.U.

1985-01-01

To understand ecological effects from transuranium elements in environment it is necessary to know how their chemical, physical and biological behaviour depends on duration of their being in natural environment. It is necesary to take into account that behaviour of transuranium elements in environment depends on physical and chemical forms of a nuclide as well as on characteristics of ecosystem. Radiation dose of certain tissues plays an essential role here but dose distribution is especially complicated for relatively non-soluble α-irradiators

Nuclear reactions and synthesis of new transuranium species

International Nuclear Information System (INIS)

Seaborg, G.T.

1983-01-01

In this short review, I shall describe the special aspects of heavy ion nuclear reaction mechanisms operative in the transuranium region, the role of new techniques, possible nuclear reactions for the production of additional transuranium elements and nuclear species and the importance of work in this region for the development of nuclear models and theoretical concepts. This discussion should make it clear that a continuing supply of leements and isotopes, some fo them relatively short-lived, produced by the HFIR-TRU facilities, will be a requirement for future synthesis of new elements and isotopes

Nuclear fission and the transuranium elements

International Nuclear Information System (INIS)

Seaborg, G.T.

1989-02-01

Many of the transuranium elements are produced and isolated in large quantities through the use of neutrons furnished by nuclear fission reactions: plutonium (atomic number 94) in ton quantities; neptunium (93), americium (95), and curium (96) in kilogram quantities; berkelium (97) in 100 milligram quantities; californium (98) in gram quantities; and einsteinium (99) in milligram quantities. Transuranium isotopes have found many practical applications---as nuclear fuel for the large-scale generation of electricity, as compact, long-lived power sources for use in space exploration, as means for diagnosis and treatment in the medical area, and as tools in numerous industrial processes. Of particular interest is the unusual chemistry and impact of these heaviest elements on the periodic table. This account will feature these aspects. 9 refs., 5 figs

Nuclear fission and the transuranium elements

Energy Technology Data Exchange (ETDEWEB)

Seaborg, G.T.

1989-02-01

Many of the transuranium elements are produced and isolated in large quantities through the use of neutrons furnished by nuclear fission reactions: plutonium (atomic number 94) in ton quantities; neptunium (93), americium (95), and curium (96) in kilogram quantities; berkelium (97) in 100 milligram quantities; californium (98) in gram quantities; and einsteinium (99) in milligram quantities. Transuranium isotopes have found many practical applications---as nuclear fuel for the large-scale generation of electricity, as compact, long-lived power sources for use in space exploration, as means for diagnosis and treatment in the medical area, and as tools in numerous industrial processes. Of particular interest is the unusual chemistry and impact of these heaviest elements on the periodic table. This account will feature these aspects. 9 refs., 5 figs.

Transuranium elements leaching from simulated HLW glasses in synthetic interstitial claywater

International Nuclear Information System (INIS)

Wang, L.

1992-08-01

The main objective of this Master Thesis is to measure the steady-state concentrations of Pu, Np, and Am upon the leaching of High-Level Waste Glass in two types of synthetic claywater: humic acid free and humic acid containing synthetic claywater. The synthetic claywater has a composition that is representative for the in-situ interstitial groundwater of the Boom clay formation, a potential geological repository of radioactive waste in Belgium. The steady-state concentrations of transuranium elements were measured by leaching experiments with a typical duration of 400 days. Five main conclusions are drawn from the experimental data. (1) The transuranium elements that are released from simulated High Level Waste Glass are dominantly present in the synthetic claywater solutions as colloids. These colloids are smaller than 2 nm in absence of humic acids. In the presence of humic acids however, the colloids interact with actinides (adsorb or coagulate) and form particles larger than 2 nm. Np and Am are associated with inorganic and organic colloids in the synthetic interstitial claywater solution whereas Pu forms only inorganic colloids. (2) The steady-state concentration of Pu is in good agreement with the solubility of the Pu compound PuO 2 .xH 2 O. It is therefore concluded that PuO 2 .xH 2 O is the solubility controlling phase. (3) The Pu(IV)-species are dominant in the leaching solutions. Carbonate and humic acid complexes are negligible. (4) The steady-state concentrations of Np and Am in leaching solutions were much lower than the values calculated on the basis of known thermodynamic data. This indicates that the solubility controlling phases for Np and Am were not correctly identified or that the measured Np and Am concentrations were not steady-state values. (5) Non-active glass leaching tests have indicated that no organic colloids were formed as a result of glass dissolution. (A.S.)

Uranium chloride extraction of transuranium elements from LWR fuel

International Nuclear Information System (INIS)

Miller, W.E.; Ackerman, J.P.; Battles, J.E.; Johnson, T.R.; Pierce, R.D.

1992-01-01

A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels containing rare earth and noble metal fission products as well as other fission products is disclosed. The oxide fuel is reduced with Ca metal in the presence of Ca chloride and a U-Fe alloy which is liquid at about 800 C to dissolve uranium metal and the noble metal fission product metals and transuranium actinide metals and rare earth fission product metals leaving Ca chloride having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein. The Ca chloride and CaO and the fission products contained therein are separated from the U-Fe alloy and the metal values dissolved therein. The U-Fe alloy having dissolved therein reduced metals from the spent nuclear fuel is contacted with a mixture of one or more alkali metal or alkaline earth metal halides selected from the class consisting of alkali metal or alkaline earth metal and Fe or U halide or a combination thereof to transfer transuranium actinide metals and rare earth metals to the halide salt leaving the uranium and some noble metal fission products in the U-Fe alloy and thereafter separating the halide salt and the transuranium metals dissolved therein from the U-Fe alloy and the metals dissolved therein. 1 figure

Nuclear power: Health implications of transuranium elements

International Nuclear Information System (INIS)

1982-01-01

This report provides general guidelines for national public health and environmental authorities. It does not provide detailed technical data, but instead broadly surveys the whole field, indicating the present position as assessed by members of the Working Group. The Working Group considered three major facets: physiological, toxicological and dosimetric aspects of the transuranium elements; the application of occupational health control, including health physics; and environmental behaviour together with public health implications associated with the transuranium elements. The intention was to cover all aspects relevant to health, with respect both to those who are occupationally engaged in work with such elements and to the general public who might be affected as the result of such operations. Consideration was also given to routine and emergency situations

Treatment of incorporated transuranium elements

International Nuclear Information System (INIS)

Volf, V.

1978-01-01

The text of this report and its tables and figures provide basic information on the decorporation of transuranium elements as well as an insight into the more general principles, trends and interactions. The detailed tables and the exhaustive list of important references should enable the reader to make his own conclusions in a minimum of time

Magnesium transport extraction of transuranium elements from LWR fuel

International Nuclear Information System (INIS)

Ackerman, J.P.; Battles, J.E.; Johnson, T.R.; Miller, W.E.; Pierce, R.D.

1992-01-01

This patent describes a process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuel containing rare earth and noble metal fission products as well as fission products of alkali metals, alkaline earth metals and iodine. It comprises reducing the oxide fuel with Ca metal in the presence of Ca halide; separating the Ca halide with the CaO and the fission products contained therein from the U-Fe alloy and the metal values dissolved therein and electrolytically contacting the calcium salts with a carbon electrode; contacting the liquid U-Fe alloy having dissolved therein reduced metals from the spent nuclear fuel with liquid Mg metal, thereafter separating the liquid Mg and the metals dissolved therein from the U-Fe alloy and the metal dissolved therein, distilling the Mg from the transuranium actinide and rare earth metals, recontacting the U-Fe alloy with liquid Mg metal a sufficient number of times until not less than about 99% by weight of the transuranium actinide values have been removed from the U-Fe alloy

Development of RBWR (Resource-renewable BWR) for environmental burden reduction of radioactive wastes

International Nuclear Information System (INIS)

Hino, Tetsushi; Ohtsuka, Masaya; Moriya, Kumiaki; Matsuura, Masayoshi

2014-01-01

Accumulation of long-life transuranium elements produced as by-products with uranium fuel burning became an issue of nuclear power. Hitachi had been developing the reactor with transuranium elements burning as fuels based on BWR type reactors successfully used as commercial reactors: RBWR (Resource-renewable BWR). Efficient transmutation and fissioning of transuranium elements needed adjustment of in-core neutron energy spectra distribution better for nuclear reaction of transuranium elements. Taking advantage of characteristics of BWR type reactors with neutron spectra hardening more easily adjustable than other type of reactors, multiple recycling and fissioning transuranium elements as fuels could make environmental burden reduction of radioactive wastes and efficient use of resources compatible. This article described the concept and history of RBWR and showed its specifications and reactor core characteristics. (T. Tanaka)

Storing solid radioactive wastes at the Savannah River Plant

International Nuclear Information System (INIS)

Horton, J.H.; Corey, J.C.

1976-06-01

The facilities and the operation of solid radioactive waste storage at the Savannah River Plant (SRP) are discussed in the report. The procedures used to segregate and the methods used to store radioactive waste materials are described, and the monitoring results obtained from studies of the movement of radionuclides from buried wastes at SRP are summarized. The solid radioactive waste storage site, centrally located on the 192,000-acre SRP reservation, was established in 1952 to 1953, before any radioactivity was generated onsite. The site is used for storage and burial of solid radioactive waste, for storage of contaminated equipment, and for miscellaneous other operations. The solid radioactive waste storage site is divided into sections for burying waste materials of specified types and radioactivity levels, such as transuranium (TRU) alpha waste, low-level waste (primarily beta-gamma), and high-level waste (primarily beta-gamma). Detailed records are kept of the burial location of each shipment of waste. With the attention currently given to monitoring and controlling migration, the solid wastes can remain safely in their present location for as long as is necessary for a national policy to be established for their eventual disposal. Migration of transuranium, activation product, and fission product nuclides from the buried wastes has been negligible. However, monitoring data indicate that tritium is migrating from the solid waste emplacements. Because of the low movement rate of ground water, the dose-to-man projection is less than 0.02 man-rem for the inventory of tritium in the burial trenches. Limits are placed on the amounts of beta-gamma waste that can be stored so that the site will require minimum surveillance and control. The major portion (approximately 98 percent) of the transuranium alpha radioactivity in the waste is stored in durable containers, which are amenable to recovery for processing and restorage should national policy so dictate

Pyrochemical extraction for selective removal of transuranium elements from molten LiCl-KCl

International Nuclear Information System (INIS)

Ackermann, J.P.; Johnson, T.R.

1993-01-01

Recent determinations of separation factors that describe partition of the actinide and rare earth elements between liquid cadmium and LiCl-KCl eutectic allowed identification of a process for selective removal of the transuranium (TRU) element chlorides from the electrolyte used for electrofining of metal fuel from the Integral Fast Reactor. It is periodically necessary to remove rare earth elements from the electrolyte to limit heat generation from radioactive decay. Countercurrent extraction of electrolyte with uranium in cadmium solution allows retention of valuable TRU elements in the reprocessed fuel, and results in a rare earth waste stream that is essentially free of TRU elements and their concomitant long-term hazards

Wastes and waste management in the uranium fuel cycle for light water reactors

International Nuclear Information System (INIS)

Costello, J.M.

1975-08-01

The manufacturing processes in the uranium fuel cycle for light water reactors have been described with particular reference to the chemical and radiological wastes produced and the waste management procedures employed. The problems and possible solutions of ultimate disposal of high activity fission products and transuranium elements from reprocessing of irradiated fuel have been reviewed. Quantities of wastes arising in each stage of the fuel cycle have been summarised. Wastes arising from reactor operation have been described briefly. (author)

Transuranic contaminated waste form characterization and data base

International Nuclear Information System (INIS)

Kniazewycz, B.G.; McArthur, W.C.

1980-07-01

This volume contains appendices A to F. The properties of transuranium (TRU) radionuclides are described. Immobilization of TRU wastes by bituminization, urea-formaldehyde polymers, and cements is discussed. Research programs at DOE facilities engaged in TRU waste characterization and management studies are described

Transuranium element purification by liquid-liquid extraction

International Nuclear Information System (INIS)

Madic, C.; Koehly, G.

1976-01-01

In the transuranium element production, the liquid-liquid extraction purification is presented. The affinity of TBP and trilaurylammonium nitrate for these elements is given. Exemples of NP/Pu, Pu/Np, U/Pu, Am/Cm, Am and Cm/Ln separation are presented [fr

Apparent distribution coefficients of transuranium elements in UK coastal waters

International Nuclear Information System (INIS)

Kershaw, P.J.; Pentreath, R.J.; Harvey, B.R.; Lovett, M.B.; Boggis, S.J.

1986-01-01

The authorized inputs of low-level radioactive waste into the Irish Sea from the British Nuclear Fuels plc reprocessing plant at Sellafield may be used to advantage to study the distribution and behaviour of artificial radionuclides in the marine environment. Apparent distribution coefficients (Ksub(d)) for the transuranium elements Np, Pu, Am and Cm have been determined by the analysis of environmental samples collected from UK coastal waters. The sampling methodology for obtaining suspended sediment-seawater Ksub(d)s by filtration is described and critically evaluated. Artefacts may be introduced in the sample collection stage. Ksub(d) values have also been determined for seabed sediment-interstitial waters and the precautions taken to preserve in-situ chemical conditions are described. Variations in Ksub(d) values are discussed in relation to distance from Sellafield, suspended load, redox conditions and oxidation state changes. (author)

The transuranium elements: From neptunium and plutonium to element 112

International Nuclear Information System (INIS)

Hoffman, D.C.

1996-01-01

Beginning in the 1930's, both chemists and physicists became interested in synthesizing new artificial elements. The first transuranium element, Np, was synthesized in 1940. Over the past six decades, 20 transuranium elements have been produced. A review of the synthesis is given. The procedure of naming the heavy elements is also discussed. It appears feasible to produce elements 113 and 114. With the Berkeley Gas-filled Separator, it should be possible to reach the superheavy elements in the region of the spherical Z=114 shell, but with fewer neutrons than the N=184 spherical shell. 57 refs, 6 figs

Proceedings of transuranium elements

International Nuclear Information System (INIS)

Anon.

1992-01-01

The identification of the first synthetic elements was established by chemical evidence. Conclusive proof of the synthesis of the first artificial element, technetium, was published in 1937 by Perrier and Segre. An essential aspect of their achievement was the prediction of the chemical properties of element 43, which had been missing from the periodic table and which was expected to have properties similar to those of manganese and rhenium. The discovery of other artificial elements, astatine and francium, was facilitated in 1939-1940 by the prediction of their chemical properties. A little more than 50 years ago, in the spring of 1940, Edwin McMillan and Philip Abelson synthesized element 93, neptunium, and confirmed its uniqueness by chemical means. On August 30, 1940, Glenn Seaborg, Arthur Wahl, and the late Joseph Kennedy began their neutron irradiations of uranium nitrate hexahydrate. A few months later they synthesized element 94, later named plutonium, by observing the alpha particles emitted from uranium oxide targets that had been bombarded with deuterons. Shortly thereafter they proved that is was the second transuranium element by establishing its unique oxidation-reduction behavior. The symposium honored the scientists and engineers whose vision and dedication led to the discovery of the transuranium elements and to the understanding of the influence of 5f electrons on their electronic structure and bonding. This volume represents a record of papers presented at the symposium

Radioactive waste management in the VS military nuclear industry

International Nuclear Information System (INIS)

Kobal'chuk, O.V.; Kruglov, A.K.; Sokolova, I.D.; Smirnov, Yu.V.

1989-01-01

Organization and plans of radioactive waste management in the US military nuclear industry, determining transition from the policy of temporal waste storage to their final and safe disposal are presented. Programs of long-term management of high-level, transuranium and low-level wastes, the problems of the work financing and the structure of management activities related to the radioactive waste processing military nuclear industry enterprises are considered

Transuranium nuclides in the environment

International Nuclear Information System (INIS)

1976-01-01

Projected development of nuclear power up to the year 2000 entails a substantial increase in the number of nuclear power reactors, of irradiated fuel reprocessing plants and of various other supporting facilities in the nuclear fuel cycle. In this period, transuranium elements, especially plutonium, will be produced in substantial quantities as by-products of the fission process and for use as fuel in present and future nuclear power reactors; these elements will have other peaceful applications as well. Growing world-wide interest and a natural desire to protect man and his environment have led to increasing concern in public, scientific and governmental sectors about the, release of such radionuclides into the environment. Although releases of transuranium nuclides from existing nuclear facilities can be controlled to very low levels, it is essential, in view of their long half-lives and high relative radiotoxicities, that their fate in the environment be understood well enough to permit associated potential impacts to be assessed and hence effective control to be provided. Extensive studies for many years have investigated the distribution and behaviour of these elements and potential detriments resulting from their release to the environment. More recently, scientists have begun to make projections for evaluating the degree of control necessary if such materials are to enter the complex chain of commercial activities associated with nuclear power production

Radiological safety considerations in the design and operation of the ORNL Transuranium Research Laboratory (TRL)

International Nuclear Information System (INIS)

Haynes, C.E.

1976-01-01

The Transuranium Research Laboratory (TRL) is the central facility at Oak Ridge National Laboratory (ORNL) for chemical and physical research involving transuranium elements. Transuranium Research Laboratory investigations are about equally divided between studies of inorganic and structural chemistry of the heavy elements and nuclear structure and properties of their isotopes. Elements studied include neptunium, plutonium, americium, curium, berkelium, californium, and einsteinium, each in microgram-to-gram quantities depending upon availability and experimental requirements. This paper describes an eight-step safety procedure followed in planning and approving individual research projects. This procedure should provide an optimum margin of safety and should permit the accomplishment of successful research

Prolixe-prototype reprocessing unit for irradiating wastes contamined with alpha emitters

International Nuclear Information System (INIS)

Madic, C.; Sontag, R.

1987-01-01

A large number of hot cells are employed for research on nuclear fuel reprocessing and the production of isotope of transuranium elements. These activities generate solid wastes highly contaminated with alpha, beta, gamma emitters. The Prolixe hot cell was built in order to: 1/ reprocess the solid wastes contaminated with alpha, beta, gamma emitters produced in the Radiochemistry building: 2/ produce package wastes storable in shallow-ground disposal sites: 3/ develop a process sufficiently flexible to make it applicable to waste produced in other installations. The process is based on waste leaching after grinding. Depending on the type of wastes the leaching reactant will have a different composition 1/ nitric acid solution for cellulose waste: 2/ nitric solutions containing Ag(II) for other material. The complete process should achieve: 1/ a high waste volume reduction factor: 2/ the production of immobilized waste packages storage in shallow-ground disposal sites: 3/ the recycling of transuranium elements: 4/ the generation of a minimal volume of effluents. This process can be considered as an alternative process to incineration for the reprocessing of solid wastes highly contaminated with alpha, beta, gamma emitters

Chemical process engineering in the transuranium processing plant

International Nuclear Information System (INIS)

Collins, E.D.; Bigelow, J.E.

1976-01-01

Since operation of the Transuranium Processing Plant began, process changes have been made to counteract problems caused by equipment corrosion, to satisfy new processing requirements, and to utilize improved processes. The new processes, equipment, and techniques have been incorporated into a sequence of steps which satisfies all required processing functions

Californium production at the transuranium processing plant

International Nuclear Information System (INIS)

King, L.J.

1976-01-01

The Transuranium Processing Plant (TRU) at ORNL, which is the production, storage, and distribution center for the ERDA heavy element research program, is described. About 0.5 percent of 252 Cf is currently being produced. TRU is a hot-cell, chemical processing facility of advanced design. New concepts have been incorporated into the facility for absolute containment, remote operation, remote equipment installation, and remote maintenance. The facilities include a battery of nine heavily shielded process cells served by master-slave manipulators and eight laboratories, four on each of two floors. Processing includes chemical dissolution of the targets followed by a series of solvent extraction, ion exchange, and precipitation steps to separate and purify the transuranium elements. The transcurium elements Bk, Cf, Es, and Fm are distributed to users. Remote techniques are used to fabricate the Am and Cm into target rods for reirradiation in the HFIR. Californium-252 that is in excess of the needs of the heavy element research program and the Cf sales program is stored at TRU and processed repeatedly to recover the daughter product 248 Cm, which is a highly desirable research material

Recent progress of the United States transuranium and uranium registries

International Nuclear Information System (INIS)

Kathren, R.L.

1986-01-01

This paper provides a brief overview of the history and objectives of the US Transuranium and Uranium Registries along with a discussion of some recent activities and accomplishments of these two parallel programs. 17 refs

Status of transuranium element production

International Nuclear Information System (INIS)

King, L.J.

1985-01-01

The Transuranium Processing Plant at Oak Ridge National Laboratory has been the production, storage, and distribution center for the heavy-element research program of the US Department of Energy since 1966. During the past four years, annual production rates of transcurium elements have been relatively stable, averaging 34 mg of 249 Bk, 369 mg of 252 Cf, 1.4 mg of 253 Es, and 0.7 pg of 257 Fm. The extensive provisions for changing and modifying equipment have allowed continual updating of the plant to include new concepts in chemical processes and equipment design. 21 refs., 4 figs., 2 tabs

Transuranium perrhenates: Np(IV), Pu(IV) and (III), Am (III)

International Nuclear Information System (INIS)

Silvestre, Jean-Paul; Freundlich, William; Pages, Monique

1977-01-01

Synthesis in aqueous solution and by solid state reactions, crystallographical characterization and study of the stability of some transuranium perrhenates: Asup(n+)(ReO 4 - )sub(n) (A=Np(IV), Pu(IV), Pu(III), Am(III) [fr

Biology of the transuranium elements: an indexed bibliography

International Nuclear Information System (INIS)

Thompson, R.C.

1976-07-01

This bibliography on the biology of the transuranium elements is a revision of one issued in 1973 (BNWL-1782). It includes essentially all of the citations from the earlier document, a few corrections and additions from the older literature, plus the new literature to mid-1975. It also includes a subject-matter index not present in the original document

Biology of the transuranium elements: an indexed bibliography

Energy Technology Data Exchange (ETDEWEB)

Thompson, R.C. (comp.)

1976-07-01

This bibliography on the biology of the transuranium elements is a revision of one issued in 1973 (BNWL-1782). It includes essentially all of the citations from the earlier document, a few corrections and additions from the older literature, plus the new literature to mid-1975. It also includes a subject-matter index not present in the original document.

Preparation Technology and Study of Properties of New Detectors for Transuranium Elements

International Nuclear Information System (INIS)

Andrushchenko, G.Yu.; Blank, A.B.; Budakovsky, S.V.; Zelenska, O.V.; Shevtsov, M.I.

2006-01-01

A porous composite materials is described for determination of radionuclides in aquatic objects of the environment. Possibilities have been studied for the use of this material in monitoring of α-nuclides content in natural waters. The composite is a scintillator with through pores, the surface of which is impregnated by a sorbent that is selective with respect to transuranium elements. The structure of the material allows combination of two processes - concentrating the radionuclide and measuring its activity. as selective sorbent to transuranium elements an anion-exchange resin VP-1Ap was used. Studies of material functionality were carried out using the model systems based on reference radioactive solutions 239 Pu

The transuranium elements: Members of the 5f series

International Nuclear Information System (INIS)

Gruen, D.M.

1990-01-01

The Symposium to commemorate the fiftieth anniversary of the discovery of the transuranium elements is an appropriate occasion on which to review the history of the development of ideas concerning the electronic structure of the new elements which, by determining their chemistry, would fix their position in the Periodic Table. Seaborg's actinide hypothesis was based on the properties of Np and Pu, as well as those of transuranium elements discovered after 1940. The elaboration of this hypothesis, with its profound consequences for our current understanding of the Periodic Table, will be traced from its beginnings to its present status, making use of the wealth of spectroscopic and magnetic data accumulated over the years to draw conclusions about the electronic structure of the actinides. Np and Pu, in particular, offered the first possibility for detailed study of the binding energies of 5f versus 6d electrons. The rich chemistry of these two elements is still providing new insights into the subtleties of electronic structure

Evolution in radioactive waste countermeasures

International Nuclear Information System (INIS)

Moriguchi, Yasutaka

1984-01-01

The establishment of radioactive waste management measures is important to proceed further with nuclear power development. While the storage facility projects by utilities are in progress, large quantity of low level wastes are expected to arise in the future due to the decommissioning of nuclear reactors, etc. An interim report made by the committee on radioactive waste countermeasures to the Atomic Energy Commission is described as follows: the land disposal measures of ultra-low level and low level radioactive wastes, that is, the concept of level partitioning, waste management, the possible practice of handling wastes, etc.; the treatment and disposal measures of high level radioactive wastes and transuranium wastes, including task sharing among respective research institutions, the solidification/storage and the geological formation disposal of high level wastes, etc. (Mori, K.)

Leachability of bituminized radioactive waste. Literature survey

International Nuclear Information System (INIS)

Akimoto, Toshiyuki; Nakayama, Shinichi; Iida, Yoshihisa; Nagano, Tetsushi

1999-02-01

Bituminized radioactive waste that will be returned from COGEMA, France is planned to be disposed of in deep geologic repository in Japan. Data on leachability of radionuclides from bituminized waste are required for the performance assessment of the disposal. We made a literature survey on bitumen and bituminized radioactive waste, placing emphasis on leach tests and leach data in terms of geologic disposal. This survey revealed that reliable leach data on transuranium elements and data obtained under reducing conditions that is characteristic to deep underground are lacking. (author). 64 refs

Almost twenty years' search of transuranium isotopes in effluents discharged to air from nuclear power plants with VVER reactors.

Science.gov (United States)

Hölgye, Z; Filgas, R

2006-04-01

Airborne effluents of 5 stacks (stacks 1-5) of three nuclear power plants, with 9 pressurized water reactors VVER of 4,520 MWe total power, were searched for transuranium isotopes in different time periods. The search started in 1985. The subject of this work is a presentation of discharge data for the period of 1998-2003 and a final evaluation. It was found that 238Pu, 239,240Pu, 241Am, 242Cm, and 244Cm can be present in airborne effluents. Transuranium isotope contents in most of the quarterly effluent samples from stacks 2, 4 and 5 were not measurable. Transuranium isotopes were present in the effluents from stack l during all 9 years of the study and from stack 3 since the 3rd quarter of 1996 as a result of a defect in the fuel cladding. A relatively high increase of transuranium isotopes in effluents from stack 3 occurred in the 3rd quarter of 1999, and a smaller increase occurred in the 3rd quarter of 2003. In each instance 242Cm prevailed in the transuranium isotope mixtures. 238Pu/239,240Pu, 241Am/239,240Pu, 242Cm/239,240Pu, and 244Cm/239,240Pu ratios in fuel for different burn-up were calculated, and comparison of these ratios in fuel and effluents was performed.

Results of two years' operation of the waste processing cell PROLIXE

International Nuclear Information System (INIS)

Lecomte, M.; Madic, C.; Broudic, J.C.

1990-01-01

Solid wastes, contaminated by alpha, beta, gamma radioisotopes, are produced by spent fuel reprocessing and isotope production. The PROLIXE plant, prototype for leaching and encapsulation was put into operation in March 1988 for waste management with the following aims: development of decontamination by oxidative leaching of alpha wastes, to obtain less than 0.1 Ci/t for surface storage; recycling radioactive isotope recovered especially transuranium elements; define a versatile process for various solid radioactive waste for an industrial plant [fr

Ion-ion interaction and energy transfer of 4+ transuranium ions in cerium tetrafluoride

International Nuclear Information System (INIS)

Liu, G.K.; Beitz, J.V.

1990-01-01

Dynamics of excited 5f electron states of the transuranium ions Cm 4+ and Bk 4+ in CeF 4 are compared. Based on time- and wavelength-resolved laser-induced fluorescence, excitation energy transfer processes have been probed. Depending on concentration and electronic energy level structure of the studied 4+ transuranium ion, the dominant energy transfer mechanisms were identified as cross relaxation, exciton-exciton annihilation, and trapping. Energy transfer rates derived from the fitting of the observed fluorescence decays to theoretical models, based on electric multipolar ion-ion interactions, are contrasted with prior studies of 4f states of 3+ lanthanide and 3d states of transition metal ions. 16 refs., 1 tab

Institute for transuranium elements Karlsruhe. Annual report 1989

International Nuclear Information System (INIS)

1990-01-01

Transient-tested high burn-up fuel samples were investigated by electron microscopy to study the effect of strain on fission product distribution, and the concentration of (U,Pu)O 2 agglomerates in irradiated MOX fuel was examined by electron microprobe analysis. Conclusions on maximum temperatures to which the core of the Three Mile Island reactor was exposed could be drawn from an examination of TMI fuel debris. Equipment to measure thermophysical fuel properties for reactor safety studies was further developed. An improved version (slice version) of the TRANSURANUS fuel pin code was tested and released for external use. Safety Aspects of Fuel Operation and Handling were dealt with by improving preparation methods of (U,Pu)N. Release and resuspension of radioactive dust particles in fires was studied. The principal objective of the Actinide Determination and Recycling activity was the reduction of long-term hazards of alpha-bearing nuclear waste. The long-term storage behaviour of UO 2 and MOX spent fuel samples as well as of vitrified waste forms was further investigated by studying the effect of leaching. The electronic structure of the transuranium elements is the central objective of basic Actinide Research. A large number of ternary alloys containing Np or Pu and Si or Ge, together with a transition metal was prepared for basic experimental studies. New high-pressure phases were discovered in PuSe, UPS, ThO 2 , and PuO 2 . Analytical techniques were evaluated and automated for safeguards. A multiwavelength pyrometer was adapted for industrial use. Major contracts with Third Parties were dealing with the development of minor actinide alloys, and the post-irradiation examination of high burn-up UO 2 and MOX fuel from LWR power stations

Transition of transuranium radionuclides to the stock-raising production at the grazing land of the cattle on the territory of the radioactive contamination

International Nuclear Information System (INIS)

Kudryashov, V.P.; Korol', R.A.; Pershukevich, E.V.; Bykovskij, V.V.

2009-01-01

As a result of receipt of transuranium elements in an organism of cattle probably pollution of animal produces by significant amounts of transuranium elements and their receipt on a food chain in a human body. (authors)

Effect of microbial processes on transuranium elements behaviour in soil, plants and animal organism

International Nuclear Information System (INIS)

Uajldung, R.Eh.; Garlend, T.P.

1985-01-01

Results of preliminary studies discussed in the present paper bring about the supposition that concentration and chemical from of an element in a plant play an essential role in variation of its availability for animals consuming plants. That is why any assessment of long-term behaviour of transuranium elements in terrestrialenvironment should be based on determination of factors affecting solubility and forms of soluble compounds in soil. These factors include concentration and chemical form of the element migrating to soil; effect of the properties of soil on element distribution between solid and liquid phases; effect soil processes on kinetics of sorption reactions, concentration of transuranium elements, forms of soluble and non-soluble chemical compounds

Radioactive waste management

International Nuclear Information System (INIS)

Alfredson, P.G.; Levins, D.M.

1975-08-01

Present and future methods of managing radioactive wastes in the nuclear industry are reviewed. In the stages from uranium mining to fuel fabrication, the main purpose of waste management is to limit and control dispersal into the environment of uranium and its decay products, particularly radium and radon. Nuclear reactors produce large amounts of radioactivity but release rates from commercial power reactors have been low and well within legal limits. The principal waste from reprocessing is a high activity liquid containing essentially all the fission products along with the transuranium elements. Most high activity wastes are currently stored as liquids in tanks but there is agreement that future wastes must be converted into solids. Processes to solidify wastes have been demonstrated in pilot plant facilities in the United States and Europe. After solidification, wastes may be stored for some time in man-made structures at or near the Earth's surface. The best method for ultimate disposal appears to be placing solid wastes in a suitable geological formation on land. (author)

Overview of management programs for plutonium-contaminated solid waste in the U.S.A

International Nuclear Information System (INIS)

Ramsey, R.W. Jr.; Daly, G.H.

1975-01-01

Programs for transuranium-contaminated solid wastes (TRU) in the U.S.A. are emphasizing a reduction in waste generation and the development of appropriate treatments to reduce the volume of wastes requiring interim storage and final disposal. Research and Development is emphasizing the establishment of sufficient information on treatment, hazards and storage to adopt a standardized procedure for handling wastes during an interim retrievable period and for final disposal. Federal responsibility for TRU waste is being proposed except for minimum amounts acceptable for commercial burial

Hanford environment as related to radioactive waste burial grounds and transuranium waste storage facilities

Energy Technology Data Exchange (ETDEWEB)

Brown, D.J.; Isaacson, R.E.

1977-06-01

A detailed characterization of the existing environment at Hanford was provided by the U.S. Energy Research and Development Administration (ERDA) in the Final Environmental Statement, Waste Management Operations, Hanford Reservation, Richland, Washington, December 1975. Abbreviated discussions from that document are presented together with current data, as they pertain to radioactive waste burial grounds and interim transuranic (TRU) waste storage facilities. The discussions and data are presented in sections on geology, hydrology, ecology, and natural phenomena. (JRD)

Hanford environment as related to radioactive waste burial grounds and transuranium waste storage facilities

International Nuclear Information System (INIS)

Brown, D.J.; Isaacson, R.E.

1977-06-01

A detailed characterization of the existing environment at Hanford was provided by the U.S. Energy Research and Development Administration (ERDA) in the Final Environmental Statement, Waste Management Operations, Hanford Reservation, Richland, Washington, December 1975. Abbreviated discussions from that document are presented together with current data, as they pertain to radioactive waste burial grounds and interim transuranic (TRU) waste storage facilities. The discussions and data are presented in sections on geology, hydrology, ecology, and natural phenomena

United States Transuranium and Uranium Registries

International Nuclear Information System (INIS)

Kathren, R.L.; Filipy, R.E.; Dietert, S.E.

1991-06-01

This report summarizes the primary scientific activities of the United States Transuranium and Uranium Registries for the period October 1, 1989 through September 30, 1990. The Registries are parallel human tissue research programs devoted to the study of the actinide elements in humans. To date there have been 261 autopsy or surgical specimen donations, which include 11 whole bodies. The emphasis of the Registry was directed towards quality improvement and the development of a fully computerized data base that would incorporate not only the results of postmortem radiochemical analysis, but also medical and monitoring information obtained during life. Human subjects reviews were also completed. A three compartment biokinetic model for plutonium distribution is proposed. 2 tabs

United States Transuranium and Uranium Registries. Annual report February 1, 2001 - January 31, 2002

International Nuclear Information System (INIS)

Ehrhart, Susan M.; Filipy, Ronald E.

2002-01-01

This report documents the activities of the United States Transuranium and Uranium Registries (USTUR) from February 2001 through January 2002. Progress in continuing collaborations and several new collaborations is reviewed

United States Transuranium and Uranium Registries. Annual report February 1, 2001--January 31, 2002

Energy Technology Data Exchange (ETDEWEB)

Ehrhart, Susan M. (ed.); Filipy, Ronald E. (ed)

2002-07-01

This report documents the activities of the United States Transuranium and Uranium Registries (USTUR) from February 2001 through January 2002. Progress in continuing collaborations and several new collaborations is reviewed.

Statistical analysis of radiochemical measurements of TRU radionuclides in REDC waste

International Nuclear Information System (INIS)

Beauchamp, J.; Downing, D.; Chapman, J.; Fedorov, V.; Nguyen, L.; Parks, C.; Schultz, F.; Yong, L.

1996-10-01

This report summarizes results of the study on the isotopic ratios of transuranium elements in waste from the Radiochemical Engineering Development Center actinide-processing streams. The knowledge of the isotopic ratios when combined with results of nondestructive assays, in particular with results of Active-Passive Neutron Examination Assay and Gamma Active Segmented Passive Assay, may lead to significant increase in precision of the determination of TRU elements contained in ORNL generated waste streams

An evaluation of the food chain pathway for transuranium elements dispersed in soils

International Nuclear Information System (INIS)

Linsley, G.S.; Simmonds, J.R.; Kelly, G.N.

1978-12-01

Man can be exposed to radiation from transuranium elements dispersed in soils by two main routes; through the inhalation of resuspended particles and by ingestion of food products derived from the contaminated soils. In this report relationships are derived between the concentration in soil of two radionuclides, plutonium-239 and americium-241, and the dose to man. The transfer of the transuranium radionuclides through the food chains to man is evaluated using compartment models which are dynamic in character. The two pathways to man are of the same order of importance, within the uncertainties of the available data, and both must be considered in dose assessments. The technique of sensitivity analysis is used to identify areas where further research and investigations are necessary to improve the reliability of the assessment of radiation dose to man. (author)

Transuranium elements in macroalgae at Monaco following the Chernobyl accident

International Nuclear Information System (INIS)

Holm, E.; Ballestra, S.; Lopez, J.J.; Barci-Funel, G.; Ardisson, G.

1991-01-01

The atmospheric deposition and transfer of transuranium elements (TU) to macroalgae at Monaco following the Chernobyl accident has been studied. The deposition of TU was small compared to most fission products: 239+240 Pu and 241 Am could not be detected in water or algae, 242 Cm was the dominant α emitter detected in Chernobyl fallout. Concentration factors of TU for the macroalgae are estimated

Recent developments in the extraction separation method for treatment of high-level liquid waste

International Nuclear Information System (INIS)

Jiao Rongzhou; Song Chongli; Zhu Yongjun

2000-01-01

A description and review of the recent developments in the extraction separation method for partitioning transuranium elements from high-level liquid waste (HLLW) is presented. The extraction separation processes such as TRUEX process, DIAMEX process, DIDPA process, CTH process, TRPO process are briefly discussed

Radioactive waste disposal

International Nuclear Information System (INIS)

Cluchet, J.; Roger, B.

1975-10-01

After mentioning the importance of the problem of the disposal of wastes produced in the electro-nuclear industry, a short reminder on a few laws of radioactivity (nature and energy of radiations, half-life) and on some basic dosimetry is given. The conditioning and storage procedures are then indicated for solid wastes. The more active fractions of liquid wastes are incorporated into blocks of glass, whereas the less active are first concentrated by chemical treatments or by evaporation. The concentrates are then embedded into concrete, asphalt or resins. Storage is done according to the nature of each type of wastes: on a hard-surfaced area or inside concrete-lined trenches for the lowest radioactivity, in pits for the others. Transuranium elements with very long half-lives are buried in very deep natural cavities which can shelter them for centuries. From the investigations conducted so far and from the experience already gained, it can be concluded that safe solutions are within our reach [fr

Inventory and sources of transuranic solid waste

International Nuclear Information System (INIS)

1978-08-01

In the past, solid radioactive waste has often been buried in the most accessible and convenient vacant place, without a great deal of thought for the long-term consequences. The transuranium (TRU) elements were very strictly conserved and, at first, solid waste containing separated fission products was not a serious land burial problem. Wartime pressures for production and lack of knowledge or understanding led to siting and operational practices that, in many situations, are unsatisfactory by present day standards. Purpose of this report is to support the development of standards and criteria which will specifically address the problem of TRU contaminated waste generated by Department of Energy (DOE) nuclear programs and commercial application of nuclear technology. This report covers: DOE facilities, commercial disposal sites, commercial nuclear industry, TRU-contaminated waste inventory, and waste projections

Partitioning and transmutation of transuranium elements under nuclear phase-out conditions. Technically reliable?; Transmutation von Transuranen unter den Randbedingungen des Kernenergieausstiegs. Technisch machbar?

Energy Technology Data Exchange (ETDEWEB)

Merk, Bruno; Rohde, Ulrich [Helmholtz-Zentrum Dresden-Rossendorf, Dresden (Germany)

2016-04-15

The German government has decided for the nuclear phase out, but a decision on a strategy for the management of the highly radioactive waste is not defined yet. Partitioning and Transmutation (P and T) could be considered as a technological option in the process of management of highly radioactive waste management, therefore a wide study has been conducted. In this group objectives for P and T and the boundary conditions of the phase out have been discussed. The fulfillment of the given objectives is analyzed using simulations of molten salt reactors with fast neutron spectrum. It is shown that the efficient transmutation of all existing transuranium isotopes would be possible in 3 to 4 reactors in a time frame of 45 to 60 years. Further on a detailed balance of different isotopic inventories is given to allow a deeper understanding of the processes during transmutation.

Selective separation of actinides and long-lived fission products from 1 AW MTR liquid waste: pilot plant tests part II

International Nuclear Information System (INIS)

Grossi, G.; Marrocchelli, A.; Pietrelli, L.; Calle, C.; Gili, M.; Luce, A.; Troiani, F.

1992-01-01

In Italy there are some 120 m 3 of liquid High-level radioactive Wastes coming from MTR, Candu and EPK River fuel elements reprocessing. These High-level radioactive wastes contain a large amount of chemicals and inert salts together with cesium, strontium and transuranium elements. Transuranium elements and strontium are separated from the inert salts by means of a selective precipitation while Cesium is adsorbed on synthetic zeolithes (AZE Process) or precipitated with sodium Tetraphenyl borate (NaTPB) (ATE process). The benchscale experiments have confirmed the feasibility of selective separation processes and have showed that decontamination efficiency for strontium, plutonium and cesium were, respectively, 100, 5000 and 1000. This second part of the CEC final report describes Searse pilot plant tests with cold experiments. 37 Refs.; 17 Figs.; 16 Tabs

Transuranium Processing Plant semiannual report of production, status, and plans for period ending June 30, 1977

International Nuclear Information System (INIS)

King, L.J.; Bigelow, J.E.; Collins, E.D.

1977-12-01

During the period January 1, 1977, through June 30, 1977, the following amounts of transuranium elements were recovered from 12 irradiated HFIR targets: 0.1g 243 Am, 21g 244 Cm, 29.5 mg 249 Bk, 288 mg 252 Cf, 1.48 mg 253 Es, and 0.7 pg 257 Fm. One batch of high-purity 248 Cm (approximately 50 mg) was separated from 252 Cf. Twenty-three shipments were made from TRU during the period; recipients and the amounts of nuclides are tabulated. Five HFIR targets, each containing 8 to 9 g of curium, were fabricated. During the next 18 months, we expect to obtain totals of 92 mg of 249 Bk, 910 mg of 252 Cf, 3.8 mg of 253 Es (in a mixture of isotopes), 615 μg of high-purity 253 Es, and 1.6 pg of 257 Fm; we also expect to make available 250 mg of high-purity 248 Cm. No process or equipment changes were made during this report period. Five neutron sources were fabricated during this report period, bringing the total fabricated to date to 97. Two sources that had previously been returned to TRU were reassigned. Special projects included the following: (1) the enrichment of the 244 Pu concentration in 100 mg of plutonium by irradiation to burn out the lighter isotopes, (2) the separation of 245 pg of 254 Cf from 39-hr /sup 254m/Es that was produced by irradiation of 5 μg of 253 Es, and (3) an experimental separation of cerium from the other rare-earth elements in a TRU process waste solution. The values that we are currently using for transuranium element decay data and for cross-section data in planning irradiation-processing cycles, calculating production forecasts, and assaying products are tabulated in the Appendix

Incineration of PWR actinide waste to launch a low waste thorium-based energy production with ADSs

International Nuclear Information System (INIS)

Flocard, H.; David, S.; Naulin, F.; Schapira, J.P.

2001-01-01

We investigate a scenario for a smooth transition from an energy production based on PWR to one relying on the Thorium cycle. The reactors used during the transition are solid-fuel fast-neutron Accelerator Driven Systems whose initial fuel incorporates the Transuranium waste produced by the PWRs. Our work relies on a realistic computation of the neutronics of these systems. The benefits of implementing this scenario (compared to exploiting PWRs) in terms of the reduction of the total radiotoxicity (interim storage, final waste, and in core material) is evaluated along and after the transition period as well as the impact on a future repository. (author)

New high-level waste management technology for IFR pyroprocessing wastes

International Nuclear Information System (INIS)

Ackerman, J.P.; Johnson, T.R.

1993-01-01

The pyrochemical electrorefining process for recovery of actinides in spent fuel from the Integral Fast Reactor accumulates fission product wastes as chlorides dissolved in molten LiCI-KCI and as metals, some of which are in molten cadmium. Pyrochemical processes are being developed to recover uranium and transuranium elements for return to the reactor, and to separate and immobilize fission products in suitable waste forms. Solvent cadmium is recycled within the process. Electrolyte salt is treated in a series of salt/cadmium extraction steps; it is also returned to the process. Salt-borne fission products are concentrated on a zeolite bed that is converted to a stable, leach-resistant mineral. Rare earth fission products from the salt, noble metal fission products, and cladding hulls are dispersed in a metal matrix

Environmental and biological behaviour of plutonium and some other transuranium elements

International Nuclear Information System (INIS)

Richmond, C.R.

1983-01-01

The objectives are to summarize our knowledge of the way in which plutonium and some other transuranium elements migrate through ecosystems; to consider how the physiochemical state of these elements and the biological systems through which they pass may influence this movement; and to put into perspective the risks of serious illness in man resulting from his exposure to these elements in the environment

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

International Nuclear Information System (INIS)

Kuncoro Arief, H; M Birmano, Dj

1998-01-01

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

Technical papers presented at a DOE meeting on criteria for cleanup of transuranium elements in soil

International Nuclear Information System (INIS)

1984-09-01

Transuranium element soil contamination cleanup experience gained from nuclear weapons accidents and cleanup at Eniwetok Atoll was reviewed. Presentations have been individually abstracted for inclusion in the data base

Radioactive waste management and regulation

International Nuclear Information System (INIS)

Willrich, M.; Lester, R.K.; Greenberg, S.C.; Mitchell, H.C.; Walker, D.A.

1977-01-01

Purpose of this book is to assist in developing public policy and institutions for the safe management of radioactive waste, currently and long term. Both high-level waste and low-level waste containing transuranium elements are covered. The following conclusions are drawn: the safe management of post-fission radioactive waste is already a present necessity and an irreversible long-term commitment; the basic goals of U.S. radioactive waste policy are unclear; the existing organization for radioactive waste management is likely to be unworkable if left unchanged; and the existing framework for radioactive waste regulation is likely to be ineffective if left unchanged. The following recommendations are made: a national Radioactive Waste Authority should be established as a federally chartered public corporation; with NRC as the primary agency, a comprehensive regulatory framework should be established to assure the safety of all radioactive waste management operations under U.S. jurisdiction or control; ERDA should continue to have primary government responsibility for R and D and demonstration of radioactive waste technology; and the U.S. government should propose that an international Radioactive Waste Commission be established under the IAEA

Separation of transuranium elements and fission products from medium activity aqueous liquid wastes

International Nuclear Information System (INIS)

Gompper, K.; Kunze, S.; Eden, G.; Loesch, G.; Zemski, C.

1986-01-01

In the course of work performed between January 1981 and June 1985 on the separation of TRU elements and fission products three liquid alpha containing waste streams were treated: - medium level waste solutions, - waste solutions from the acid digestion of burnable alpha containing solid residues, - waste solutions from mixed oxide fuel element fabrication. The method of separation was initially developed and optimized with simulating substances. Subesequently it was tested with real waste solutions

Critical masses for the even-neutron-numbered transuranium actinides

International Nuclear Information System (INIS)

Westfall, R.M.

1981-01-01

As part of a standards effort of the American Nuclear Society to establish subcritical mass limits for the transuranium actinides, critical masses were calculated for seven actinides, critical masses were calculated for seven actinide elements in bare, water-reflected, and steel-reflected metal systems. For the nuclides /sup 242/Pu and /sup 241/Am, values obtained with ENDF/B-V cross-section data were in much better agreement with values inferred from experimental measurement than were initial values calculated with ENDF/B-IV data. A brief description of the analytical methods employed is followed by a presentation of the results. 10 refs

Transuranium contamination in BWRs after fuel accidents and its impact on decommissioning exposures and costs

Energy Technology Data Exchange (ETDEWEB)

Lundgren, K.

1996-12-01

The theme of the present study is to quantify the amount of transuranium activity in different parts of the plant after various fuel accidents, and which impact such contamination has on radiation exposure and costs for decommissioning the plant. The consequences of four different accident degrees have been treated: Common fuel failures, e.g. in line with recent experiences from Swedish BWRs; Fuel channel obstruction resulting in partial melting of one fuel assembly; Total loss of electric power resulting in partial meltdown of the core, but with primary circuit intact preventing a massive contamination of the containment; A LOCA followed by a core meltdown and melting and penetration of the reactor pressure vessel. The amount of transuranium activity distributed, the form of this activity and the plant contamination are evaluated for these accidents. The costs and exposures have been split up on cleanup activities after the accident and decommissioning. 75 refs.

Transuranium contamination in BWRs after fuel accidents and its impact on decommissioning exposures and costs

International Nuclear Information System (INIS)

Lundgren, K.

1996-12-01

The theme of the present study is to quantify the amount of transuranium activity in different parts of the plant after various fuel accidents, and which impact such contamination has on radiation exposure and costs for decommissioning the plant. The consequences of four different accident degrees have been treated: Common fuel failures, e.g. in line with recent experiences from Swedish BWRs; Fuel channel obstruction resulting in partial melting of one fuel assembly; Total loss of electric power resulting in partial meltdown of the core, but with primary circuit intact preventing a massive contamination of the containment; A LOCA followed by a core meltdown and melting and penetration of the reactor pressure vessel. The amount of transuranium activity distributed, the form of this activity and the plant contamination are evaluated for these accidents. The costs and exposures have been split up on cleanup activities after the accident and decommissioning. 75 refs

First-principles calculations of the thermodynamic properties of transuranium elements in a molten salt medium

International Nuclear Information System (INIS)

Noh, Seunghyo; Kwak, Dohyun; Lee, Juseung; Kang, Joonhee; Han, Byungchan

2014-01-01

We utilized first-principles density-functional-theory (DFT) calculations to evaluate the thermodynamic feasibility of a pyroprocessing methodology for reducing the volume of high-level radioactive materials and recycling spent nuclear fuels. The thermodynamic properties of transuranium elements (Pu, Np and Cm) were obtained in electrochemical equilibrium with a LiCl-KCl molten salt as ionic phases and as adsorbates on a W(110) surface. To accomplish the goal, we rigorously calculated the double layer interface structures on an atomic resolution, on the thermodynamically most stable configurations on W(110) surfaces and the chemical activities of the transuranium elements for various coverages of those elements. Our results indicated that the electrodeposition process was very sensitive to the atomic level structures of Cl ions at the double-layer interface. Our studies are easily expandable to general electrochemical applications involving strong redox reactions of transition metals in non-aqueous solutions.

Biological effects of transuranium elements in experimental animals

International Nuclear Information System (INIS)

Bair, W.J.

1975-01-01

Results are reported from life span studies of the biological effects of the transuranium elements ( 238 Pu, 239 Pu, 241 Am, and 242 Cm) on laboratory animals following inhalation, skin absorption, or injection in various chemical forms. The dose levels at which major biological effects have been observed in experimental animals are discussed relative to the maximum permissible lung burden of 0.016 μCi for occupational exposures. Lung cancer has been observed at dose levels equivalent to about 100 times the maximum permissible lung burden. Current experiments directed towards determining whether health effects will occur at lower levels and the mechanisms by which α emitters induce cancer are reviewed. (U.S.)

Synthesis and crystal chemistry of transuranium element chalcogenides. Contribution to the study of the 5f electron localization

International Nuclear Information System (INIS)

Damien, Daniel.

1976-09-01

The synthesis and crystal chemistry of Np, Pu, Am and Cm transuranium element chalcogenides are described. From plutonium, transuranium element chalcogenides exhibit the same crystal structure as their rare-earth homologues. The variations of the lattice constants of these compounds in terms of the atomic number are characterized by the lack of the 5f contraction and are interpreted by a localization of the 5f electrons depending upon the considered transuranium element, the nature of the ligand and the crystal structure. To compare the degree of magnitude of the 5f electron delocalization in various compounds, a delocalization scale is proposed based on a comparison between the molar volumes of actinide and isostructural lanthanide compounds. This scale provides a delocalization coefficient for each compound under study. Examination of these coefficients shows that the 5f electrons, in series of actinide compounds, become localized when going from neptunium to curium and that the delocalization process does not only depend upon overlaps between 5f-6d orbitals of neighbouring actinide atoms; the delocalization coefficients show the existence of a secondary delocalization effect due to overlaps between the p anion and f actinide orbitals which are more important for the Vb anion group (N, P, As, Sb) than for the Vib one (S,Se,Te) [fr

'Masurium' and the 'early transuranium elements' or how discovery of nuclear fission was not clearly seen

International Nuclear Information System (INIS)

Keller, C.

1988-01-01

Fifty years after the discovery of fission, the scientific community is aware that this type of nuclear reaction could have been discovered more than a decade earlier. Noddack, Tacke and Berg announced in 1925 the discovery of elements Z = 43 (masurium) and rhenium (Z = 75), the first one could be detected only in U-bearing minerals. A recent re-examination by P.H.M. von Assche of the published data clearly showed that the original claim for element Z = 43 of the authors in 1925 was correct and, therefore, they detected not only element Z = 43 but also the first fission product. Because this discovery of element Z = 43 could not be repeated by other authors as that time, the scientific credibility of Noddack-Tacke was very low in order to give credit to her proposal that the 'early' transuranium elements by Enrico Fermi might also be fragments of known (lighter) elements. Enrico Fermi in 1934 obtained these 'early' (and as we today know: wrong) transuranium isotopes by irradiation of uranium with neutrons. A 'wrong' periodic system in the thirties which placed Th, Pa and U as 6d-elements and not as 5f-actinides chemically helped to consider these fission products as transuranium elements Z = 93/94. In 1937/38 I. Curie and P. Savitch discovered an 'actinium-nuclide' with 3,5 h half-life which, however, had properties similar to lanthanium and not to actinium, as they stated. (orig.) [de

The trends of radioactive waste disposal

International Nuclear Information System (INIS)

Nomi, Mitsuhiko

1977-01-01

The disposal of radioactive wastes instead of their treatment has come to be important problem. The future development of nuclear fuel can not be expected unless the final disposal of nuclear fuel cycle is determined. Research and development have been made on the basis of the development project on the treatment of radioactive wastes published by Japan Atomic Energy Commission in 1976. The high level wastes produced by the reprocessing installations for used nuclear fuel are accompanied by strong radioactivity and heat generation. The most promising method for their disposal is to keep them in holes dug at the sea bottom after they are solidified. Middle or low level wastes are divided into two groups; one contains transuranium elements and the other does not. These wastes are preserved on the ground or in shallow strata, while the safe abandonment into the ground or the sea has been discussed about the latter. The co-operations among nations are necessary not only for peaceful utilization of atomic energy but also for radioactive waste disposal. (Kobatake, H.)

High temperature slagging incinerator for TRU-waste treatment

International Nuclear Information System (INIS)

Van De Voorde, N.; Hennart, D.; Gijbels, J.; Mergan, L.

1984-01-01

Since 1974 the Belgian Nuclear Study Center (SCK/CEN) at Mol, with the support of the European Communities, has developed an ''integral'' system for the treatment and the conditioning of radioactive contaminated wastes. The system converts directly, at high temperature (1500 0 C), mixtures of combustibles (paper, plastics, rubber etc.) and non-combustibles (metals, soil, sludge, concrete.) contaminated with transuranium elements as well as beta-gamma emitting isotopes, into a chemically inert and physically stable slag. More than 4000 hours of successful operation, with wide variety of simulated waste composition as well as real waste, have confirmed the safe operability of the high temperature sl'Gging incinerator and the connected installations, such as sorting cells, waste shredder, off-gas purification train, slag extraction system, remoted control, and the alpha-containment building. During the fall of 1983, a final confirmation of the performance of the installation was given by the successful accomplishment of an incineration campaign of 16 to 17 tons of simulated solid plutonium contaminated wastes

Technology for commercial radioactive waste management

International Nuclear Information System (INIS)

1979-05-01

Conceptual processes and facilities for treating gaseous and various transuranium (TRU) wastes produced during the past fission portion of the light water reactor fuel cycle are described in volume 2. The goal of the treatment process for TRU wastes and for long-lived radionuclides removed from the gaseous waste streams is to convert these wastes to stable products suitable for placement in geologic isolation repositories. The treatment concepts are based on available technology. They do not necessarily represent an optimum design but are representative of what could be achieved with current technology. In actual applications it is reasonable to expect that there could be some improvement over these concepts that might be reflected in either lower costs or lower environmental impacts or both. These conceptual descriptions do provide a reasonable basis for cost analysis and for development of estimates of environmental impacts. The waste treatment technologies considered here include: high-level waste solidification, packaging of fuel residue, failed equipment and noncombustible waste treatment, general trash and combustible waste treatment, degraded solvent treatment, dilute aqueous waste pretreatment, immobilization of wet and solid wastes, off-gas particle removal systems, fuel reprocessing plant dissolver off-gas treatment, process off-gas treatment, and fuel reprocessing plant atmospheric protection system

Resuspension of the transuranium elements - a review of existing data

International Nuclear Information System (INIS)

Linsley, G.S.

1978-08-01

Resuspension is an important mechanism in the transfer to man of transuranium elements deposited on surfaces in the environment. In this report the data on resuspension are reviewed, including the limited number of relevant measurements which have been made in the United Kingdom. The various models developed to represent the resuspension process are reviewed and the most appropriate, when site specific data are absent, for application in UK conditions are identified. Recommendations are made on the main areas where further environmental studies are required to enable more reliable predictive models to be developed for application in these conditions. (author)

Method of processing chloride waste

International Nuclear Information System (INIS)

Tokiwai, Moriyasu; Tsunashima, Mikiyasu; Horie, Masaaki; Koyama, Masafumi; Sudo, Minoru; Kitagawa, Masatoshi; Ogasawara, Tadashi.

1991-01-01

In a method of applying molten salt electrolysis to chloride wastes discharged from a electrolytic refining step of a dry reprocessing step for spent fuels, and removed with transuranium elements of long half-decaying time, metals capable of alloying with alkali and alkaline earth metals under melting by electrolysis are used as a cathode material, and an electrolytic temperature is made higher than the melting point of salts in a molten salt electrolysis bath, to recover Li, Ca and Na as alloys with the cathode material in a first electrolysis step. Then, the electrolytic temperature is made higher than the melting point of the chloride salts remained in the bath after the electrolysis step described above by using the cathode material, to recover Ba, Rb, Sr and Cs of nuclear fission products also as alloys with the cathode material in a second electrolysis step. Accordingly, the amount of wastes formed can be reduced, and the wastes contain no heat generating nuclear fission elements. (T.M.)

Transmutation of All German Transuranium under Nuclear Phase Out Conditions - Is This Feasible from Neutronic Point of View?

Science.gov (United States)

Merk, Bruno; Litskevich, Dzianis

2015-01-01

The German government has decided for the nuclear phase out, but a decision on a strategy for the management of the highly radioactive waste is not defined yet. Partitioning and Transmutation (P&T) could be considered as a technological option for the management of highly radioactive waste, therefore a wide study has been conducted. In the study group objectives for P&T and the boundary conditions of the phase out have been discussed. The fulfillment of the given objectives is analyzed from neutronics point of view using simulations of a molten salt reactor with fast neutron spectrum. It is shown that the efficient transmutation of all existing transuranium isotopes would be possible from neutronic point of view in a time frame of about 60 years. For this task three reactors of a mostly new technology would have to be developed and a twofold life cycle consisting of a transmuter operation and a deep burn phase would be required. A basic insight for the optimization of the time duration of the deep burn phase is given. Further on, a detailed balance of different isotopic inventories is given to allow a deeper understanding of the processes during transmutation in the molten salt fast reactor. The effect of modeling and simulation is investigated based on three different modeling strategies and two different code versions.

Transmutation of All German Transuranium under Nuclear Phase Out Conditions - Is This Feasible from Neutronic Point of View?

Directory of Open Access Journals (Sweden)

Bruno Merk

Full Text Available The German government has decided for the nuclear phase out, but a decision on a strategy for the management of the highly radioactive waste is not defined yet. Partitioning and Transmutation (P&T could be considered as a technological option for the management of highly radioactive waste, therefore a wide study has been conducted. In the study group objectives for P&T and the boundary conditions of the phase out have been discussed. The fulfillment of the given objectives is analyzed from neutronics point of view using simulations of a molten salt reactor with fast neutron spectrum. It is shown that the efficient transmutation of all existing transuranium isotopes would be possible from neutronic point of view in a time frame of about 60 years. For this task three reactors of a mostly new technology would have to be developed and a twofold life cycle consisting of a transmuter operation and a deep burn phase would be required. A basic insight for the optimization of the time duration of the deep burn phase is given. Further on, a detailed balance of different isotopic inventories is given to allow a deeper understanding of the processes during transmutation in the molten salt fast reactor. The effect of modeling and simulation is investigated based on three different modeling strategies and two different code versions.

The radiological significance of transuranium radioisotopes released to the environment during operation of the LMFBR fuel cycle

International Nuclear Information System (INIS)

Barr, N.F.

1976-01-01

Estimates based on current knowledge and conservative assumptions indicate that release of transuranium elements from the Liquid Metal Fast Breeder Reactor (LMFBR) fuel cycle are likely to proaduce population dose commitments small compared to those produced by naturally occurring alpha emitters and globally dispersed transuranium radioisotopes from tests of nuclear weapons in the atmosphere. Potential health consequences of these releases to current and future generations are estimated to be very small compared to risks associated with the production of energy by fossil fuels. The estimates are subject to a number of uncertainties imposed by lack of knowledge. Some of the uncertainties are not likely to be greatly reduced until LMFBR facilities are designed and operated. Others may be significantly reduced prior to facility design and operation. The paper discusses the sensitivity of the estimates to uncertainties and approches to reducing those uncertainties that strongly influence the estimates. (author)

Basic design of alpha aqueous waste treatment process in NUCEF

Energy Technology Data Exchange (ETDEWEB)

Mineo, Hideaki; Matsumura, Tatsuro; Nishizawa, Ichio; Mitsui, Takeshi; Ueki, Hiroyuki; Wada, Atsushi; Sakai, Ichita; Takeshita, Isao [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Nishimura, Kenji

1996-11-01

This paper described the basic design of Alpha Aqueous Waste Treatment Process in NUCEF. Since various experiments using the TRU (transuranium) elements are carried out in NUCEF, wastes containing TRU elements arise. The liquid wastes in NUCEF are categorized into three types. Decontamination and volume reduction of the liquid waste mainly of recovery water from acid recovery process which has lowest radioactive concentration is the most important task, because the arising rate of the waste is large. The major function of the Alpha Aqueous Waste Treatment Process is to decontaminate the radioactive concentration below the level which is allowed to discharge into sea. Prior the process design of this facility, the followings are evaluated:property and arising rate of the liquid waste, room space to install and licensing condition. Considering varieties of liquid wastes and their large volume, the very high decontamination factor was proposed by a process of multiple evaporation supported with filtration and adsorption in the head end part and reverse osmosis in the distillate part. (author)

Waste Management Operations Program

International Nuclear Information System (INIS)

Sease, J.D.

1983-01-01

The major function of the Program is to operate the Laboratory's systems and facilities for collecting and disposing of radioactive gaseous, liquid, and solid wastes. This includes collection and shallow land burial of about 2000 m 3 of β-γ contaminated waste and retrievable storage of about 60 m 3 of transuranium contaminated waste annually; ion-exchange treatment and release to the environment of about 450 x 10 3 m 3 of slightly contaminated water; volume reduction by evaporation of about 5000 m 3 of intermediate-level liquid waste followed by hydrofracture injection of the concentrate; and scrubbing and/or filtration of the gases from radioactive operations prior to release to the atmosphere. In addition, this year disposal of about 350,000 gal of radioactive sludge from the old (no longer in service) gunite tanks began. Operations are in conformance with rules and regulations presently applicable to ORNL. This Program is responsible for planning and for development activities for upgrading the facilities, equipment, and procedures for waste disposal to ensure ORNL work incorporates the latest technology. Major (line-item) new facilities are provided as well as substantial (GPP) upgrading of old facilities. These activities as well as the technical and engineering support to handle them are discussed

Transuranium element transport in agricultural systems (soil to food chain transfer of nuclear fuel cycle radionuclides). Annual progress report

International Nuclear Information System (INIS)

Wallace, A.

1977-10-01

Progress is reported on the following research projects: preparation of bibliography covering literature on plant uptake of transuranium elements; development of techniques for growth of agricultural crops in large containers that simulate field conditions; equipment for counting of alpha-emitting transuranium elements; studies on variability in concentration ratio of 241 Am under different environmental conditions; alpha radiation burn in bush beans exposed to 241 Am in solution; constancy of concentration ratio as a measure of plant uptake of 241 Am; growth of radishes in soil with and without DTPA, and radish peel as source of radionuclides; effects of varying levels of DTPA in loam soil on concentration ratio values; and a plant species (Atriplex hymenelytra--desert holly) with high C.R. values and search for other plants with high C.R. values

Amster: a molten-salt reactor concept generating its own 233U and incinerating transuranium elements

International Nuclear Information System (INIS)

Lecarpentier, D.; Garzenne, C.; Vergnes, J.; Mouney, H.; Delpech, M.

2002-01-01

In the coming century, sustainable development of atomic energy will require the development of new types of reactors able to exceed the limits of the existing reactor types, be it in terms of optimum use of natural fuel resources, reduction in the production of long-lived radioactive waste, or economic competitiveness. Of the various candidates with the potential to meet these needs, molten-salt reactors are particularly attractive, in the light of the benefits they offer, arising from two fundamental features: - A liquid fuel does away with the constraints inherent in solid fuel, leading to a drastic simplification of the fuel cycle, in particular making in possible to carry out on-line pyrochemical reprocessing; - Thorium cycle and thermal spectrum breeding. The MSBR concept proposed by ORNL in the 1970's thus gave a breeding factor of 1.06, with a doubling time of about 25 years. However, given the tight neutron balance of the thorium cycle (the η of 233 U is about 2.3), MSBR performance is only possible if there are strict constraints set on the in-line reprocessing unit: all the 233 Pa must be removed from the core so that it can decay on the 233 U in no more than about ten days (or at least 15 tonnes of salt to be extracted from the core daily), and the absorbing fission products, in particular the rare earths, must be extracted in about fifty days. With the AMSTER MSR concept, which we initially developed for incinerating transuranium elements, we looked to reduce the mass of salt to be reprocessed in order to minimise the size and complexity of the reprocessing unit coupled to the reactor, and the quantity of transuranium elements sent for disposal, as this is directly proportional to the mass of salt reprocessed for extraction of the fission products. Given that breeding was not an absolute necessity, because the reactor can be started by incinerating the transuranium elements from the spent fuel assemblies of current reactors, or if necessary by loading

Transmutation of All German Transuranium under Nuclear Phase Out Conditions – Is This Feasible from Neutronic Point of View?

Science.gov (United States)

Merk, Bruno; Litskevich, Dzianis

2015-01-01

The German government has decided for the nuclear phase out, but a decision on a strategy for the management of the highly radioactive waste is not defined yet. Partitioning and Transmutation (P&T) could be considered as a technological option for the management of highly radioactive waste, therefore a wide study has been conducted. In the study group objectives for P&T and the boundary conditions of the phase out have been discussed. The fulfillment of the given objectives is analyzed from neutronics point of view using simulations of a molten salt reactor with fast neutron spectrum. It is shown that the efficient transmutation of all existing transuranium isotopes would be possible from neutronic point of view in a time frame of about 60 years. For this task three reactors of a mostly new technology would have to be developed and a twofold life cycle consisting of a transmuter operation and a deep burn phase would be required. A basic insight for the optimization of the time duration of the deep burn phase is given. Further on, a detailed balance of different isotopic inventories is given to allow a deeper understanding of the processes during transmutation in the molten salt fast reactor. The effect of modeling and simulation is investigated based on three different modeling strategies and two different code versions. PMID:26717509

Operation of a pilot incinerator for solid waste

International Nuclear Information System (INIS)

Hootman, H.E.; Trapp, D.J.; Warren, J.H.

1979-01-01

A laboratory-scale incinerator (0.5 kg waste/hr) was built and operated for more than 18 months as part of a program to adapt and confirm technology for incineration of Savannah River Plant solid wastes, which are contaminated with about 0.3 Ci/kg of alpha-emitting transuranium (TRU) nuclides (Slide 1). About 4000 packages of simulated nonradioactive wastes were burned, including HEPA (high-efficiency particulate air) filters, resins, and other types of solid combustible waste from plutonium finishing operations. Throughputs of more than 3 kg/hr for periods up to 4 hours were demonstrated. The incinerator was oerated at temperatures above 750 0 C for more than 7700 hours during a period of 12 months, for an overall availability of 88%. The incinerator was shut down three times during the year: once to replace the primary combustion chamber electrical heater, and twice to replace oxidized electrical connectors to the secondary chamber heaters. Practical experience with this pilot facility provided the design basis for the full-size (5 kg waste/hr) nonradioactive test incinerator, which began operation in March 1979

United States Transuranium Registry. Annual report, October 1, 1983-September 30, 1984

International Nuclear Information System (INIS)

Swint, M.J.; Kathren, R.L.

1985-04-01

This report provides an overview of the objectives, program, facilities and FY-84 accomplishments of the United States Transuranium Registry. Specific activities summarized include postmortem radiochemical analysis of two whole bodies, one with a significant deposition of 241 Am and the other with a deposition of 239 Pu. Results of a followup of early Manhattan District workers as potential registrants, a possible relationship between actinide concentration in bone and ash content, and interlaboratory cooperative activities are briefly discussed along with the initiation of studies of actinides in bone marrow and hair

Underground disposal of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

NONE

1979-08-15

Disposal of low- and intermediate-level radioactive wastes by shallow land burial, emplacement in suitable abandoned mines, or by deep well injection and hydraulic fracturing has been practised in various countries for many years. In recent years considerable efforts have been devoted in most countries that have nuclear power programmes to developing and evaluating appropriate disposal systems for high-level and transuranium-bearing waste, and to studying the potential for establishing repositories in geological formations underlaying their territories. The symposium, organized jointly by the IAEA and OECD's Nuclear Energy Agency in cooperation with the Geological Survey of Finland, provided an authoritative account of the status of underground disposal programmes throughout the world in 1979. It was evidence of the experience that has been gained and the comprehensive investigations that have been performed to study various options for the underground disposal of radioactive waste since the last IAEA/NEA symposium on this topic (Disposal of Radioactive Waste into the Ground) was held in 1967 in Vienna. The 10 sessions covered the following topics: National programme and general studies, Disposal of solid waste at shallow depth and in rock caverns, underground disposal of liquid waste by deep well injection and hydraulic fracturing, Disposal in salt formations, Disposal in crystalline rocks and argillaceous sediments, Thermal aspects of disposal in deep geological formations, Radionuclide migration studies, Safety assessment and regulatory aspects.

Development of an integrated facility for processing transuranium solid wastes at the Savannah River Plant

International Nuclear Information System (INIS)

Boersma, M.D.; Hootman, H.E.; Permar, P.H.

1978-01-01

An integrated facility is being designed for processing solid wastes contaminated with long-lived alpha emitting (TRU) nuclides; this waste has been stored retrievably at the Savannah River Plant since 1965. The stored waste, having a volume of 10 4 m 3 and containing 3x10 5 Ci of transuranics, consists of both mixed combustible trash and failed and obsolete equipment primarily from transuranic production and associated laboratory operations. The facility for processing solid transuranic waste will consist of five processing modules: 1) unpackaging, sorting, and assaying; 2) treatment of combustibles by controlled air incineration; 3) size reduction of noncombustibles by plasma-arc cutting followed by decontamination by electropolishing; 4) fixation of the processed waste in cement; and 5) packaging for shipment to a federal repository. The facility is projected for construction in the mid-1980's. Pilot facilities, sized to manage currently generated wastes, will also demonstrate the key process steps of incineration of combustibles and size reduction/decontamination of noncombustibles; these facilities are projected for 1980-81. Development programs leading to these extensive new facilities are described

Prediction of the health effects of inhaled transuranium elements from experimental animal data

International Nuclear Information System (INIS)

Bair, W.J.; Thomas, J.M.

1976-01-01

Although animal experiments are conducted to obtain data that can be used to predict the consequences of exposure to alpha-emitting elements on human health, scientists have been hesitant to project the results of animal experiments to man. However, since a human data base does not exist for inhaled transuranics, the animal data cannot be overlooked. The paper describes the derivation of linear non-threshold response relationships for lung cancer in rats after inhalation of alpha-emitting transuranium elements. These relationships were used to calculate risk estimates, which were then compared with a value calculated from the incidence of lung cancer in humans who had been exposed to sources of radiation other than the transuranics. Both estimates were compared with the estimated cancer risk associated with the annual whole-body dose limit of 5 rems for occupational exposure. The rat data suggest that the risk from a working lifetime exposure of 15 rem/a to the lungs from transuranium elements may be 5 times the risk incurred with a whole-body exposure of 5 rem/a, while the human data suggest the risk may be less. Since the histological type of plutonium-induced lung cancer that occurs in experimental animals is rare in man, the use of animal data to estimate risks may be conservative. Risk estimates calculated directly from the results of experiments in which animals actually inhaled transuranic particles circumvent such controversial issues as 'hot particles'. (author)

Transuranium processing plant semiannual report of production, status, and plans for period ending December 31, 1977

International Nuclear Information System (INIS)

King, L.J.; Bigelow, J.E.; Collins, E.D.

1978-08-01

Transuranium elements were obtained from 13 irradiated HFIR targets. One batch of high-purity 248 Cm (approximately 75 mg) was separated from 252 Cf. Eighteen shipments were made from TRU during the period. Seven HFIR targets, each containing 8 to 9 g of curium, were fabricated. A new scrubber system was installed in the dissolver off-gas (DOG) stream to remove the bulk of the 131 I and to reduce the amount sorbed in the Hopcalite--charcoal system. During TRU target Campaign 53, the DOG stream was scrubbed with hyperazeotropic nitric acid (the IODOX process). Both the equipment and the process performed satisfactorily. Three neutron sources were fabricated during this report period, bringing the total fabricated to date to 100. Six sources were returned to TRU and are available for reassignment. Special projects included the production of several grams of ultrahigh-purity 243 Am and the development of a method for purification of the ZnBr 2 solution from a shielding window. The values currently being used for transuranium element decay data and for cross-section data in planning irradiation-processing cycles, calculating production forecasts, and assaying products are tabulated

Case histories of EA documents for nuclear waste

International Nuclear Information System (INIS)

Vocke, R.W.

1985-01-01

Nuclear power programs and policies in the United States have been subject to environmental assessment under the National Environmental Policy Act (NEPA) since 1971. NEPA documentation prepared for programmatic policy decision-making within the nuclear fuel cycle and concurrent federal policy are examined as they relate to radioactive waste management in this paper. Key programmatic environmental impact statements that address radioactive waste management include: the Atomic Energy Commission document on management of commercial high-level and transuranium-contaminated radioactive waste, which focussed on development of engineered retrievable surface storage facilities (RSSF); the Nuclear Regulatory Commission (NRC) document on use of recycled plutonium in mixed oxide fuel in light water cooled reactors, which focussed on plutonium recycle and RSSF; the NRC statement on handling of spent light water power reactor fuel, which focussed on spent fuel storage; and the Department of Energy (DOE) statement on management of commercially generated radioactive wastes, which focussed on development of deep geologic repositories. DOE is currently pursuing the deep geologic repository option, with monitored retrievable storage as a secondary option

Physical--chemical studies of transuranium elements. Progress report, April 1, 1976--March 31, 1977

International Nuclear Information System (INIS)

Peterson, J.R.

1977-01-01

Major advances in our continuing program to determine, interpret, and correlate the basic chemical and physical properties of the transuranium elements are summarized for the period April 1, 1976, through March 31, 1977. Implementation of data reduction programs and acquisition of a CRT time-sharing graphics terminal/stand-alone computer have advanced significantly the handling capabilities of single-beam spectral data obtained by our microscope spectrophotometer. EsCl 3 , EsBr 3 , and EsI 3 have been well characterized spectroscopically, and limited X-ray diffraction data have been obtained from EsBr 3 and EsI 3 . The reduction of mixed Es-lanthanide trihalides has produced what might be Es(II). Dimorphism in BkCl 3 , CfCl 3 , and BkBr 3 has been studied spectrophotometrically and the results confirmed by X-ray analysis. Our solution microcalorimeter was improved by reducing the system-generated electrical noise and developing a novel sample container. The operating sensitivity was determined to be within the desired 0.1 percent precision requirement. The necessary hardware was obtained and software development was initiated for the capability to acquire, store, and analyze the heat of solution data automatically. A very sensitive apparatus (SQUID) for the determination of magnetic susceptibility has been constructed and is being evaluated. Our device should greatly facilitate the study of microgram-sized samples of transuranium elements and compounds

Decontamination of alpha-bearing solid wastes and plutonium recovery

International Nuclear Information System (INIS)

Koehly, G.; Madic, C.; Lecomte, M.; Bourges, J.; Saulze, J.L.; Broudic, J.C.

1993-01-01

Nuclear activities in the Radiochemistry building of Fontenay-aux-Roses Nuclear Research Center concern principally the study of fuel reprocessing and the production of transuranium isotopes. During these activities solid wastes are produced. In order to improve the management of these wastes, it has been decided to build new facilities: a group of three glove-boxes named ELISE for the treatment of α active solid waste and a hot-cell, PROLIXE, for the treatment of solid wastes. Leaching processes were developed in order to: decontaminate these wastes and recover actinide elements, particularly the highly valuable plutonium, from the leachates. The processes developed are sufficiently flexible to be able to accommodate solid wastes produced in other facilities. Laboratory studies were conducted to develop the leaching process based on the use of electrogenerated Ag(II) species which is particularly suitable to provoke the dissolution of PuO 2 . Successful exhaustive Pu decontaminations with DF(Pu) higher than 10 4 were achieved for the first time during the treatment of stainless steel PuO 2 cans (future MELOX plant) by electrogenerated Ag (II) in nitric acid medium

United States Transuranium and Uranium Registries. Annual report October 1, 1994 - September 30, 1995

Energy Technology Data Exchange (ETDEWEB)

Kathren, R.L.; Harwick, L.A.; Markel, M.J.

1996-07-01

The United States Transuranium and Uranium Registries (USTUR) comprise a human tissue research program studying the deposition, biokinetics and dosimetry of the actinide elements in humans with the primary goals of providing data fundamental to the verification, refinement, or future development of radiation protection standards for these and other radionuclides, and of determining possible bioeffects on both a macro and subcellular level attributable to exposure to the actinides. This report covers USTUR activities during the year from October 1994 through September 1995.

United States Transuranium and Uranium Registries. Annual report February 1, 2000--January 31, 2001

Energy Technology Data Exchange (ETDEWEB)

Ehrhart, Susan M. (ed.); Filipy, Ronald E. (ed.)

2001-07-01

The United States Transuranium and Uranium Registries (USTUR) comprise a human tissue research program studying the deposition, biokinetics and dosimetry of the actinide elements in humans with the primary goals of providing data fundamental to the verification, refinement, or future development of radiation protection standards for these and other radionuclides, and of determining possible bioeffects on both a macro and subcellular level attributable to exposure to the actinides. This report covers USTUR activities during the year from February 2000 through January 2001.

United States Transuranium and Uranium Registries. Annual report February 1, 2000-January 31, 2001

International Nuclear Information System (INIS)

Ehrhart, Susan M.; Filipy, Ronald E.

2001-01-01

The United States Transuranium and Uranium Registries (USTUR) comprise a human tissue research program studying the deposition, biokinetics and dosimetry of the actinide elements in humans with the primary goals of providing data fundamental to the verification, refinement, or future development of radiation protection standards for these and other radionuclides, and of determining possible bioeffects on both a macro and subcellular level attributable to exposure to the actinides. This report covers USTUR activities during the year from February 2000 through January 2001

Case histories of environmental assessment documents for nuclear waste

International Nuclear Information System (INIS)

Vocke, R.W.

1985-01-01

Nuclear power programs and policies in the United States have been subject to environmental assessment under the National Environmental Policy Act (NEPA) since 1971. NEPA documentation prepared for programmatic policy decision-making fuel cycle and concurrent federal policy are examined as they relate to radioactive waste management in this paper. Key programmatic environmental impact statements that address radioactive waste management include: the Atomic Energy Commission document on management of commercial high level and transuranium-contaminated radioactive waste, which focussed on development of engineered retrievable surface storage facilities (RSSF); the Nuclear Regulatory Commission (NRC) document on use of recycled plutonium in mixed oxide fuel in light water cooled reactors, which focussed on plutonium recycle and RSSF; the NRC statement on handling of spent light water power reactor fuel, which focussed on spent fuel storage; and the Department of Energy (DOE) statement on management of commercially generated radioactive wastes, which focussed on development of deep geologic repositories. DOE is currently pursuing the deep geologic repository option, with monitored retrievable storage as a secondary option

Organic components of nuclear wastes and their potential for altering radionuclide distribution when released to soil

International Nuclear Information System (INIS)

McFadden, K.M.

1980-08-01

Normal waste processing at the Hanford operations requires the use of many organic materials, chiefly in the form of complexing agents and diluents. These organic materials and their chemical and radiolytic degradation products, have potential for complexing fission products and transuranium elements, both in the waste streams and upon infiltration into soil, perhaps influencing future sorption or migration of the nuclides. Particular complexation characteristics of various nuclides which constitute the major fission products, long-lived isotopes, and the most mobile in radioactive wastes are discussed briefly with regards to their anticipated sorption or mobility in soils. Included in the discussion are Am, Sb, Ce, Cs, Co, Cm, Eu, I, Np, Pm, Pu, Ra, Ru, Sr, Tc, U, and Zr. 107 references

United States Transuranium and Uranium Registries. Annuary report, February 1, 2004 - June 30, 2005

Energy Technology Data Exchange (ETDEWEB)

Alldredge, J. Richard [Washington State Univ., Richland, WA (United States); Ehrhart, Susan M. [Washington State Univ., Richland, WA (United States); Eliston, James T. [Washington State Univ., Richland, WA (United States); Emmel, Robert R. [Washington State Univ., Richland, WA (United States); Filipy, Ronald E. [Washington State Univ., Richland, WA (United States); James, Anthony C. [Washington State Univ., Richland, WA (United States); Sasser, Lyle B. [Washington State Univ., Richland, WA (United States); Wood, Tanya G. [Washington State Univ., Richland, WA (United States)

2006-05-31

Three events of significance to the U. S. Transuranium and Uranium Registries (USTUR) occurred during this reporting period: 1. The search for a new Associate Director was successful in that Dr. Anthony C. (Tony) James was appointed to the position, 2. A five-year grant for the operation of the USTUR was approved by the U. S. Department of Energy; the previous grant cycles were for three years, 3. I retired from the USTUR Directorship on July 1, 2005 and Tony James became the new Director.

United States Transuranium Registry annual report October 1, 1977-October 1, 1978 to DOE Office of Health and Environmental Research

International Nuclear Information System (INIS)

Breitenstein, B.D. Jr.; Norwood, W.D.; Newton, C.E. Jr.

1979-01-01

The US Transuranium Registry (USTR) serves as a center for the acquisition and recording of information of the transuranic elements in man and their effects on man. To data 15,045 US transuranium workers have been tabulated, authority for 1048 autopsies obtained, and 93 autopsies granted. Department of Energy contractor and National Regulatory Commission licensee activities at participating sites are discussed. A significant increase in participation from the Savannah River plant has been received during the past year. The low level transuranic measurement laboratory analyzing tissue specimens for the USTR (except Rocky Flats specimens) was transferred from Battelle Pacific Northwest Laboratory to Los Alamos Scientific Laboratory. Dr. Charles W. Mays was appointed Chairman of the USTR Advisory Committee upon the resignation of Dr. James H. Sterner. To improve the quality of autopsy tissue for analysis prosectors were appointed at the Hanford, Rocky Flats, and Los Alamos sites. USTR educational and informational activities were extensive and varied

Transuranium Processing Plant semiannual report of production, status, and plans for period ending December 31, 1976

International Nuclear Information System (INIS)

King, L.J.; Bigelow, J.E.; Collins, E.D.

1977-10-01

During the period July 1, 1976, through December 31, 1976, transuranium elements were obtained from 11 irradiated HFIR targets; products recovered are 0.3 g 243 Am, 16.6 g 244 Cm, 23 g 249 Bk, 211 g 252 Cf, 1.15 mg 253 Es, and 0.4 pg 247 Fm. Two batches of high-purity 248 Cm were purified chemically for shipment, and another batch containing about 62 mg of 248 Cm was separated from 252 Cf. Thirty shipments were made from TRU during the period; recipients and the amounts of nuclides are listed in tabular form. Nine HFIR targets, each containing 8 to 9 g of curium, were fabricated. The sequence of chemical processing steps used to purify the californium product was changed; this change yielded a shorter recovery time for high-purity 253 Es, which enabled a 50% increase in the amount obtained. Eight neutron sources were fabricated during this report period, bringing the total fabricated to date to 92. Three sources that had previously been returned to TRU were reassigned; two others are also available for reassignment. The values currently being used for transuranium element decay data and for cross-section data in planning irradiation-processing cycles, calculating production forecasts, and assaying products are tabulated in the Appendix

Transuranium processing plant semiannual report of production, status, and plans for period ending December 31, 1974

International Nuclear Information System (INIS)

King, L.J.; Bigelow, J.E.; Collins, E.D.

1975-07-01

During the period July 1, 1974, through December 31, 1974, the following amounts of transuranium elements were recovered from 11 irradiated HFIR targets: 1.5 g 243 Am, 45 g 244 Cm, 24 mg 249 Bk, 252 mg 252 Cf, 1.25 mg 253 Es, and 0.5 pg 257 Fm. In addition, 34 mg of high-purity 248 Cm was separated from 252 Cf which had been recovered and purified during earlier periods. Nine HFIR targets, each containing 8 to 9 g of actinides (predominantly curium), were fabricated. Some of the chemical processing steps used for processing HFIR targets were added, deleted, or rearranged in order to reduce processing time and increase product yields. One cubicle equipment rack was replaced and the out-of-cell piping and equipment associated with the remotely operated valves in the TRU cubicles was revised. One neutron source was fabricated. Three sources that had been used previously in various projects and returned to TRU were reloaned. A special project was begun to recover 126 Sn from TRU process solutions. The values currently in use for transuranium element decay data and for cross-section data in planning irradiation-processing cycles, calculating production forecasts, and assaying products are tabulated in the Appendix. (U.S.)

Transuranium elements intake during works connected with the Chernobyl' NPP accident effect elimination

International Nuclear Information System (INIS)

Popov, V.I.; Kukhta, B.A.; Kononykhina, N.N.

1992-01-01

The materials of studies realized in 1989, 1990, 1991 and dealing with internal irradiation control caused by intake of transuranium elements (TUE) for the Chernobyl' NPP personnel and persons engaged in the accident effect elimination are generalized. the leading part of TUE inhalation intake in formation of internal irradiation doses is revealed. Evaluation of TUE inhalation intake hazards is made according to the results of measuring TUE activity in urine samples for the personnel examined (271 persons). The results of surveillance shows the effect of organism internal irradiation connected with TUE intake through respiratory organs. 23 refs.; 1 tab

Experimental studies on behaviour of long-lived radionuclides in relation to deep-ocean disposal of nuclear waste

International Nuclear Information System (INIS)

Aston, S.R.; Fowler, S.W.

1984-01-01

Laboratory experiments have been carried out to investigate the interactions of long-lived radionuclides with sediments from present or potential deep-ocean radioactive waste disposal sites. The studies have been concerned with both geochemical aspects and sediment/animal radioecology. Examples drawn from the comparative behaviour of technetium and three transuranium nuclides (neptunium, plutonium and americium) are presented in relation to their uptake from sea water by deep-ocean sediments, ease of desorption and transfer from contaminated sediments to benthic invertebrates. The results provide information for the prediction of the behaviour of long-lived radionuclides in the deep-sea water/sediment boundary after their release from wastes. (author)

Transuranium and other alpha-emitting nuclides in the marine environment

International Nuclear Information System (INIS)

Pentreath, R.J.

1980-01-01

Marine environment contains naturally occurring alpha-emitting transuranium nuclides which are discharged from nuclear fuel reprocessing plants into the marine environment. Calculation of their potential of both the inhalation pathway and ingestion pathway to man, their residence time in the oceans, their loss to sediments, the chemical state in which they exist in sea water, their oxidation states in sea water, and their biological availability to sea organisms are discussed. The areas where data are lacking are indicated. Studies on the Windscale Site (U.K.) are extensively referred to in the discussion of above-mentioned aspects. It is brought out that the study of the naturally occurring actinides can be useful in the understanding of behaviour of man-made radionuclides in the marine environment, because many of the former are good analogues of the latter. (M.G.B.)

Transuranic contaminated waste container characterization and data base. Revision I

International Nuclear Information System (INIS)

Kniazewycz, B.G.

1980-05-01

The Nuclear Regulatory Commission (NRC) is developing regulations governing the management, handling and disposal of transuranium (TRU) radioisotope contaminated wastes as part of the NRC's overall waste management program. In the development of such regulations, numerous subtasks have been identified which require completion before meaningful regulations can be proposed, their impact evaluated and the regulations implemented. This report was prepared to assist in the development of the technical data base necessary to support rule-making actions dealing with TRU-contaminated wastes. An earlier report presented the waste sources, characteristics and inventory of both Department of Energy (DOE) generated and commercially generated TRU waste. In this report a wide variety of waste sources as well as a large TRU inventory were identified. The purpose of this report is to identify the different packaging systems used and proposed for TRU waste and to document their characteristics. This document then serves as part of the data base necessary to complete preparation and initiate implementation of TRU waste container and packaging standards and criteria suitable for inclusion in the present TRU waste management program. It is the purpose of this report to serve as a working document which will be used as appropriate in the TRU Waste Management Program. This report, and those following, will be compatible not only in format, but also in reference material and direction

United States Transuranium Registry summary report, July 1, 1974 to October 1, 1975 to ERDA Division of Biomedical and Environmental Research

International Nuclear Information System (INIS)

Norwood, W.D.; Newton, C.E. Jr.

1975-11-01

The primary purpose of the Registry is to protect the interests of workers, employers and the public by serving as a national focal point for the acquisition and provision of the latest and most precise information about the effects of the transuranic elements on man. This is being done by establishing the population at risk. To date some 9063 transuranium workers have been so identified. On a continuing basis, the best current estimates of the amount and location of any internal deposition of any of the transuranium elements in employees are being accumulated. These determinations have been improved by reconciliation with actual burdens found in various organs at autopsy or by alternate methods. Such employees are followed clinically and by epidemiological methods to determine whether there may be any adverse effects on such desposits on health or longevity. Registry statistics are given for the following sites: Hanford, Rocky Flats, Los Alamos, Savannah River, Mount, and Oak Ridge. The seven appendces contain information related to the Registry activities

Use of triton-WR-1339 (TWR) for a quantitative determination of the lysosomal binding of transuranium elements in the rat liver

International Nuclear Information System (INIS)

Gruner, K.R.

1978-01-01

The subcellular localisation of 239 Pu and 241 Am in the rat liver was investigated. A biochemical separation method with modified lysosomes was applied for the first time; the method permitted unique statements on the mitochondrial or lysosomal association of transuranium elements. Lysosomal association of 239 Pu and 241 Am between days 4 and 6 after radionuclide injection was most easily detected by follow-up treatment with TWR, i.e. the nonionic detergent was applied 2 days after injection of the radionuclide and 4 days before the onset of the analytical procedure. Extracellular transuranium depots could not be proved to exist neither by comparing absolute retention figures in perfused and nonperfused livers nor by subcellular distribution studies. A quantitative relation between the DTPA mobilisation efficiency in the total liver and the subcellular distribution patterns obtained for americium could be estimated for the period between the first and 18th day after radionuclide injection. It suggests on intracellular effect of DTPA. (orig./MG) [de

Waste treatment at the Radiochemical Engineering Development Center

International Nuclear Information System (INIS)

Brunson, R.R.; Bond, W.D.; Chattin, F.R.; Collins, R.T.; Sullivan, G.R.; Wiles, R.H.

1997-01-01

At the Radiochemical Engineering Development Center (REDC) irradiated targets are processed for the recovery of valuable radioisotopes, principally transuranium nuclides. A system was recently installed for treating the various liquid alkaline waste streams for removal of excess radioactive contaminants at the REDC. Radionuclides that are removed will be stored as solids and thus the future discharge of radionuclides to liquid low level waste tank storage will be greatly reduced. The treatment system is of modular design and is installed in a hot cell (Cubicle 7) in Building 7920 at the REDC where preliminary testing is in progress. The module incorporates the following: (1) a resorcinol-formaldehyde resin column for Cs removal, (2) a cross flow filtration unit for removal of rare earths and actinides as hydroxide, and (3) a waste solidification unit. Process flowsheets for operation of the module, key features of the module design, and its computer-assisted control system are presented. Good operability of the cross flow filter system is mandatory to the successful treatment of REDC wastes. Results of tests to date on the operation of the filter in its slurry collection mode and its slurry washing mode are presented. These tests include the effects of entrained organic solvent in the waste stream feed to the filter

Annual report of the United States transuranium and uranium registries, October 1, 1988--September 30, 1989

International Nuclear Information System (INIS)

Kathren, R.L.; Swint, M.J.; Dietert, S.E.

1990-04-01

This report summarizes the primary scientific activities of the United States Transuranium and Uranium Registries for the period October 1, 1988 through September 30, 1989. The Registries are parallel human tissue research programs devoted to the study of the actinide elements in man. The emphasis of the Transuranium Registry was directed toward evaluation of six whole body donations. In the five cases whose exposure was through inhalation, approximately half of the total body content of Pu-239 + 240 and a third of the Am-241 was found in the respiratory tract, suggesting that these nuclides are more avidly retained than predicted by the current model of the International Commission on Radiological Protection. A significant fraction of these nuclides is found in soft tissues other than liver, and an uptake fraction of 0.2 is proposed for muscle, with a residence half-time of 10 years. Studies of these and routine autopsy cases indicate that more than 90% of the total respiratory tract plutonium or americium is in the lungs, with the remainder in the lymph nodes, and that a greater fraction is found in the lungs of smokers relative to the lymph nodes. Primary activities of the Uranium Registry centered around the acquisition of a whole body donation from a woman who had received an injection of colloidal thorium dioxide some 38 years prior to death

Developing an institutional strategy for transporting defense transuranic waste materials

International Nuclear Information System (INIS)

Guerrero, J.V.; Kresny, H.S.

1986-01-01

In late 1988, the US Department of Energy (DOE) expects to begin emplacing transuranic waste materials in the Waste Isolation Pilot Plant (WIPP), an R and D facility to demonstrate the safe disposal of radioactive wastes resulting from defense program activities. Transuranic wastes are production-related materials, e.g., clothes, rags, tools, and similar items. These materials are contaminated with alpha-emitting transuranium radionuclides with half-lives of > 20 yr and concentrations > 100 nCi/g. Much of the institutional groundwork has been done with local communities and the State of New Mexico on the siting and construction of the facility. A key to the success of the emplacement demonstration, however, will be a qualified transportation system together with institutional acceptance of the proposed shipments. The DOE's Defense Transuranic Waste Program, and its contractors, has lead responsibility for achieving this goal. The Joint Integration Office (JIO) of the DOE, located in Albuquerque, New Mexico, is taking the lead in implementing an integrated strategy for assessing nationwide institutional concerns over transportation of defense transuranic wastes and in developing ways to resolve or mitigate these concerns. Parallel prototype programs are under way to introduce both the new packaging systems and the institutional strategy to interested publics and organizations

Criteria for designing an interim waste storage facility

International Nuclear Information System (INIS)

Vicente, Roberto

2011-01-01

The long-lived radioactive wastes with activity above clearance levels generated by radioisotope users in Brazil are collected into centralized waste storage facilities under overview of the National Commission on Nuclear Energy (CNEN). One of these centers is the Radioactive Waste Management Department (GRR) at the Nuclear and Energy Research Institute (IPEN), in Sao Paulo, which since 1978 also manages the wastes generated by IPEN itself. Present inventory of stored wastes includes about 160 tons of treated wastes, distributed in 1290 steel, 200-liters drums, and 52 steel, 1.6 m 3 -boxes, with an estimated total activity of 0.8 TBq. Radionuclides present in these wastes are fission and activation products, transuranium elements, and isotopes from the uranium and thorium decay series. The capacity and quality of the storage rooms at GRR evolved along the last decades to meet the requirements set forth by the Brazilian regulatory authorities.From a mere outdoor concrete platform over which drums were simply stacked and covered with canvas to the present day building, a great progress was made in the storage method. In this paper we present the results of a study in the criteria that were meant to guide the design of the storage building, many of which were eventually adopted in the final concept, and are now built-in features of the facility. We also present some landmarks in the GRR's activities related to waste management in general and waste storage in particular, until the treated wastes of IPEN found their way into the recently licensed new storage facility. (author)

Disposal of Hanford site tank wastes

International Nuclear Information System (INIS)

Kupfer, M.J.

1993-09-01

Between 1943 and 1986, 149 single-shell tanks (SSTs) and 28 double-shell tanks (DSTs) were built and used to store radioactive wastes generated during reprocessing of irradiated uranium metal fuel elements at the U.S. Department of Energy (DOE) Hanford Site in Southeastern Washington state. The 149 SSTs, located in 12 separate areas (tank farms) in the 200 East and 200 West areas, currently contain about 1.4 x 10 5 m 3 of solid and liquid wastes. Wastes in the SSTs contain about 5.7 x 10 18 Bq (170 MCi) of various radionuclides including 90 Sr, 99 Tc, 137 Cs, and transuranium (TRU) elements. The 28 DSTs also located in the 200 East and West areas contain about 9 x 10 4 m 3 of liquid (mainly) and solid wastes; approximately 4 x 10 18 Bq (90 MCi) of radionuclides are stored in the DSTs. Important characteristics and features of the various types of SST and DST wastes are described in this paper. However, the principal focus of this paper is on the evolving strategy for final disposal of both the SST and DST wastes. Also provided is a chronology which lists key events and dates in the development of strategies for disposal of Hanford Site tank wastes. One of these strategies involves pretreatment of retrieved tank wastes to separate them into a small volume of high-level radioactive waste requiring, after vitrification, disposal in a deep geologic repository and a large volume of low-level radioactive waste which can be safely disposed of in near-surface facilities at the Hanford Site. The last section of this paper lists and describes some of the pretreatment procedures and processes being considered for removal of important radionuclides from retrieved tank wastes

Management of transuranic wastes throughout the world

International Nuclear Information System (INIS)

Lakey, L.T.; Christensen, H.; De Jonghe, P.; Frejaville, G.; Lavie, J.M.; Thackrah, D.G.

1983-01-01

Transuranic (TRU) wastes are those radioactive wastes, except spent fuel and high-level wastes, that are contaminated with sufficient long-lived, alpha-emitting nuclides that the decay to innocuous levels in engineered storage structures or shallow-land burial sites cannot be used as a disposal method. This class of waste is produced principally during spent fuel reprocessing, recycle fuel fabrication, and weapons material production. At least ten countries are involved in operations producing this class of waste, which represents a small fraction of the alpha-emitting nuclides in the world's inventory and of the total volume of radioactive wastes produced in nuclear activities. No consensus has been reached on a numerical definition; definitions in use vary from >0.03 to >1000 nCi transuranium radionuclides per gram of waste (TRU/g). The definitions are presently used to separate wastes going to sea dumping or shallow-land burial from those requiring greater isolation. All countries emphasize plutonium recovery and volume reduction in their plans for treating TRU wastes. Incineration is the most prevalent treatment in use. When fixation is used, cement and bitumen are the preferred fixation media. All high-concentration TRU wastes are now being placed in interim storage. No TRU wastes are presently being disposed except the low-concentration wastes being dumped at sea by Belgium and the United Kingdom and those being injected into geologic strata by the United States (Oak Ridge National Laboratory) and the USSR. All countries prefer and are planning to use deep geologic repositories for final disposal of TRU wastes. According to present schedules, the Waste Isolation Pilot Plant (WIPP) facility in the United States, with a scheduled startup date of 1989, will be the first operating repository since the closure of the Federal Republic of Germany's Asse Salt Mine in 1977

Development of a partitioning method for the management of high-level liquid waste

International Nuclear Information System (INIS)

Kubota, M.; Dojiri, S.; Yamaguchi, I.; Morita, Y.; Yamagishi, I.; Kobayashi, T.; Tani, S.

1989-01-01

Fundamental studies especially focused on the separation of neptunium and technetium have been carried out to construct the advanced partitioning process of fractioning elements in a high-level liquid waste into four groups: transuranium elements, technetium-noble metals, strontium-cesium, and other elements. For the separation of neptunium by solvent extraction, DIDPA proved excellent for extracting Np(V), and its extraction rate was accelerated by hydrogen peroxide. Np(V) was found to be also separated quantitatively as precipitate with oxalic acid. For the separation of technetium, the denitration with formic acid was effective in precipitating it along with noble metals, and the adsorption with activated carbon was also effective for quantitative separation. Through these fundamental studies, the advanced partitioning process is presented as the candidate to be examined with an actual high-level liquid waste

Method of reprocessing spent nuclear fuels

International Nuclear Information System (INIS)

Kamiyama, Hiroaki; Inoue, Tadashi; Miyashiro, Hajime.

1987-01-01

Purpose: To facilitate the storage management for the wastes resulting from reprocessing by chemically separating transuranium elements such as actionoid elements together with uranium and plutonium. Method: Spent fuels from a nuclear reactor are separated into two groups, that is, a mixture of uranium, plutonium and transuranium elements and cesium, strontium and other nuclear fission products. Virgin uranium is mixed to adjust the mixture of uranium, plutonium and transuranium elements in the first group, which is used as the fuels for the nuclear reactor. After separating to recover useful metals such as cesium and strontium are separated from short half-decay nuclear fission products of the second group, other nuclear fission products are stored and managed. This enables to shorten the storage period and safety storage and management for the wastes. (Takahashi, M.)

United States Transuranium Registry annual report October 1, 1975-October 1, 1976 to ERDA Division of Biomedical and Environmental Research

International Nuclear Information System (INIS)

Breitenstein, B.D. Jr.; Norwood, W.D.; Newton, C.E. Jr.

1976-12-01

The US Transuranium Registry is a center for collecting precise information about the occupational effects of transuranic elements on man. To date 13,943 past and present transuranium workers have been tabulated. Health, mortality, causes of death and transuranic organ depositions are being studied. Bryce D. Breitenstein, Jr., M.D. was named Director of the Registry in July 1976. The Los Alamos Scientific Laboratory is directing the epidemiological portion of a plutonium worker health study with George Voelz, M.D. and Louis Hempelmann, M.D. serving as principal investigators. The USTR is affiliated with this study. USTR statistical data shows progressive acquisition of information for 1975 and 1976. ERDA contractor and NRC licensee activities at participating sited are discussed. Preparation of the input format to record and store USTR data has been completed and is ready for trial operation. USTR educational and informational activities were extensive and varied. Many queries arose from the use of published Registry autopsy data by Ralph Nader's associate Dr. S. Wolfe. There was continued cooperation with representatives of the British Atomic Energy Authority in their efforts to develop a plutonium registry

United States transuranium and uranium registries - 25 years of growth, research, and service. Annual report, April 1992--September 1993

International Nuclear Information System (INIS)

Kathren, R.L.; Harwick, L.A.; Toohey, R.E.; Russell, J.J.; Filipy, R.E.; Dietert, S.E.; Hunacek, M.M.; Hall, C.A.

1994-01-01

The Registries originated in 1968 as the National Plutonium Registry with the name changed to the United States Transuranium Registry the following year to reflect a broader concern with the heavier actinides as well. Initially, the scientific effort of the USTR was directed towards study of the distribution and dose of plutonium and americium in occupationally exposed persons, and to assessment of the effects of exposure to the transuranium elements on health. This latter role was reassessed during the 1970's when it was recognized that the biased cohort of the USTR was inappropriate for epidemiologic analysis. In 1978, the administratively separate but parallel United States Uranium Registry was created to carry out similar work among persons exposed to uranium and its decay products. A seven member scientific advisory committee provided guidance and scientific oversight. In 1992, the two Registries were administratively combined and transferred from the purview of a Department of Energy contractor to Washington State University under the provisions of a grant. Scientific results for the first twenty-five years of the Registries are summarized, including the 1985 publication of the analysis of the first whole body donor. Current scientific work in progress is summarized along with administrative activities for the period

United States transuranium and uranium registries - 25 years of growth, research, and service. Annual report, April 1992--September 1993

Energy Technology Data Exchange (ETDEWEB)

Kathren, R.L.; Harwick, L.A.; Toohey, R.E.; Russell, J.J.; Filipy, R.E.; Dietert, S.E.; Hunacek, M.M.; Hall, C.A.

1994-10-01

The Registries originated in 1968 as the National Plutonium Registry with the name changed to the United States Transuranium Registry the following year to reflect a broader concern with the heavier actinides as well. Initially, the scientific effort of the USTR was directed towards study of the distribution and dose of plutonium and americium in occupationally exposed persons, and to assessment of the effects of exposure to the transuranium elements on health. This latter role was reassessed during the 1970`s when it was recognized that the biased cohort of the USTR was inappropriate for epidemiologic analysis. In 1978, the administratively separate but parallel United States Uranium Registry was created to carry out similar work among persons exposed to uranium and its decay products. A seven member scientific advisory committee provided guidance and scientific oversight. In 1992, the two Registries were administratively combined and transferred from the purview of a Department of Energy contractor to Washington State University under the provisions of a grant. Scientific results for the first twenty-five years of the Registries are summarized, including the 1985 publication of the analysis of the first whole body donor. Current scientific work in progress is summarized along with administrative activities for the period.

Alkaline chemistry of transuranium elements and technetium and the treatment of alkaline radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Delegard, C.H. [Westinghouse Hanford Co., Richland, WA (United States); Peretrukhin, V.F.; Shilov, V.P.; Pikaev, A.K. [Russian Academy of Sciences (Russian Federation). Inst. of Physical Chemistry

1995-05-01

Goal of this survey is to generalize the known data on fundamental physical-chemical properties of TRUs and Tc, methods for their isolation, and to provide recommendations that will be useful for partitioning them from alkaline high-level wastes.

Alkaline chemistry of transuranium elements and technetium and the treatment of alkaline radioactive wastes

International Nuclear Information System (INIS)

Delegard, C.H.; Peretrukhin, V.F.; Shilov, V.P.; Pikaev, A.K.

1995-05-01

Goal of this survey is to generalize the known data on fundamental physical-chemical properties of TRUs and Tc, methods for their isolation, and to provide recommendations that will be useful for partitioning them from alkaline high-level wastes

Physical--chemical studies of transuranium elements. Progress report, April 1, 1977--March 31, 1978

International Nuclear Information System (INIS)

Peterson, J.R.

1978-01-01

Major advances in our continuing program to determine, interpret, and correlate the basic chemical and physical properties of the transuranium elements are summarized for the period April 1, 1977, through March 31, 1978. CfCl 2 , EsCl 2 , EsBr 2 , and EsI 2 were synthesized and characterized spectrophotometrically, as were several mixed-valence lanthanide-actinide halides (e.g., GdCf 4 Cl 11 ) and CmF 4 , CfF 4 , and EsF 3 . All samples not containing einsteinium were also examined by X rays. Studies of the chemical consequences of the radioactive decay series 253 Es alpha decaying to 249 Bk beta decaying to 249 Cf have continued and expanded. Elemental Cm-248 has been prepared on the one-half milligram scale and used to synthesize CmP and CmSb. Single crystals of AmTe 2 and AmSe 2 have been grown from a Te melt and by iodine transport, respectively. Our SQUID magnetometer was tested successfully in a preliminary configuration, and the expected sensitivity of the device was confirmed. A new design for the flux sensing coils was incorporated prior to an apparatus calibration experiment with lead. A porous vitreous carbon material was found to make a useful optically transparent electrode for simultaneous electrochemical and absorption spectroscopic investigations. Cyclic voltammograms of UO 2 2+ were obtained prior to a spectroelectrochemical study of the radiation of UO 2 2+ . The major obstacle in our solution microcalorimetry program was overcome by the realization of a leak-free sample container. Calorimeter performance now warrants experiments with transuranium element samples. The electrochemical reductions of Cf(III) and Es(III) have been studied by polarography and/or cyclic voltammetry. The results suggest that both are reduced to the divalent state before being reduced to the amalgam

Dismantling and waste management: CEA's strategy and research programs

International Nuclear Information System (INIS)

Behar, C.

2012-01-01

There are 3 main dismantling operations in CEA. First, the dismantling of the UP1 facility in the Marcoule site. UP1 was a reprocessing plant of nuclear fuels that operated from 1958 to 1997 and is now the biggest dismantling operation in the world. Its dismantling operation follows a 6-step scheme that will end in 2050. Secondly, the Passage project on the Grenoble site that concerns the dismantling of 3 research reactors (Siloette, Melusine and Siloe), of a laboratory dedicated to the analysis of active materials (Lama) and of a station for the processing of waste (Sted). Thirdly the Aladin project that concerns the installations of the Fontenay-aux-Roses site. The dismantling operations are complex because all the first research programs on high activity chemistry and on transuranium elements were performed in Fontenay-aux-Roses facilities and because ancient activities have to leave a clean place to be replaced by new ones. The radioactive waste produced by CEA enter the flow of waste that is normally processed and managed by ANDRA. Only high-activities waste have not yet a definitive solution, they are stored in waiting the opening of a geological repository. CEA leads research programs on the separation and transmutation of minor actinides and on the long-term behaviour of waste packages put in deep geological layers. (A.C.)

US Transuranium Registry report on the 241Am content of a whole body. Part I: Introduction and history of the case

International Nuclear Information System (INIS)

Breitenstein, B.D.; Newton, C.E.; Norris, H.T.

1985-01-01

The first whole-body analysis of the U.S. Transuranium Registry was initiated in 1979. The donor was a 49-yr-old male Caucasian radiochemist who died of metastatic malignant melanoma. The donor had a recognized, longstanding 241 Am internal deposition first identified in a routine urine sample in 1958. A summary of the clinical and postmortem findings is presented with the chronologic sequence of the procedures

Proceedings of public hearings: plutonium and the other transuranium elements, Washington, D.C., December 10--11, 1974. Volume 1

International Nuclear Information System (INIS)

1974-01-01

The Environmental Protection Agency embarked on a program to evaluate the environmental impact of the transuranium elements and to consider whether further guidelines or standards are needed to assure adequate protection of the general ambient environment and of the public health from potential contamination of the environment by radionuclides of these elements. Public hearings were held in Washington, D. C., and Denver, Colorado, to gather information regarding the public and social implications of plutonium utilization; the factors involved in the balancing of costs vs benefits; dosimetry, health, and environmental effects; environmental levels and pathways; applications using plutonium; and control and cleanup technology. The proceedings of the hearing in Washington, D. C., Dec. 10-11, 1974, are presented. Data are included on current and potential sources of transuranium elements in the environment; animal studies on the tissue distribution of 233 U, 237 Np, 238 Pu, 239 Pu, 241 Am, 244 Cm, 249 Bk, 252 Cf, and 253 Es and pathological effects of body burdens of these radionuclides; and data on the health status of personnel known to have body burdens of 238 Pu or 239 Pu acquired during acute or chronic exposure, many of them over 30 years previously. It is pointed out that the lack of demonstrable biological effects of Pu in man provides presumptive evidence that the radiation protection standards in effect are adequate. (U.S.)

Transuranium element behavior in the environment: What speciation studies can tell us

International Nuclear Information System (INIS)

Cleveland, J.M.

1989-01-01

Some of the transuranium elements - especially plutonium - can exist in the environment in several different oxidation states which differ chemically from one another as much as if they were different elements. Hence an understanding of the environmental chemistry of these elements requires knowledge of their oxidation-state distribution, or speciation, under a variety of realistic conditions. Such studies are in their infancy, but already several chemical speciation methods have yielded results indicating the uniqueness of transuranic environment chemistry; for example, dioxoplutonium(V), which is unstable in the acid solutions employed in laboratory and processing plant, is often the most prevalent plutonium oxidation state in natural waters. More sensitive and less invasive physical speciation methods under development will hopefully permit the extension of these studies to a wider variety of environmental conditions and to determinations of sorbed species necessary for an understanding of sorption processes

United States Transuranium Registry summary report to June 30, 1974 to USAEC Division of Biomedical and Environmental Research

International Nuclear Information System (INIS)

Norwood, W.D.; Newton, C.E. Jr.

1974-06-01

This report gives some of the highlights of the US Transuranium Registry since its inception in late 1968 together with more detailed information concerning the activities for the year ending April 30, 1974. Articles are referred to which describe autopsy studies to determine plutonium body content, performed since 1949 for the purpose of evaluating plant health safety programs. The purpose of the Registry is described and its administrative direction is discussed. The Registry is a data collecting agency whose success depends upon how well the data is collected by the cooperating companies is described

Process for separately recovering uranium, transuranium elements, and fission products of uranium from atomic reactor fuel

International Nuclear Information System (INIS)

Balal, A.L.; Metscher, K.; Muehlig, B.; Reichmuth, C.; Schwarz, B.; Zimen, K.E.

1976-01-01

Spent reactor fuel elements are dissolved in dilute nitric acid. After addition of acetic acid as a complexing agent, the nitric acid is partly decomposed and the mixture subjected to electrolysis while a carrier liquid, which may be dilute acetic acid or a dilute mixture of acetic acid and nitric acid is caused to flow in the electric field between the electrodes either against the direction of ion migration or transversely thereto. The ions of uranium, plutonium, and other transuranium elements, and of fission products accumulate in discrete portions of the electrolyte and are separately withdrawn as at least three fractions after one or more stages of electrolysis

Present status of partitioning developments

International Nuclear Information System (INIS)

Nakamura, Haruto; Kubota, Masumitsu; Tachimori, Shoichi

1978-09-01

Evolution and development of the concept of partitioning of high-level liquid wastes (HLLW) in nuclear fuel reprocessing are reviewed historically from the early phase of separating useful radioisotopes from HLLW to the recent phase of eliminating hazardous nuclides such as transuranium elements for safe waste disposal. Since the criteria in determining the nuclides for elimination and the respective decontamination factors are important in the strategy of partitioning, current views on the criteria are summarized. As elimination of the transuranium is most significant in the partitioning, various methods available of separating them from fission products are evaluated. (auth.)

United States Transuranium and Uranium Registries: Researching radiation protection. USTUR annual report for February 1, 1999 through January 31, 2000

International Nuclear Information System (INIS)

Ehrhart, Susan M.; Filipy, Ronald E.

2000-01-01

The United States Transuranium and Uranium Registries (USTUR) comprise a human tissue research program studying the deposition, biokinetics and dosimetry of the actinide elements in humans with the primary goals of providing data fundamental to the verification, refinement, or future development of radiation protection standards for these and other radionuclides, and of determining possible bioeffects on both a macro and subcellular level attributable to exposure to the actinides. This report covers USTUR activities during the year from February 1999 through January 2000

United States Transuranium and Uranium Registries: Researching radiation protection. USTUR annual report for February 1, 1999 through January 31, 2000

Energy Technology Data Exchange (ETDEWEB)

Ehrhart, Susan M. (ed.); Filipy, Ronald E. (ed.)

2000-07-01

The United States Transuranium and Uranium Registries (USTUR) comprise a human tissue research program studying the deposition, biokinetics and dosimetry of the actinide elements in humans with the primary goals of providing data fundamental to the verification, refinement, or future development of radiation protection standards for these and other radionuclides, and of determining possible bioeffects on both a macro and subcellular level attributable to exposure to the actinides. This report covers USTUR activities during the year from February 1999 through January 2000.

Application od scaling technique for estimation of radionuclide inventory in radioactive waste

International Nuclear Information System (INIS)

Hertelendi, E.; Szuecs, Z.; Gulyas, J.; Svingor, E.; Csongor, J.; Ormai, P.; Fritz, A.; Solymosi, J.; Gresits, I.; Vajda, N.; Molnar, Zs.

1996-01-01

Safety studies related to the disposal of low- and intermediate waste indicate that the long term risk is determined by the presence of long-lived nuclides such as 14 C, 59 Ni, 63 Ni, 99 Tc, 129 I and the transuranium elements. As most of these nuclides are difficult to measure, the correlation between these critical nuclides and some other easily measurable key nuclides such as 60 Co and 137 Cs has been investigated for typical waste streams of Paks Nuclear Power Plant (Hungary) and scaling factors have been proposed. An automated gamma-scanning monitor has been purchased and calibrated to determine the gamma-emitting radionuclides. Radiochemical methods have been developed to determine significant difficult-to-measure radionuclides. The radionuclides of interest have been 3 H, 14 C, 90 Sr, 55 Fe, 59 Ni, 99 Tc, 129 I and TRUs. The measurements taken so far have revealed brand new information and data on radiological composition of waste of WWER-type reactors. The reliability of the radioanalytical methods was checked by an international intercomparison test. For all radionuclides the Hungarian results were in the average range of the total data set. (author)

Separation of transuranium elements from high-level waste by extraction with diisodecyl phosphoric acid

International Nuclear Information System (INIS)

Morita, Y.; Kubota, M.; Tani, S.

1991-01-01

Separation of transuranic elements (TRU) by extraction with diisodecyl phosphoric acid (DIDPA) has been studied to develop a partitioning process for high-level waste (HLW). In the present study, experiments of counter-current continuous extraction and back-extraction using a miniature mixer-settler were carried out to find the optimum process condition for the separation of Np initially in the pentavalent state and to examine the extraction behaviors of fission and corrosion products. (J.P.N.)

Old waste products - new requirements. Preparations for the later repository

International Nuclear Information System (INIS)

Graf, A.; Merx, H.

2003-01-01

For more than 30 years now, the Hauptabteilung Dekontaminationsbetriebe (HDB, Central Decontamination Department) of the Forschungszentrum Karlsruhe has been engaged in the management of radioactive wastes produced by the operation and decommissioning of research reactors and institutes of the Research Center, the Karlsruhe reprocessing plant, the European Institute for Transuranium Elements, and the Baden-Wuerttemberg state collection center. For this purpose, the wastes delivered to HDB have been conditioned at various facilities according to the requirements specified. These conditioning requirements, however, have changed in the course of time. In the past, only minimum declaration and conditioning requirements had to be fulfilled for the ASSE repository storage facility. Since 1994, the KONRAD repository storage conditions have been adopted. They comprise a variety of quality criteria. Judging from today, duration of interim storage until transfer to a repository storage facility will take another 30 years at least. In addition to the documentary qualification of the waste products, it is therefore required to take measures to ensure long-term safety of both the waste packages and their storage. This is why the HDB, in agreement with the supervisory authority, i.e. the Federal Radiation Protection Authority, and its experts, has decided to put the waste products into KONRAD containers in certified compliance with the repository storage conditions and to backfill these containers with concrete in accordance with approved procedures. Thus, waste packages suited for repository storage will be produced and corrosion processes and the possible release of radioactivity will be prevented. (orig.)

Old waste products - new requirements. Preparations for the later repository

Energy Technology Data Exchange (ETDEWEB)

Graf, A.; Merx, H. [Forschungszentrum Karlsruhe GmbH Technik und Umwelt (Germany). Hauptabteilung Dekontaminationsbetriebe

2003-07-01

For more than 30 years now, the Hauptabteilung Dekontaminationsbetriebe (HDB, Central Decontamination Department) of the Forschungszentrum Karlsruhe has been engaged in the management of radioactive wastes produced by the operation and decommissioning of research reactors and institutes of the Research Center, the Karlsruhe reprocessing plant, the European Institute for Transuranium Elements, and the Baden-Wuerttemberg state collection center. For this purpose, the wastes delivered to HDB have been conditioned at various facilities according to the requirements specified. These conditioning requirements, however, have changed in the course of time. In the past, only minimum declaration and conditioning requirements had to be fulfilled for the ASSE repository storage facility. Since 1994, the KONRAD repository storage conditions have been adopted. They comprise a variety of quality criteria. Judging from today, duration of interim storage until transfer to a repository storage facility will take another 30 years at least. In addition to the documentary qualification of the waste products, it is therefore required to take measures to ensure long-term safety of both the waste packages and their storage. This is why the HDB, in agreement with the supervisory authority, i.e. the Federal Radiation Protection Authority, and its experts, has decided to put the waste products into KONRAD containers in certified compliance with the repository storage conditions and to backfill these containers with concrete in accordance with approved procedures. Thus, waste packages suited for repository storage will be produced and corrosion processes and the possible release of radioactivity will be prevented. (orig.)

Scenarios of radiological impacts in the long-term safety analysis of radioactive waste disposal at the Vector Site located in the Chernobyl exclusion zone

Energy Technology Data Exchange (ETDEWEB)

Rybalka, N.; Mykolaichuk, O. [State Nuclear Regulatory Inspectorate of Ukraine, Kyiv (Ukraine); Alekseeva, Z.; Kondratiev, S.; Nikolaev, E. [State Scientific and Technical Center for Nuclear and Radiation Safety, Kyiv (Ukraine)

2013-07-01

In Ukraine, at the Vector site in the Chernobyl exclusion zone, it is planned to dispose of large amounts of radioactive wastes, including those of Chernobyl origin, containing transuranium elements. The paper analyzes the main possible scenarios of radiological impacts of the Vector site for a long-term period after expiration of its active administrative control taking into account location of the Vector site in the exclusion zone. In the paper, assessment of total activities that can be disposed of on site is demonstrated, based on non-exceeding of admissible radiological impacts. (orig.)

Fate of cesium, strontium, iodine and some transuranium elements in farm animals

International Nuclear Information System (INIS)

Mueller-Brunecker, G.

1982-11-01

Domestic animals may take up Cs, I, Sr and the most important transuranium elements by contaminated food, inhalation and cutaneous resorption. The resorption takes place (with differing percentage distribution) via gastrointestinal tract, lungs, skin and with wounds via injured skin areas. With chronical exposure and after resorption of radionuclides a distribution balance develops in the blood; with a single incorporation the activity concentration in the blood one increases and decreases again. According to the affinity of the radionuclide its major part is transported to one particular organ or tissue system, where depending on the degree of specific activity the most different damages may be provoked. Considerable amounts of the radionuclide quantities are discharged with urine, feces or milk. The amount discharged into the milk is of particular radioecologic interest. The portion of the radionuclides, which is discharged into the muscles and the milk of animals for slaughter is indicated by transmission factors, which have to be subjected to revision. The transmission factors given in literature are classified according to the animal species and discussed in the corresponding chapters. (orig./MG) [de

Surrogate formulations for thermal treatment of low-level mixed waste

International Nuclear Information System (INIS)

Chiang, J.M.; Bostick, W.D.; Hoffman, D.P.; Hermes, W.H.; Gibson, L.V. Jr.; Richmond, A.A.

1994-01-01

The plasma hearth process (PHP) presented in this report has been tested at a facility at Ukiah, California, in a cooperative effort between the Department of Energy (DOE), Science Applications International Corporation, Inc., and ReTech, Inc. The electrically heated plasma gas is used to destroy organic materials and bind radionuclides and Resource Conservation and Recovery Act (RCRA) metals in the glassy slag. Proof-of-principle tests were conducted successfully using nonhazardous and non-radioactive materials placed in 30-gal steel drums. On-line analyses of the gaseous effluents indicated complete combustion; emissions of CO, NO x , and particulates were low. The process also produced highly stable solid waste forms. The experiments for the next phase have been planned employing surrogates for the hazardous and radioactive components of the simulated waste streams. Natural cerium oxide is selected to simulate the behavior of radioactive actinide and transuranium elements, while natural cesium chloride is simulated for the study of relatively volatile radioactive fission products. For RCRA organics, naphthalene and 1,2-dichlorobenzene are semivolatile compounds selected to represent significant challenges to thermal destruction, whereas chlorobenzene is selected for the study of relatively volatile organics. Salts of chromium, nickel, lead, and cadmium are chosen to represent the twelve regulated toxic metals for emission and partitioning studies. The simulated waste packages presented in the text do not necessarily represent an individual waste stream within the DOE complex; rather, they were formulated to represent the most probable components in generic waste stream categories

Effect of γ-ray emission on transuranium element production cross sections in heavy ion reactions

International Nuclear Information System (INIS)

Il'inov, A.S.; Oganesyan, Yu.Ts.; Cherepanov, E.A.

1980-01-01

The effect of competition of the γ ray emission with neutron evaporation and of compound nuclei fission induced by heavy ion reactions on the production cross sections for transuranium elements is considered. It is shown that taking account of γ ray emission leads to the broadening of the excitation functions of the (HI, xny) reactions such as 18 O+ 238 U, 40 Ar+ 206 Pb, 40 Ar+ 207 Pb and 40 Ar+ 208 Pb reactions and to the displacement of their maximum toward the higher energies as well as to an increase of the absolute cross sections which is especially strong close to the fusion barrier. Cross sections for the radiative capture of heavy ions by a heavy target nucleus in 40 Ar+ 206 Pb, 40 Ar+ 208 Pb, 48 Ca+ 204 Pb and 48 Ca+ 208 Pb reactions are estimated

Transuranium Processing Plant semiannual report of production, status, and plans for period ending June 30, 1975

International Nuclear Information System (INIS)

King, L.J.; Bigelow, J.E.; Collins, E.D.

1976-03-01

During the period January 1, 1975, through June 30, 1975, the following amounts of transuranium elements were recovered from 22 irradiated HFIR targets: 2g 243 Am, 59 g 244 Cm, 51 mg 249 Bk, 465 mg 252 Cf, 2.5 mg 253 Es, and 1.4 pg 257 Fm. In addition, 45 mg of high-purity 248 Cm was operated from 252 Cf which had been recovered and purified during earlier periods, and 56 mg of a lower-quality 248 Cm was separated from californium purification rework solutions. Five HFIR targets, each containing approximately 9 g of actinides (predominantly curium), were fabricated. A new long-term projection showed that 252 Cf production in the TRU-HFIR complex could increase to as much as 2.5 g/year. During the next 18 months, we expect to recover totals of 46 mg of 249 Bk, 520 mg of 252 Cf, 2.0 mg of 253 Es (in a mixture of isotopes), 220 μg of high-purity 253 Es, and 1.6 pg of 257 Fm. We also expect to obtain 125 mg of high-purity 248 Cm from purified californium now in storage. There are no plans to process any of the remaining SRP Pu-Al tubes or to irradiate any plutonium targets in the HFIR; thus, we do not expect to recover any 244 Pu. Two neutron sources were fabricated, bringing the total fabricated to 77. Two sources that had been used previously in various projects were returned to the TRU inventory and are available for reassignment. In special projects, we (1) produced about 1 mg of 250 Cf by irradiation of 249 Bk in HFIR rabbits, and (2) processed some irradiated 248 Cm samples and obtained yield and isotopic composition data for use in determining the capture cross section of 249 Cm in the HFIR. The values that are currently being used for transuranium element decay data and for cross-section data in planning irradiation-processing cycles, calculating production forecasts, and assaying products are tabulated in the Appendix

Chemistry of pyroprocessing for nuclear waste transmutation

Energy Technology Data Exchange (ETDEWEB)

Ackerman, J.P. [Argonne National Laboratory, IL (United States)

1995-10-01

Pyrochemical treatment of spent nuclear fuel is an attractive approach for separating the transuranium (TRU) elements neptunium, plutonium, americium, and curium because of its simplicity, diversion resistance, and potentially low cost.

TRU waste transport economics: an overview

International Nuclear Information System (INIS)

Edling, D.A.; Hopkins, D.R.; Walls, H.C.

1978-01-01

There are currently three predominant methods used to transport transuranium contaminated waste. These are: (1) ATMX Railcars--500 and 600 series, (2) Super Tigers, and (3) Poly Panthers. Both the ATMX-500 and 600 series railcars are massive doubly walled steel railcars which provide the equivalent protection of a Type B package. In ATMX-600 the rapid loading and unloading of the 9 x 9 x 50 feet cargo space is achieved by prepackaging the TRU waste into standard 20-foot steel cargo containers. The ATMX-500 railcars are divided into three inside bays, having dimensions of 16 (l) x 9.25 (w) x 6.25 (h) feet. A typical load consists of 128 55-gallon drums (however, space can accommodate 192 drums), 12 fiberglass boxes (4 x 4 x 7), or a combination of palletized drums and boxes. A Super Tiger is an overpack authorized for Type A, Type B, and large quantities of radioactive materials having outside dimensions of 8 x 8 x 20 feet. Maximum payload is approximately 28,700 lb with a gross weight of 45,000 lb. The primary factors influencing transport costs are examined including freight rates of transport mode, effective cargo (weight and volume) management, effective utilization of available space (package design), transport mileage, and rental fees or initial capital outlay. Miscellaneous factors are also examined

The United States Transuranium and Uranium Registries: overview and recent progress

International Nuclear Information System (INIS)

Kathren, R.L.

1989-01-01

This paper describes the organisation, activities and recent scientific accomplishments of the United States Transuranium and Uranium Registries. Through voluntary donations of tissue obtained at autopsies, the Registries carry out studies of the concentration, distribution and biokinetics of actinides in occupationally exposed persons. Findings from tissue analyses from more than 200 autopsies include the following: a greater proportion of the americium intake, as compared with plutonium, is found in the skeleton; the half-time of americium in liver is significantly shorter than that of plutonium; the concentration of actinide in the skeleton is inversely proportional to the calcium and ash content of the bone; only a small percentage of the total skeletal deposition of plutonium is found in the marrow, implying a smaller risk from irradiation of the marrow relative to the bone surfaces; estimates of plutonium body burden made from urinalysis typically exceed those made from autopsy data; pathologists are unable to discriminate between a group of uranium workers and persons without known occupational exposure on the basis of evaluation of microscopic kidney slides; the skeleton is an important long-term depot for uranium and its fractional uptake by both skeleton and kidney may be greater than indicated by current models. These and other findings and current studies are discussed in depth. (author)

The R and D activities carried out in Ispra according to a cooperation between ENEA COMB and JRC Ispra in the field of radioactive waste management

International Nuclear Information System (INIS)

Nannicini, R.; Dworschak, H.; Daniele, F.

1987-01-01

The R and D activities, carried out in Ispra since 1984, in the field of radioactive waste management,COMB (Technological Development Laboratory) and JRC, concerned final hot tests of the ENEA owned ESTER mini-pilot plant for HLW vitrification, the trasportation of3 of the activeglass? containing crucibles from the Ispra to the Karlsruhe (Transuranium Institute) establishment of JRC for produced by the ESTER plant. While the ESTER experience is being successfully finished, contemporarily the basis has been established to start the PETRA experience, more complete than the previous one, but also more complex. The PETRA experimental infrastructure will be particulary useful for studying, developing and verifying, in real activity conditions, advanced chemical extracting agents and mainly new matrices for the immobilisation of HLWs, or their fractions, and of mixtures of various aqueous waste streams

United States Transuranium Registry: Annual report, October 1, 1986 through September 30, 1987

International Nuclear Information System (INIS)

Swint, M.J.; Kathren, R.L.

1988-04-01

This report summarizes progress of the United States Transuranium Registry for the 1987 fiscal year, including as an appendix the observations and recommendations of the Scientific Advisory Committee. Completion of the first phase of the analytical laboratory intercomparison study has led to verification and reduction in the uncertainty of the values for two NBS Standard Reference Materials. The human arm phantom built as an in-vivo counting calibration standard for Am-241 has been completed and made available for use by other laboratories, along with the previously completed skull phantom. Preliminary evaluation of USTR Case 193, a whole body plutonium case, was completed and reported at a national scientific meeting. The autopsy results tend to verify improvements in recent biokinetic models. Tissue donation was received from a former Hanford worker who received an extensive internal deposition of Am-241 from an explosion in a glove box 10 years prior to death from heart disease. Because of the extraordinary nature of this case, plans are being developed for interlaboratory collaboration to ensure that the knowledge derived from evaluation of this case will be maximized

Analysis of fire and smoke threat to off-gas HEPA filters in a transuranium processing plant

International Nuclear Information System (INIS)

Alvares, N.J.

1988-01-01

The author performed an analysis of fire risk to the high-efficiency particulate air (HEPA) filters that provide ventilation containment for a transuranium processing plant at the Oak Ridge National Laboratory. A fire-safety survey by an independent fire-protection consulting company had identified the HEPA filters in the facility's off-gas containment ventilation system as being at risk from fire effects. Independently studied were the ventilation networks and flow dynamics, and typical fuel loads were analyzed. It was found that virtually no condition for fire initiation exists and that, even if a fire started, its consequences would be minimal as a result of standard shut-down procedures. Moreover, the installed fire-protection system would limit any fire and thus would further reduce smoke or heat exposure to the ventilation components. 4 references, 4 figures, 5 tables

Transuranium removal from Hanford high level waste simulants using sodium permanganate and calcium

International Nuclear Information System (INIS)

Wilmarth, W.R.; Rosencrance, S.W.; Nash, C.A.; Fonduer, F.F.; Di Pirete, D.P.; Di Prete, C.C.

2000-01-01

Plutonium and americium are present in the Hanford high level liquid waste complexant concentrate (CC) due to the presence of complexing agents including di-(2-ethylhexyl) phosphoric acid (D 2 EHPA), tributylphosphate (TBP), hydroxyethylene diamine triacetic acid (HEDTA), ethylene diamine tetraacetic acid (EDTA), citric acid, glycolic acid, and sodium gluconate. The transuranic concentrations approach 600 nCi/g and require processing prior to encapsulation into low activity glass. BNFL's (British Nuclear Fuels Limited's) original process was a ferric co-precipitation method based on earlier investigations by Herting and Orth, et al. Furthermore, flocculation and precipitation are widely used for clarification in municipal water treatment. Co-precipitation of Np, Am, and Pu with ferric hydroxide is also used within an analytical method for the sum of those analytes. Tests to evaluate BNFL's original precipitation process indicated the measured decontamination factors (DFs) and filter fluxes were too low. Therefore, an evaluation of alternative precipitation agents to replace ferric ion was undertaken. Agents tested included various transition metals, lanthanide elements, uranium species, calcium, strontium, and permanganate

FBR type reactor

International Nuclear Information System (INIS)

Hayase, Tamotsu.

1991-01-01

The present invention concerns an FBR type reactor in which transuranium elements are eliminated by nuclear conversion. There are loaded reactor core fuels being charged with mixed oxides of plutonium and uranium, and blanket fuels mainly comprising depleted uranium. Further, liquid sodium is used as coolants. As transuranium elements, isotope elements of neptunium, americium and curium contained in wastes taken out from light water reactors or the composition thereof are used. The reactor core comprises a region with a greater mixing ratio and a region with a less mixing ratio of the transuranium elements. The mixing ratio of the transuranium elements is made greater for the fuels in the reactor core region at the boundary with the blanket of great neutron leakage. With such a constitution, since the positive reactivity value at the reactor core central portion is small in the Na void reactivity distribution in the reactor core, the positive reactivity is small upon Na boiling in the reactor core central region upon occurrence of imaginable accident, to attain reactor safety. (I.N.)

Transuranium Processing Plant semiannual report of production, status, and plans for period ending June 30, 1975

Energy Technology Data Exchange (ETDEWEB)

King, L.J.; Bigelow, J.E.; Collins, E.D.

1976-03-01

During the period January 1, 1975, through June 30, 1975, the following amounts of transuranium elements were recovered from 22 irradiated HFIR targets: 2g /sup 243/Am, 59 g /sup 244/Cm, 51 mg /sup 249/Bk, 465 mg /sup 252/Cf, 2.5 mg /sup 253/Es, and 1.4 pg /sup 257/Fm. In addition, 45 mg of high-purity /sup 248/Cm was operated from /sup 252/Cf which had been recovered and purified during earlier periods, and 56 mg of a lower-quality /sup 248/Cm was separated from californium purification rework solutions. Five HFIR targets, each containing approximately 9 g of actinides (predominantly curium), were fabricated. A new long-term projection showed that /sup 252/Cf production in the TRU-HFIR complex could increase to as much as 2.5 g/year. During the next 18 months, we expect to recover totals of 46 mg of /sup 249/Bk, 520 mg of /sup 252/Cf, 2.0 mg of /sup 253/Es (in a mixture of isotopes), 220 ..mu..g of high-purity /sup 253/Es, and 1.6 pg of /sup 257/Fm. We also expect to obtain 125 mg of high-purity /sup 248/Cm from purified californium now in storage. There are no plans to process any of the remaining SRP Pu-Al tubes or to irradiate any plutonium targets in the HFIR; thus, we do not expect to recover any /sup 244/Pu. No changes were made in the chemical processing flowsheets normally used at TRU. Two neutron sources were fabricated, bringing the total fabricated to 77. In special projects, we (1) produced about 1 mg of /sup 250/Cf by irradiation of /sup 249/Bk in HFIR rabbits, and (2) processed some irradiated /sup 248/Cm samples and obtained yield and isotopic composition data for use in determining the capture cross section of /sup 249/Cm in the HFIR. The values that are currently being used for transuranium element decay data and for cross-section data in planning irradiation-processing cycles, calculating production forecasts, and assaying products are tabulated in the Appendix.

United States Transuranium and Uranium Registries. Annual report, February 1, 2003 - January 31, 2004

Energy Technology Data Exchange (ETDEWEB)

Alldredge, J. R. [Washington State Univ., Pullman, WA (United States); Brumbaugh, T. L. [Washington State Univ., Pullman, WA (United States); Ehrhart, Susan M. [Washington State Univ., Pullman, WA (United States); Elliston, J. T. [Washington State Univ., Pullman, WA (United States); Filipy, R. E. [Washington State Univ., Pullman, WA (United States); James, A. C. [Washington State Univ., Pullman, WA (United States); Pham, M. V. [Washington State Univ., Pullman, WA (United States); Wood, T. G. [Washington State Univ., Pullman, WA (United States); Sasser, L. B. [Washington State Univ., Pullman, WA (United States)

2004-01-31

This year was my fourteenth year with the U. S. Transuranium and Uranium Registries (USTUR). How time flies! Since I became the director of the program five years ago, one of my primary goals was to increase the usefulness of the large USTUR database that consists of six tables containing personal information, medical histories, radiation exposure histories, causes of death, and the results of radiochemical analysis of organ samples collected at autopsy. It is essential that a query of one or more of these tables by USTUR researchers or by collaborating researchers provides complete and reliable information. Also, some of the tables (those without personal identifiers) are destined to appear on the USTUR website for the use of the scientific community. I am pleased to report that most of the data in the database have now been verified and formatted for easy query. It is important to note that no data were discarded; copies of the original tables were retained and the original paper documents are still available for further verification of values as needed.

United States Transuranium and Uranium Registries: A human tissue research program. USTUR annual report for October 1, 1997 through January 31, 1999

Energy Technology Data Exchange (ETDEWEB)

Ehrhart, Susan M. (ed.); Filipy, Ronald E. (ed.)

1999-10-01

The United States Transuranium and Uranium Registries (USTUR) are a human tissue research program studying the deposition, biokinetics and dosimetry of the actinide elements in humans with the primary goals of providing data fundamental to the verification, refinement, or future development of radiation protection standards for these and other radionuclides, and of determining possible bioeffects on both a macro and subcellular level attributable to exposure to the actinides. This annual report covers October 1, 1997, through January 31, 1999; the reporting period has been extended so that future annual reports will coincide with the period covered by the grant itself.

Chemical Technology Division progress report for the period April 1, 1981-March 31, 1983

International Nuclear Information System (INIS)

1983-09-01

Separate abstracts were prepared for eight sections of the report: nuclear waste management; fossil energy; basic science and technology; biotechnology and environmental programs; transuranium-element processing; Nuclear Regulatory Commission programs; Three Mile Island support studies; and miscellaneous programs

Chemical Technology Division progress report for the period April 1, 1981-March 31, 1983. [Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

1983-09-01

Separate abstracts were prepared for eight sections of the report: nuclear waste management; fossil energy; basic science and technology; biotechnology and environmental programs; transuranium-element processing; Nuclear Regulatory Commission programs; Three Mile Island support studies; and miscellaneous programs.

The speciation of dissolved elements in aquatic solution. Radium and actinides

International Nuclear Information System (INIS)

Haesaenen, E.

1994-01-01

In the publication, the chemistry and speciation of radium, thorium, protactinium, uranium, neptunium, lutonium, americium and curium in ground-water environment is reviewed. Special attention is given to the transuranium elements, which have a central role in the repository of nuclear wastes. The most important methods used in the speciation of these elements is presented. The laser-induced methods, developed in the 1980's, are especially discussed. These have made it possible, e.g., to speciate the transuranium elements in their very low, actual repository ground-water concentrations (10-100 ng/l). (54 refs., 10 figs., 3 tabs.)

Radioanalytical Chemistry for Automated Nuclear Waste Process Monitoring

International Nuclear Information System (INIS)

Egorov, Oleg B.; Grate, Jay W.; DeVol, Timothy A.

2003-01-01

This research program is directed toward rapid, sensitive, and selective determination of beta and alpha-emitting radionuclides such as 99Tc, 90Sr, and trans-uranium (TRU) elements in low activity waste (LAW) processing streams. The overall technical approach is based on automated radiochemical measurement principles. Nuclear waste process streams are particularly challenging for rapid analytical methods due to the complex, high- ionic-strength, caustic brine sample matrix, the presence of interfering radionuclides, and the variable and uncertain speciation of the radionuclides of interest. As a result, matrix modification, speciation control, and separation chemistries are required for use in automated process analyzers. Significant knowledge gaps exist relative to the design of chemistries for such analyzers so that radionuclides can be quantitatively and rapidly separated and analyzed in solutions derived from low-activity waste processing operations. This research is addressing these knowledge gaps in the area of separation science, nuclear detection, and analytical chemistry and instrumentation. The outcome of these investigations will be the knowledge necessary to choose appropriate chemistries for sample matrix modification and analyte speciation control and chemistries for rapid and selective separation and preconcentration of target radionuclides from complex sample matrices. In addition, new approaches for quantification of alpha emitters in solution using solid state diode detectors, as well as improved instrumentation and signal processing techniques for use with solid-state and scintillation detectors, will be developed. New knowledge of the performance of separation materials, matrix modification and speciation control chemistries, instrument configurations, and quantitative analytical approaches will provide the basis for designing effective instrumentation for radioanalytical process monitoring. Specific analytical targets include 99 Tc, 90Sr and

TRU decontamination of high-level Purex waste by solvent extraction using a mixed octyl(phenyl)-N,N-diisobutyl-carbamoylmethylphosphine oxide/TBP/NPH (TRUEX) solvent

International Nuclear Information System (INIS)

Horwitz, E.P.; Kalina, D.G.; Diamond, H.; Kaplan, L.; Vandegrift, G.F.; Leonard, R.A.; Steindler, M.J.; Schulz, W.W.

1984-01-01

The TRUEX (transuranium extraction) process was tested on a simulated high-level dissolved sludge waste (DSW). A batch counter-current extraction mode was used for seven extraction and three scrub stages. One additional extraction stage and two scrub stages and all strip stages were performed by batch extraction. The TRUEX solvent consisted of 0.20 M octyl(phenyl)-N,N-diisobutylcarbamoyl-methylphosphine oxide-1.4 M TBP in Conoco (C 12 -C 14 ). The feed solution was 1.0 M in HNO 3 , 0.3 M in H 2 C 2 O 4 and contained mixed (stable) fission products, U, Np, Pu, and Am, and a number of inert constituents, e.g., Fe and Al. The test showed that the process is capable of reducing the TRU concentration in the DSW by a factor of 4 x 10 4 (to <100 nCi/g of disposed form) and reducing the quantity of TRU waste by two orders of magnitude

Trans-Uranium Doping Utilization for Increasing Protected Plutonium Proliferation of Small Long Life Reactor

Energy Technology Data Exchange (ETDEWEB)

Permana, Sidik [Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology 2-12-1-N1-17, O-okayama, Meguro-ku, Tokyo 152-8550 (Japan); Nuclear and Biophysics Research Group, Department of Physics, Bandung Institute of Technology, Gedung Fisika, Jl. Ganesha 10, Bandung 40132 (Indonesia); Suud, Zaki [Nuclear and Biophysics Research Group, Department of Physics, Bandung Institute of Technology, Gedung Fisika, Jl. Ganesha 10, Bandung 40132 (Indonesia); Suzuki, Mitsutoshi [Japan Atomic Energy Agency, Nuclear Non-proliferation Science and Technology Center, 2-4 Shirane Shirakata, Tokai-mura, Ibaraki, 319-1195 (Japan)

2009-06-15

Scientific approaches are performed by adopting some methodologies in order to increase a material 'barrier' in plutonium isotope composition by increasing the even mass number of plutonium isotope such as Pu-238, Pu-240 and Pu-242. Higher difficulties (barrier) or more complex requirement for peaceful use of nuclear materials, material fabrication and handling and isotopic enrichment can be achieved by a higher isotopic barrier. Higher barrier which related to intrinsic properties of plutonium isotopes with even mass number (Pu-238, Pu-240 and Pu-242), in regard to their intense decay heat (DH) and high spontaneous fission neutron (SFN) rates were used as a parameter for improving the proliferation resistance of plutonium itself. Pu-238 has relatively high intrinsic characteristics of DH (567 W/kg) and SFN rate of 2660 n/g/s can be used for making a plutonium characteristics analysis. Similar characteristics with Pu-238, other even mass number of plutonium isotopes such as Pu-240 and Pu-242 have been shown in regard to SFN values. Those even number mass of plutonium isotope contribute to some criteria of plutonium characterization which will be adopted for present study such as IAEA, Pellaud and Kessler criteria (IAEA, 1972; Pellaud, 2002; and Kessler, 2004). The study intends to evaluate the trans-uranium doping effect for increasing protected plutonium proliferation in long-life small reactors. The development of small and medium reactor (SMR) is one of the options which have been adopted by IAEA as future utilization of nuclear energy especially for less developed countries (Kuznetsov, 2008). The preferable feature for small reactors (SMR) is long life operation time without on-site refueling and in the same time, it includes high proliferation resistance feature. The reactor uses MOX fuel as driver fuel for two different core types (inner and outer core) with blanket fuel arrangement. Several trans-uranium doping and some doping rates are evaluated

Decay calculations on medium-level and actinide-containing wastes from the LWR fuel cycle. Pt. 2

International Nuclear Information System (INIS)

Haug, H.O.

1981-12-01

1. The radiotoxicity index as inherent property of the radionuclide inventory was calculated for medium-level and actinide-containing wastes. The calculations were based on the annual limits of intake of the German Radiation Protection Ordinance as well as the new values of annual limits of intake from ICRP-30. The latter imply a higher rating of the toxicity of transuranium nuclides and a lower rating of Sr-90, Tc-99, and Ra-226. Thus, the annual radiotoxicity index is controlled by the transuranics after 10 to 100 years. 2. From the comparison of the radiotoxicity index of conditional and packed wastes with the same volume of uranium ore, it was evaluated that the relative radiotoxicity of the medium-level wastes decreases below the level of pitchblende after less than 100 years and below a 3% uranium ore after less than 2000 of decay. However, based on ICRP-30, the relative radiotoxicity index decreases below the level of pitchblende after 1000 years and decays to the level of the 3% uranium ore at about 10 5 years. 3. The comparison of the radiotoxicity concentration of the total disposal layer with a uranium ore deposit shows that the radiotoxicity concentration based on ICRP-30 of the self-heating wastes placed in single boreholes decays within 2000 years (high level waste within 3000 years) below the level of a uranium ore deposit of 0.2% uranium. The radiotoxicity concentration of the medium-level process waste and the alpha-waste disposed off in disposal chambers decreases to the level of a uranium ore deposit with 0.4 to 6% uranium after about 10 4 years, and 1% after about 10 5 years. (orig./HP) [de

Accelerator driven systems. ADS benchmark calculations. Results of stage 2. Radiotoxic waste transmutation

Energy Technology Data Exchange (ETDEWEB)

Freudenreich, W.E.; Gruppelaar, H

1998-12-01

This report contains the results of calculations made at ECN-Petten of a benchmark to study the neutronic potential of a modular fast spectrum ADS (Accelerator-Driven System) for radiotoxic waste transmutation. The study is focused on the incineration of TRans-Uranium elements (TRU), Minor Actinides (MA) and Long-Lived Fission Products (LLFP), in this case {sup 99}Tc. The benchmark exercise is made in the framework of an IAEA Co-ordinated Research Programme. A simplified description of an ADS, restricted to the reactor part, with TRU or MA fuel (k{sub eff}=0.96) has been analysed. All spectrum calculations have been performed with the Monte Carlo code MCNP-4A. The burnup calculations have been performed with the code FISPACT coupled to MCNP-4A by means of our OCTOPUS system. The cross sections are based upon JEF-2.2 for transport calculations and supplemented with EAF-4 data for inventory calculations. The determined quantities are: core dimensions, fuel inventories, system power, sensitivity on external source spectrum and waste transmutation rates. The main conclusions are: The MA-burner requires only a small accelerator current increase during burnup, in contrast to the TRU-burner. The {sup 99} Tc-burner has a large initial loading; a more effective design may be possible. 5 refs.

Accelerator driven systems. ADS benchmark calculations. Results of stage 2. Radiotoxic waste transmutation

International Nuclear Information System (INIS)

Freudenreich, W.E.; Gruppelaar, H.

1998-12-01

This report contains the results of calculations made at ECN-Petten of a benchmark to study the neutronic potential of a modular fast spectrum ADS (Accelerator-Driven System) for radiotoxic waste transmutation. The study is focused on the incineration of TRans-Uranium elements (TRU), Minor Actinides (MA) and Long-Lived Fission Products (LLFP), in this case 99 Tc. The benchmark exercise is made in the framework of an IAEA Co-ordinated Research Programme. A simplified description of an ADS, restricted to the reactor part, with TRU or MA fuel (k eff =0.96) has been analysed. All spectrum calculations have been performed with the Monte Carlo code MCNP-4A. The burnup calculations have been performed with the code FISPACT coupled to MCNP-4A by means of our OCTOPUS system. The cross sections are based upon JEF-2.2 for transport calculations and supplemented with EAF-4 data for inventory calculations. The determined quantities are: core dimensions, fuel inventories, system power, sensitivity on external source spectrum and waste transmutation rates. The main conclusions are: The MA-burner requires only a small accelerator current increase during burnup, in contrast to the TRU-burner. The 99 Tc-burner has a large initial loading; a more effective design may be possible. 5 refs

Actinide-soil interactions in waste management at the Savannah River Plant

International Nuclear Information System (INIS)

Holcomb, H.P.; Horton, J.H.; Wilhite, E.L.

1976-01-01

Three aspects of the transuranium (TRU) nuclide-soil interaction were studied in connection with Savannah River Plant (SRP) burial ground operations. Results of the studies are reported as three separate parts of this report

Research and development plan for the Slagging Pyrolysis Incinerator

International Nuclear Information System (INIS)

Hedahl, T.G.; McCormack, M.D.

1979-01-01

Objective is to develop an incinerator for processing disposed transuranium waste. This R and D plan describes the R and D efforts required to begin conceptual design of the Slagging Pyrolysis Incinerator (Andco-Torrax). The program includes: incinerator, off-gas treatment, waste handling, instrumentation, immobilization analyses, migration studies, regulations, Belgium R and D test plan, Disney World test plan, and remote operation and maintenance

Radioanalytical Chemistry for Automated Nuclear Waste Process Monitoring

International Nuclear Information System (INIS)

Egorov, Oleg B.; Grate, Jay W.; DeVol, Timothy A.

2004-01-01

This research program is directed toward rapid, sensitive, and selective determination of beta and alpha-emitting radionuclides such as 99Tc, 90Sr, and trans-uranium (TRU) elements in low activity waste (LAW) processing streams. The overall technical approach is based on automated radiochemical measurement principles, which entails integration of sample treatment and separation chemistries and radiometric detection within a single functional analytical instrument. Nuclear waste process streams are particularly challenging for rapid analytical methods due to the complex, high-ionic-strength, caustic brine sample matrix, the presence of interfering radionuclides, and the variable and uncertain speciation of the radionuclides of interest. As a result, matrix modification, speciation control, and separation chemistries are required for use in automated process analyzers. Significant knowledge gaps exist relative to the design of chemistries for such analyzers so that radionuclides can be quantitatively and rapidly separated and analyzed in solutions derived from low-activity waste processing operations. This research is addressing these knowledge gaps in the area of separation science, nuclear detection, and analytical chemistry and instrumentation. The outcome of these investigations will be the knowledge necessary to choose appropriate chemistries for sample matrix modification and analyte speciation control and chemistries for rapid and selective separation and preconcentration of target radionuclides from complex sample matrices. In addition, new approaches for quantification of alpha emitters in solution using solid-state diode detectors, as well as improved instrumentation and signal processing techniques for use with solid-state and scintillation detectors, will be developed. New knowledge of the performance of separation materials, matrix modification and speciation control chemistries, instrument configurations, and quantitative analytical approaches will

Chemistry Division annual progress report for period ending January 31, 1986

Energy Technology Data Exchange (ETDEWEB)

1986-05-01

This report has been indexed by 11 separate chapters. The subjects covered are: coal chemistry, aqueous chemistry at high temperatures and pressures, geochemistry, materials chemistry, chemistry of transuranium elements and compounds, separations chemistry, catalysis, electron spectroscopy, nuclear waste chemistry, heuristic modeling, and special topics. (PLG)

Chemistry Division annual progress report for period ending January 31, 1986

International Nuclear Information System (INIS)

1986-05-01

This report has been indexed by 11 separate chapters. The subjects covered are: coal chemistry, aqueous chemistry at high temperatures and pressures, geochemistry, materials chemistry, chemistry of transuranium elements and compounds, separations chemistry, catalysis, electron spectroscopy, nuclear waste chemistry, heuristic modeling, and special topics

Transuranium element toxicity: dose-response relationships at low exposure levels. Summary and speculative interpretation relative to exposure limits

International Nuclear Information System (INIS)

Thompson, R.C.

1975-01-01

A summary is given of information on transuranium element toxicity and the correlation of this information with current established exposure limits. It is difficult to calculate a biologically relevant radiation dose from deposited plutonium; it is exposure that must be controlled in order to prevent biological effect, and if the relationship between exposure and effect is known, then radiation dose is of no concern. There are extensive data on the effects of plutonium in bone. Results of studies at the University of Utah indicate that plutonium in beagles may be as much as ten times more toxic than radium. It has been suggested that this toxicity ratio may be even higher in man than in the beagle dog because of differences in surface-to-volume ratios and differences in the rate of burial of surface-deposited plutonium. The present capabilities for extrapolating dose-effect relationships seem to be limited to the setting of upper limits, based on assumptions of linearity and considerations related to natural background

Design and installation of high-temperature ultrasonic measuring system and grinder for nuclear fuel containing trans-uranium elements

International Nuclear Information System (INIS)

Serizawa, Hiroyuki; Kikuchi, Hironobu; Iwai, Takashi; Arai, Yasuo; Kurosawa, Makoto; Mimura, Hideaki; Abe, Jiro

2005-07-01

A high-temperature ultrasonic measuring system had been designed and installed in a glovebox (711-DGB) to study a mechanical property of nuclear fuel containing trans-uranium (TRU) elements. A figuration apparatus for the cylinder-type sample preparation had also been modified and installed in an established glovebox (142-D). The system consists of an ultrasonic probe, a heating furnace, cooling water-circulating system, a cooling air compressor, vacuum system, gas supplying system and control system. An A/D converter board and an pulsar/receiver board for the measurement of wave velocity were installed in a personal computer. The apparatus was modified to install into the glovebox. Some safety functions were supplied to the control system. The shape and size of the sample was revised to minimize the amount of TRU elements for the use of the measurement. The maximum sample temperature is 1500degC. The performance of the installed apparatuses and the glovebox were confirmed through a series of tests. (author)

Determination of Np, Pu and Am in high level radioactive waste with extraction-liquid scintillation counting

International Nuclear Information System (INIS)

Yang Dazhu; Zhu Yongjun; Jiao Rongzhou

1994-01-01

A new method for the determination of transuranium elements, Np, Pu and Am with extraction-liquid scintillation counting has been studied systematically. Procedures for the separation of Pu and Am by HDEHP-TRPO extraction and for the separation of Np by TTA-TiOA extraction have been developed, by which the recovery of Np, Pu and Am is 97%, 99% and 99%, respectively, and the decontamination factors for the major fission products ( 90 Sr, 137 Cs etc.) are 10 4 -10 6 . Pulse shape discrimination (PSD) technique has been introduced to liquid scintillation counting, by which the counting efficiency of α-activity is >99% and the rejection of β-counts is >99.95%. This new method, combining extraction and pulse shape discrimination with liquid scintillation technique, has been successfully applied to the assay of Np, Pu and Am in high level radioactive waste. (author) 7 refs.; 7 figs.; 4 tabs

A study on the criticality search of transuranium recycling BWR core by adjusting supplied fuel composition in equilibrium state

International Nuclear Information System (INIS)

Seino, Takeshi; Sekimoto, Hiroshi

1998-01-01

There have been some difficulties in carrying out an extensive evaluation of the equilibrium state of Light Water Reactor (LWR) recycling operations keeping their fixed criticality condition using conventional design codes because of the complexity of their calculation model for practical fuel and core design and because of a large amount of calculation time. This study presents an efficient approach to secure the criticality in an equilibrium cycle by adjusting a supplied fuel composition. The criticality search is performed by the use of fuel importance obtained from the equation adjoint to a continuously fuel supplied core burnup equation. Using this method, some numerical analyses were carried out in order to evaluate the mixed oxide (MOX) fuel composition of equilibrium Boiling Water Reactor (BWR) cores satisfying the criticality requirement. The results showed the comprehensive and quantitative characteristics on the equilibrium cores confining transuraniums for different MOX fuel loading fractions and irradiating conditions

German Spent Nuclear Fuel Legacy: Characteristics and High-Level Waste Management Issues

Directory of Open Access Journals (Sweden)

A. Schwenk-Ferrero

2013-01-01

Full Text Available Germany is phasing-out the utilization of nuclear energy until 2022. Currently, nine light water reactors of originally nineteen are still connected to the grid. All power plants generate high-level nuclear waste like spent uranium or mixed uranium-plutonium dioxide fuel which has to be properly managed. Moreover, vitrified high-level waste containing minor actinides, fission products, and traces of plutonium reprocessing loses produced by reprocessing facilities has to be disposed of. In the paper, the assessments of German spent fuel legacy (heavy metal content and the nuclide composition of this inventory have been done. The methodology used applies advanced nuclear fuel cycle simulation techniques in order to reproduce the operation of the German nuclear power plants from 1969 till 2022. NFCSim code developed by LANL was adopted for this purpose. It was estimated that ~10,300 tonnes of unreprocessed nuclear spent fuel will be generated until the shut-down of the ultimate German reactor. This inventory will contain ~131 tonnes of plutonium, ~21 tonnes of minor actinides, and 440 tonnes of fission products. Apart from this, ca.215 tonnes of vitrified HLW will be present. As fission products and transuranium elements remain radioactive from 104 to 106 years, the characteristics of spent fuel legacy over this period are estimated, and their impacts on decay storage and final repository are discussed.

Chemical Technology Division progress report, April 1, 1983-March 31, 1985

International Nuclear Information System (INIS)

1985-10-01

The status of the following programs is reported: fission energy; nuclear and chemical waste management; environmental control technology; basic science and technology; biotechnology programs; transuranium-element processing; Nuclear Regulatory Commission programs; Consolidated Edison Uranium Solidification Project; radioactive materials production; computer 1 engineering applications; and miscellanous programs

Chemical Technology Division progress report, April 1, 1983-March 31, 1985

Energy Technology Data Exchange (ETDEWEB)

1985-10-01

The status of the following programs is reported: fission energy; nuclear and chemical waste management; environmental control technology; basic science and technology; biotechnology programs; transuranium-element processing; Nuclear Regulatory Commission programs; Consolidated Edison Uranium Solidification Project; radioactive materials production; computer 1 engineering applications; and miscellanous programs.

Safety analysis report for packaging: DOT-7A fiberglass-coated plywood box for transuranium solid waste

International Nuclear Information System (INIS)

Adcock, F.E.; Cash, C.L.

1976-01-01

A DOT Specification 7A, fiberglass-coated plywood box for shipping alpha-emitting transuranic waste has been developed. Nominal size for the box is 4 by 4 by 7 ft; maximum gross weight is 5000 lb. Construction is of 3 / 4 -in. plywood with internal framing members of 2- by 4-in. lumber. The entire box, including the glued and nailed lid, is covered with a 0.12-in.-thick fiberglass coating. The required four-foot drop tests were passed without the box being damaged. Additional drops from 12 ft resulted in some cracking in a 2600-lb box and in cracking plus some loss of contents in a test box loaded to 5700 lb. A static load of 25,000 lb caused no deformation or damage. This box costs $3.50/ft 3 , which is approximately half the cost of steel drums with rigid polyethylene liners

A study on the criticality search of transuranium recycling BWR core by adjusting supplied fuel composition in equilibrium state

International Nuclear Information System (INIS)

Seino, Takeshi; Sekimoto, Hiroshi

1997-01-01

There have been some difficulties in carrying out an extensive evaluation of the equilibrium state of Light Water Reactor (LWR) recycling operations keeping their fixed criticality condition using conventional design codes, because of the complexity of their calculational model for practical fuel and core design and because of a large amount of calculation time. This study presents an efficient approach to secure the criticality in an equilibrium cycle by adjusting a supplied fuel composition. The criticality search is performed by the use of fuel importance obtained from the equilibrium adjoint to a continuously fuel supplied core burnup equation. Using this method, some numerical analyses were carried out in order to evaluate the mixed oxide (MOX) fuel composition of equilibrium Boiling Water Reactor (BWR) cores satisfying the criticality requirement. The results showed the comprehensive and quantitative characteristics on the equilibrium cores confining transuranium for different MOX fuel loading fractions and irradiating conditions. (author)

Application of extraction chromatography to the recovery of neptunium, plutonium and americium from an industrial waste

International Nuclear Information System (INIS)

Madic, C.; Kertesz, C.; Sontag, R.; Koehly, G.

1980-01-01

A pilot scale investigation was made to evaluate the possible application of the extraction chromatographic method (LLC) to the partitioning of alpha emitters from liquid wastes containing traces of transuranium elements. A secondary purpose was to obtain pure Am0 2 , which is used to produce alpha, gamma, and neutron sources. The process developed for alpha partitioning consists essentially of the extraction of macro amounts of uranium with 30% TBP in dodecane in mixer-settlers, then coextraction of Np-237, Pu-239, and Am-241 by LLC on a macro column filled with di-n-hexyl-octoxy-methyl-phosphine oxide (POX.11) adsorbed on an inert support. In each run about 200 liters of initial waste are decontaminated of alpha emitters. The loading step is followed by selective elution of americium, neptunium, and plutonium. The americium eluate is then subjected to the following operations: (1) separation of Am from Fe and Cd by LLC on a TBP column and (2) separation of Am from lanthanide traces by LLC on an HD(DiBM)P column after oxidation of Am(III) to Am(VI). The Am in the eluate is subsequently reduced to Am(III) and precipitated as oxalate with oxalic acid. The oxalate is then filtered and calcined to yield pure AmO 2

Groundwater monitoring and modelling of the “Vector” site for near-surface radioactive waste disposal in the Chornobyl exclusion zone

Directory of Open Access Journals (Sweden)

D. Bugai

2017-12-01

Full Text Available Results of purposeful groundwater monitoring and modelling studies are presented, which were carried out in order to better understand groundwater flow patterns from the “Vector” site for near-surface radioactive waste disposal and storage in the Chornobyl exclusion zone towards river network. Both data of observations at local-scale monitoring well network at “Vector” site carried out in 2015 - 2016 and modelling analyses using the regional groundwater flow model of Chornobyl exclusion zone suggest that the groundwater discharge contour for water originating from “Vector” site is Sakhan River, which is the tributary to Pripyat River. The respective groundwater travel time is estimated at 210 - 340 years. The travel times in subsurface for 90Sr, 137Cs, and transuranium radionuclides (Pu isotopes, 241Am are estimated respectively at thousands, tenths of thousands, hundreds of thousands – million of years. These results, as well as presented data of analyses of lithological properties of the geological deposits of the unsaturated zone at “Vector” site, provide evidence for good protection of surface water resources from radioactivity sources (e.g., radioactive wastes to be disposed in the near-sursface facilities at “Vector” site.

Chemistry Division annual progress report for period ending January 31, 1984

Energy Technology Data Exchange (ETDEWEB)

1984-05-01

Progress is reported in the following fields: coal chemistry, aqueous chemistry at high temperatures and pressures, geochemistry, high-temperature chemistry and thermodynamics of structural materials, chemistry of transuranium elements and compounds, separations chemistry, elecrochemistry, catalysis, chemical physics, theoretical chemistry, nuclear waste chemistry, chemistry of hazardous chemicals, and thermal energy storage.

Dechlorination and Stabilization of Molten Salt Waste by Using xSiO2-yAl2O3- zP2O5 at Melting Temperature

International Nuclear Information System (INIS)

Park, Hwanseo; Kim, Intae; Kim, Hwanyoung; Kim, Joonhyung

2007-01-01

Molten salt waste, which is generated from the pyroprocess to separate uranium and trans-uranium elements from spent nuclear fuel, has been interested to researchers in the radioactive waste management. For its final disposal, direct immobilization into a suitable host matrix or indirect solidification by other chemical routes requires the control of chlorides and its volatility since molten salt wastes mainly consist of volatile metal chlorides. Glass-bonded sodalite (Na 6 M 2 Al 6 Si 6 O 24 Cl 2 , 1-5) suggested by Argonne National Laboratory (ANL), to the present, could be a practical solution to the immobilization of this waste, where waste form can be fabricated at about 915 .deg., lower than the melting temperature of many borosilicate glasses ( -1150 .deg.). A wet dechlorination to oxides or a thermal conversion into borate glass was suggested to remove Cl from salt waste (6-7) and it seemed that the preference of radionuclides for the intended chemical conversions or immobilizations described above could be hardly accomplished or failed, except the phosphate precipitation method suggested by Volkovich and his co-workers (8). Our research group suggested a novel method to treat molten salt waste, named GRSS (Gel-Route Stabilization/Solidification) using Si-P-Al system as a gel-forming system. This showed little vaporization during high temperature process and good leach resistance on Cs and Sr. As another method, this study suggested a method to stabilize molten salt wastes by using xSiO 2 -yAl 2 O 3 - zP 2 O 5 material. GRSS method is considered as a 'reaction system' to completely convert salt waste into stable product while the inorganic material used in this study is a stabilizer for salt wastes. Using this material, this study investigated the reactivity on different metal chlorides, thermal stability, leach-resistance and etc

Encapsulating of high-level radioactive waste with use of pyrocarbon and silicon carbide coatings

International Nuclear Information System (INIS)

Chernikov, A.

2007-01-01

It is known that high-level radioactive waste (HLW) constitute a real danger to biosphere, especially that their part, which contains transuranium and long-lived radionuclides resulting during reprocessing of nuclear fuel industrial and power reactors. Such waste contains approximately 99 % of long-lived fission products and transplutonium elements. At present, the concept of multi barrier protection of biosphere from radioactive waste is generally acknowledged. The main barriers are the physicochemical form of waste and enclosing strata of geological formation at places of waste-disposal. Applied methods of solidification of HLW with preparation of phosphatic and borosilicate glasses do not guarantee in full measure safety of places of waste-disposal of solidified waste in geological formations during thousand years. One promising way to improve HLW handling safety is placing of radionuclides in mineral-like matrixes similar to natural materials. The other possible way to increase safety of HLW disposal places is suggested for research by experts of Russian research institutes, for example, in the proposal for the Project of ISTC and considered in the present report, is to introduce an additional barrier on a radionuclides migration path by coating of HLW particles. Unique protective properties of pyrocarbon and silicon carbide such as low coefficients of diffusion of gaseous and solid fission products and high chemical and radiation stability [1] attract attention to these materials for coating of solidified HLW. The objective of the Project is the development of method of HLW encapsulating with use of pyrocarbon and silicon carbide coatings. To gain this end main direction of researches, including analysis of various encapsulation processes of fractionated HLW, and expected results are presented. Realization of the Project will allow to prove experimentally the efficiency of the proposed approach in the solution of the problem of HLW conditioning and ecological

Decontamination of evaporator concentrated for cesium, strontium and transuranium elements

International Nuclear Information System (INIS)

Dozol, J.F.; Eymard, S.; Gambade, R.; La Rosa, G.; Casas i Garcia, J.

1992-01-01

Reprocessing produces medium activity liquid wastes. These wastes are evaporated, the distillate is discharged into the environment and all active and inactive salts are concentrated, leading to an important volume of wastes. The objective of this work is to separate long-lived radionuclides into a small volume addressed to a geological formation from the large volume of the concentrate, this concentrate after embedding is disposed on surface site. Supported liquid membranes (S.L.M.s) are used because they enable us to use low inventory of organic phase, hence to use very sophisticated and expensive extractants. To confirm the results obtained with simulated wastes, tests were carried out with genuine concentrate using two S.L.M.s: the first one with CMPO/TBP diluted in decalin, the second one impregnated by the mixture DC18-C-6/decanol/hexylbenzene. The decontamination factor (DF) achieved for actinides is about 100 with the CMPO/TBP SLM. The DF is increased by the second membrane: after treatment with crown ether SLM, the total DF is higher than 400

Groundwater quality monitoring well installation for Waste Area Groupings 8 and 9 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

Mortimore, J.A.; Ebers, M.L.

1994-09-01

This report documents the drilling and installation of nine groundwater quality monitoring (GQM) wells on the perimeter of Waste Area Grouping (WAG) 8 and two GQM wells on the perimeter of WAG 9. WAG 8 encompasses approximately 34 acres, most of which are located in Melton Valley. Irregular in shape, the site has two sinuous extensions from its northern end that contain the low-level radioactive waste (LLW) transfer lines. WAG 8 contains 22 solid waste management units (SWMUs) that can be divided into 4 groups. These groups include the High Flux Isotope Reactor/Transuranium Processing Facility waste collection basins, the LLW line leak sites, and the active LLW tanks. WAG 9 encompasses about 3 acres and is located west of the main portion of WAG 8 and south of Melton Valley Drive. WAG 9 contains four SWMUs. The wells in WAGs 8 and 9 were drilled and developed from June 1989 to March 1990. Monitoring wells were installed to characterize and assess the WAGs in accordance with applicable Department of Energy, state, and Environmental Protection Agency regulatory requirements. The purpose of the well installation program was to install GQM wells for groundwater characterization at WAGs 8 and 9. Data packages produced during installation activities by the ERCE hydrogeologists are an important product of the program. These packages document the well drilling, installation, and development activities and provide valuable data for well sampling and WAG characterization. The forms contained in the packages include predrilling and postdrilling checklists, drilling and construction logs, development and hydraulic conductivity records, and quality control-related documents

Proposals for setting possible limits on intake of transuranium radionuclides absorbed from the gastrointestinal tract

International Nuclear Information System (INIS)

Zalikin, G.A.; Nisimov, P.G.

1987-01-01

The absorption of transuranium elements ( 238 Pu, 241 Am, 252 Cf) from the gastrointestinal (GI) tract as influenced by physiological factors (e.g. age) and physical and chemical properties of compounds incorporated has been studied in 600 white mongrel rats. Average values of absorption have been determined for simple salts and a complex citrate. A number of factors increasing absorption have been found. Thus, originally bound compounds contained in the meat of animals incorporated with 238 Pu and 241 Am when alive, 241 Am-containing potato juice and green oat stalks enhanced absorption by a factor of 5 to 30 as compared with an adequate control. Ethanol administered orally as a 20% solution increased the absorption of americium nitrate by 60% and that of citrate by 23%. Oral administratio of 241 Am nitrate solution together with ferric chloride changes the metabolic kinetics of the nuclide completely. The total absorption of americium from DI tract is 7.1 times that of the control, but a considerable fraction absorbed into blood is excreted with urine (4.2% over 8 days). Among physiological factors age effects the absorption of transuranics from the GI tract to acertain degree. The absorption of 252 Cf in 7 day-old young rats proves to be 8.1 times that of adults. Gestation brought about a 2.7 fold increase of 241 Am absorption

Transuranium element incorporation into the β-U3O8 uranyl sheet

International Nuclear Information System (INIS)

Miller, M.L.; Burns, P.C.; Ewing, R.C.; Finch, R.J.

1997-01-01

Spent nuclear fuel (SNF) is unstable under oxidizing conditions. Although recent studies have determined the paragenetic sequence for uranium phases that result from the corrosion of SNF, there are only limited data on the potential of alteration phases for the incorporation of transuranium elements. The crystal chemical characteristics of transuranic elements (TUE) are to a certain extent similar to uranium; thus TUE incorporation into the sheets of uranyl oxide hydrate structures can be assessed by examination of the structural details of the β-U 3 O 8 sheet type. The sheets of uranyl polyhedra observed in the crystal structure of β-U 3 O 8 also occur in the mineral billietite, where they alternate with α-U 3 O 8 type sheets. Preliminary crystal structure determinations for the minerals ianthinite, and wyartite, indicate that these phases also contain β-U 3 O 8 type sheets. The β-U 3 O 8 sheet anion topology contains triangular, rhombic, and pentagonal sites in the proportions 2:1:2. In all structures containing β-U 3 O 8 type sheets, the triangular sites are vacant. The pentagonal sites are filled with U 6+ O 2 forming pentagonal bipyramids. The rhombic dipyramids filling the rhombic sites contain U 6+ O 2 in billietite, U 4+ O 2 in β-U 3 O 8 , U 4+ (H 2 O) 2 in ianthinite, and U 4+ O 3 in wyartite-II. Interlayer species include: H 2 O (billietite, wyartite II, and ianthinite), Ba 2+ (billietite) Ca 2+ wyartite II, and Co 3 2- wyartite II; there is no interlayer in β-U 3 O 8 . The similarity of known TUE coordination polyhedra with those of U suggests that the β-U 3 O 8 sheet will accommodate TUE substitution coupled with variations in apical anion configuration and interlayer population providing the required charge balance

European institute for transuranium elements. Annual report 1987

International Nuclear Information System (INIS)

1988-01-01

The Report covers work done in the field of operation limits of nuclear fuels, transient behaviour of oxide fuels and fission product release under severe fuel damage conditions, actinide cycle safety, actinide research, safeguards reactor safety waste management and radiation protection

United States Transuranium Registry annual report October 1, 1979-October 1, 1980 to Human Health and Assessments Division, US Department of Energy

International Nuclear Information System (INIS)

Breitenstein, B.D. Jr.; Heid, K.R.; Swint, M.J.

1981-01-01

One of the primary objectives of the United States Transuranium Registry is to improve health physics models used to evaluate occupational exposure from internally deposited transuranic elements. During FY 1980 emphasis continued to be placed on improving methods for collecting data. The use of a prosector for all cases assures that autopsy tissue samples are properly identified and reasonably well cleaned. A procedure has been developed at the University of California Los Alamos Scientific Laboratory to ash tissue specimens collected as part of this program. This same method is also being utilized at the Rocky Flats Analytical laboratory. A comparison of data collected from thirteen USTR autopsy cases using wet and ashed weights was made. The results suggest that the use of ashed weights improves the agreement of the systemic burden at autopsy to that estimated using ante mortem health physics data by a factor of nearly two

Radionuclide-migration model for buried waste at the Savannah River Plant

International Nuclear Information System (INIS)

King, C.M.; Root, R.W. Jr.

1982-01-01

Solid waste has been buried at the Savannah River Plant burial ground since 1953. The solid waste is contaminated with alpha-emitting transuranium (TRU) nuclides, with beta-gamma-emitting activation and fission products, and with tritium. To provide guidance for the current use and eventual permanent retirement of the burial site from active service, a radionuclide environmental transport model has been used to project the potential influence on man if the burial site were occupied after decommissioning. The model used to simulate nuclide migration includes the various hydrological, animal, vegetative, atmospheric, and terrestrial pathways in estimating dose to man as a function of time. Specific scenarios include a four-person home farm on the 195-acre burial ground. Key input to the model includes site-specific nuclide migration rates through soil, nuclide distribution coefficients, and site topography. Coupled with literature data on plant and animal concentration factors, transfer coefficients reflecting migration routes are input to a set of linear differential equations for subsequent matrix solution. Output from the model is the nuclide-specific decayed curie intake by man. To discern principal migration routes, model-compartment inventories with time can also be displayed. Dose projections subsequently account for organ concentrations in man for the nuclide of interest. Radionuclide migration has been examined in depth with the dose-to-man model. Movement by vegetative pathways is the primary route for potential dose to man for short-lived isotopes. Hydrological routes provide a secondary scheme for long-lived nuclides. Details of model methodology are reviewed

Workshop on environmental research for transuranic elements, Seattle, Washington, November 12--14, 1975

International Nuclear Information System (INIS)

1975-01-01

Brief summaries are presented of discussions among scientists conducting research on the transport and diffusion of transuranium elements in aquatic and terrestrial ecosystems. Emphasis was placed on 238 Pu, 239 Pu, 240 Pu, and 241 Am in ecosystems and food chains. Areas for future research were suggested to insure the safe storage of radioactive wastes from the nuclear industry

Transmutation of radioactive wastes: how and why?

International Nuclear Information System (INIS)

Patarin, L.

2004-01-01

After having evoked the natural or spontaneous transmutation of natural or artificial radioactive atoms, the author describes how this transmutation is technically obtained, indicates the two main families of atoms present in a used nuclear fuel and for which transmutation is to be investigated (long-lived fission residues or products, and transuranium elements) and of which the behaviour in neutron fluxes must be explored. He discusses the industrial means required for artificial transmutation. He discusses the interest of performing such a transmutation

Relevance of the studies of the OKLO natural nuclear reactors to the storage of radioactive wastes

International Nuclear Information System (INIS)

Hagemann, R.; Roth, E.

1978-01-01

The geological environment of the OKLO natural nuclear reactors is described along with the operating caracteristics of the reactors. Data relevant to the stability of most of the fission products and to the transuranium elements in the reaction zones are reviewed. (orig.) [de

Materials evaluation for a transuranic processing facility

International Nuclear Information System (INIS)

Barker, S.A.; Schwenk, E.B.; Divine, J.R.

1990-11-01

The Westinghouse Hanford Company, with the assistance of the Pacific Northwest Laboratory, is developing a transuranium extraction process for preheating double-shell tank wastes at the Hanford Site to reduce the volume of transuranic waste being sent to a repository. The bench- scale transuranium extraction process development is reaching a stage where a pilot plant design has begun for the construction of a facility in the existing B Plant. Because of the potential corrosivity of neutralized cladding removal waste process streams, existing embedded piping alloys in B Plant are being evaluated and ''new'' alloys are being selected for the full-scale plant screening corrosion tests. Once the waste is acidified with HNO 3 , some of the process streams that are high in F - and low in Al and zr can produce corrosion rates exceeding 30,000 mil/yr in austenitic alloys. Initial results results are reported concerning the applicability of existing plant materials to withstand expected process solutions and conditions to help determine the feasibility of locating the plant at the selected facility. In addition, process changes are presented that should make the process solutions less corrosive to the existing materials. Experimental work confirms that Hastelloy B is unsatisfactory for the expected process solutions; type 304L, 347 and 309S stainless steels are satisfactory for service at room temperature and 60 degrees C, if process stream complexing is performed. Inconel 625 was satisfactory for all solutions. 17 refs., 5 figs., 8 tabs

The EBR-II spent fuel treatment program

International Nuclear Information System (INIS)

Lineberry, M.J.; McFarlane, H.F.

1995-01-01

Argonne National Laboratory has refurbished and equipped an existing hot cell facility for demonstrating a high-temperature electrometallurgical process for treating spent nuclear fuel from the Experimental Breeder Reactor-11. Two waste forms will be produced and qualified for geologic disposal of the fission and activation products. Relatively pure uranium will be separated for storage. Following additional development, transuranium elements will be blended into one of the high-level waste streams. The spent fuel treatment program will help assess the viability of electrometallurgical technology as a spent fuel management option

Transuranium processing plant semiannual report of production, status, and plans for period ending June 30, 1976

Energy Technology Data Exchange (ETDEWEB)

King, L.J.; Bigelow, J.E.; Collins, E.D.

1977-02-01

During the period January 1, 1976, through June 30, 1976, the following amounts of transuranium elements were recovered from ten irradiated HFIR targets: 2 g /sup 243/Am, 50 g /sup 244/Cm, 29 mg /sup 249/Bk, 277 mg /sup 252/Cf, 1.7 mg /sup 253/Es, and 0.5 pg /sup 257/Fm. About 50 mg of high-purity /sup 248/Cm was purified chemically for shipment, and another 75 mg of /sup 248/Cm was separated from /sup 252/Cf. Nineteen HFIR targets, each containing approximately 9 g of curium, were fabricated. There have been no changes during this report period in the chemical processing flowsheets normally used at TRU. Five neutron sources were fabricated, bringing the total fabricated to 84. Six sources that were used previously in various projects have been returned to TRU and are available for reassignment. Special projects included (1) the continued study of /sup 250/Cm production by irradiation of /sup 248/Cm; (2) the production of 0.54 mg of /sup 250/Cf by irradiation of /sup 249/Bk; (3) the separation of approximately 200 pg of /sup 254/Cf from 39-hr /sup 254m/Es that was produced by irradiation of 5 ..mu..g of /sup 253/Es; and (4) the determination of process steps needed to obtain rare-earth fission products in an oxide form from LiCl-based anion exchange raffinate solution.

Management of transuranium-contaminated solid wastes from the Department of Energy nuclear materials production and R and D programs

International Nuclear Information System (INIS)

Perge, A.F.; Trice, V.G. Jr.

1978-01-01

This plan has been extracted from a master plan that covers management of all types of wastes for which the Department of Energy (DOE) has responsibility. The overall plan has not received approval as policy for the new DOE which came into being in October 1977. Thus, we have to label it as a draft plan, even though our programs, as operating today, are being carried forward in conformance with most of it. Several of our assumptions are controversial and may be modified before the plan is approved. The points we will cover are: A. Goals, B. Scope, C. Assumptions, D. Strategy, E. Specific Objectives, F. Current Activities, and G. Milestones and Schedule. The last point, Milestones and Schedule, was not covered at the meeting. However, it is included here in the proceedings

Treatability Studies Used to Test for Exothermic Reactions of Plutonium Decontamination Chemicals

Energy Technology Data Exchange (ETDEWEB)

Ewalt, John R.; Minette, Michael J.; Hopkins, Andrea M.; Cooper, Thurman D.; Simiele, Connie J.; Scott, Paul A.; Scheele, Randall D.; Charboneau, Stacy L.

2005-08-07

Fluor Hanford is decommissioning the PFP at the Hanford Site and is considering using agressive chemicals to remove transuranium contaminants. As part of the evaluation of these methods, Fluor is considering the path for disposal and the thermal stability of the waste products from the decontamination process. This paper provides the results of our studies on cerium nitrate and RadPro(TM), a nitric acid based complexant.

Chemical Technology Division annual progress report for period ending March 31, 1976

International Nuclear Information System (INIS)

1976-09-01

The status is reported for various research programs including waste management, transuranium-element processing, isotopic separations, preparation of 233 UO 2 , separations chemistry, biomedical technology, environmental studies, coal technology program, actinide oxides and nitrides and carbides, chemical engineering, controlled thermonuclear program, iodine studies, reactor safety, NRC programs, and diffusion of adsorbed species in porous media. Details of these programs are given in topical reports and journal articles

Annual report 1990. Institute for Transuranium Elements

International Nuclear Information System (INIS)

1991-01-01

Basic Safety Research on Nuclear Fuels in 1990 centered on studies of the interrelation between structure, fission gas release and operating conditions of high burn-up LWR fuel. Basic mechanisms of fission product release were clarified. For safety studies, the specific heat capacity of molten UO 2 was measured up to 8000 K. Structural and chemical changes limit the operation of mixed nitride fuels to-centre temperatures below 2000 K. The Safe Handling of Fuel concentrated on the spread of airborne contamination in accident situations. The nuclear transmutation of long-lived radioactive waste constituents and the recycling of self- generated Pu was studied. The effects of long- term storage on leachibility and mechanical stability of waste glasses was simulated. UO 2 corrosion in aqueous solutions, for spent fuel storage possibilities, was studied. Neptunium and plutonium compounds were prepared and characterised for solid state measurements. Band structures of actinide intermetallics were calculated. Photoelectron spectroscopy was performed with PuSe and UA1Ni and high-pressure phases as well as compressibilities were determined for PuO 2 , PuSe, Pm, and a Pm-Sm alloy. The pressure dependence of the optical reflectivity was measured for several compounds of U and Th. The effectiveness of acoustic aerosol agglomeration was confirmed. Analytical work for the Commission's Safeguards Directorate is continued in collaboration. A robotized system for the preparation and conditioning of samples from a reprocessing plant for mass spectrometry was installed. Major contract Work for Third Parties in 1990 dealt with the study of dissolution characteristics of high burn-up fuel, the preparation of minor actinide alloys, production of alpha-emitting nuclides for radio-therapy, and the transfer of fuel pin codes

United States Transuranium Registry annual report, October 1, 1980-October 1, 1981 to Human Health and Assessments Division, US Department of Energy

International Nuclear Information System (INIS)

Breitenstein, B.D. Jr.; Heid, K.R.; Swint, M.J.

1982-01-01

The Registry initiates and supports programs at the various sites, where significant numbers of transuranic workers are employed, to conduct interviews and secure medical, health physics and autopsy releases. Terminated employees, not previously contacted, are encouraged to participate in the Registry program. This effort requires cooperation from the company administration as well as the medical and health physics staff. For those persons who are not reached through this network, we attempt to reach them through information about the Registry in professional newsletters and publications. Table 1 is a summary of the status of the US Transuranium Registry autopsy program as of September 1981. The need to prove or improve the accuracy of the present in vivo models is of paramount interest to health physicists. The correlation of in vivo measurements with the radiochemical analysis brings the possibilities of increased predictability of whole body deposition closer to reality. The correlation of in vivo with autopsy tissue will aid epidemiological studies to define those observable health effects in the exposed population that should be looked for

United States Transuranium and Uranium Registries. Annual Report, October 1, 1993--September 30, 1994

Energy Technology Data Exchange (ETDEWEB)

Kathren, R.L.; Harwick, L.A. [comps.] [eds.

1995-08-01

This report summarizes the salient activities and progress of the United States Transuranium. and Uranium Registries for the period October 1, 1993 through September 30, 1994, along with details of specific programs areas including the National Human Radiobiology Tissue Repository (NHRTR) and tissue radiochemistry analysis project. Responsibility for tissue radioanalysis was transferred from Los Alamos National Laboratory to Washington State University in February 1994. The University of Washington was selected as the Quality Assurance/Quality Control laboratory and a three way intercomparison with them and LANL has been initiated. The results of the initial alpha spectrometry intercomparison showed excellent agreement among the laboratories and are documented in full in the Appendices to the report. The NHRTR serves as the initial point of receipt for samples received from participants in the USTUR program. Samples are weighed, divided, and reweighed, and a portion retained by the NHRTR as backup or for use in other studies. Tissue specimens retained in the NHRTR are maintained frozen at -70 C and include not only those from USTUR registrants but also those from the radium dial painter and thorium worker studies formerly conducted by Argonne National Laboratory. In addition, there are fixed tissues and a large collection of histopathology slides from all the studies, plus about 20,000 individual solutions derived from donated tissues. These tissues and tissue related materials are made available to other investigators for legitimate research purposes. Ratios of the concentration of actinides in various tissues have been used to evaluate the biokinetics, and retention half times of plutonium and americium. Retention half times for plutonium in various soft tissues range from 10-20 y except for the testes for which a retention half time of 58 y was observed. For americium, the retention half time in various soft tissues studied was 2.2-3.5 y.

United States Transuranium and Uranium Registries. Annual Report, October 1, 1993--September 30, 1994

International Nuclear Information System (INIS)

Kathren, R.L.; Harwick, L.A.

1995-01-01

This report summarizes the salient activities and progress of the United States Transuranium. and Uranium Registries for the period October 1, 1993 through September 30, 1994, along with details of specific programs areas including the National Human Radiobiology Tissue Repository (NHRTR) and tissue radiochemistry analysis project. Responsibility for tissue radioanalysis was transferred from Los Alamos National Laboratory to Washington State University in February 1994. The University of Washington was selected as the Quality Assurance/Quality Control laboratory and a three way intercomparison with them and LANL has been initiated. The results of the initial alpha spectrometry intercomparison showed excellent agreement among the laboratories and are documented in full in the Appendices to the report. The NHRTR serves as the initial point of receipt for samples received from participants in the USTUR program. Samples are weighed, divided, and reweighed, and a portion retained by the NHRTR as backup or for use in other studies. Tissue specimens retained in the NHRTR are maintained frozen at -70 C and include not only those from USTUR registrants but also those from the radium dial painter and thorium worker studies formerly conducted by Argonne National Laboratory. In addition, there are fixed tissues and a large collection of histopathology slides from all the studies, plus about 20,000 individual solutions derived from donated tissues. These tissues and tissue related materials are made available to other investigators for legitimate research purposes. Ratios of the concentration of actinides in various tissues have been used to evaluate the biokinetics, and retention half times of plutonium and americium. Retention half times for plutonium in various soft tissues range from 10-20 y except for the testes for which a retention half time of 58 y was observed. For americium, the retention half time in various soft tissues studied was 2.2-3.5 y

Strategic review on management and disposal of low- and intermediate-level solid radwastes

International Nuclear Information System (INIS)

Li Xuequn

1993-01-01

An overview on the actual status of solid low- and intermediate-level wastes (L/ILW) management in China is described. Some of the main problems at present are analysed. The strategies on management and disposal of the wastes are discussed in light of systematology. A large amount of solid L/ILW and distilled residual solution to be solidified have been accumulated during the past 30 years development of nuclear industry in China. These wastes, containing fission products, activated products, and uranium and transuranium elements respectively, mainly come from nuclear reactors, spent fuel reprocessing plants, and nuclear fuel fabrication plants. In the century, solid L/ILW and solidified wastes are produced mainly by nuclear industry; but in the next century, solid wastes will be steadily produced mainly from nuclear power plants

Monte-Carlo Application for Nondestructive Nuclear Waste Analysis

Science.gov (United States)

Carasco, C.; Engels, R.; Frank, M.; Furletov, S.; Furletova, J.; Genreith, C.; Havenith, A.; Kemmerling, G.; Kettler, J.; Krings, T.; Ma, J.-L.; Mauerhofer, E.; Neike, D.; Payan, E.; Perot, B.; Rossbach, M.; Schitthelm, O.; Schumann, M.; Vasquez, R.

2014-06-01

, neutron flux distribution. The validation of the measurements simulations with Mont-Carlo transport codes for the design, optimization and data analysis of further P&DGNAA facilities is performed in collaboration with LMN CEA Cadarache. The performance of the prompt gamma neutron activation analysis (PGNAA) for the nondestructive determination of actinides in small samples is investigated. The quantitative determination of actinides relies on the precise knowledge of partial neutron capture cross sections. Up to today these cross sections are not very accurate for analytical purpose. The goal of the TANDEM (Trans-uranium Actinides' Nuclear Data - Evaluation and Measurement) Collaboration is the evaluation of these cross sections. Cross sections are measured using prompt gamma activation analysis facilities in Budapest and Munich. Geant4 is used to optimally design the detection system with Compton suppression. Furthermore, for the evaluation of the cross sections it is strongly needed to correct the results to the self-attenuation of the prompt gammas within the sample. In the framework of cooperation RWTH Aachen University, Forschungszentrum Jülich and the Siemens AG will study the feasibility of a compact Neutron Imaging System for Radioactive waste Analysis (NISRA). The system is based on a 14 MeV neutron source and an advanced detector system (a-Si flat panel) linked to an exclusive converter/scintillator for fast neutrons. For shielding and radioprotection studies the codes MCNPX and Geant4 were used. The two codes were benchmarked in processing time and accuracy in the neutron and gamma fluxes. Also the detector response was simulated with Geant4 to optimize components of the system.

Transuranium radionuclide pollution in the waters of the La Maddalena National Marine Park

International Nuclear Information System (INIS)

Aumento, F.; Le Donne, K.; Eroe, K.

2005-01-01

Following the grounding and subsequent explosion, in October 2003, of a nuclear submarine in the waters of the La Maddalena National Marine Park, fears arose of possible radioactive leakages. However, isotopic analyses on algae showed that the gamma-ray emitting artificial radionuclides that one might expect to leak from a damaged nuclear reactor (such as U-235, I-131, Cs-137) were absent, and that U-238/U-234 activities were in equilibrium with values typical of sea water; this excluded any direct anthropogenic contamination as a result of the accident. We used alpha autoradiographic techniques to detect possible traces of transuranium radionuclides; 160 samples of algae, granites, sea urchins, gastropods, limpets, cuttlefish and jellyfish were collected from the area, as well as from other Mediterranean coastlines and the Baltic Sea. All samples were autoradiographed, and selected samples further analysed by alpha spectrometry. There were no alpha track concentrations above background levels in our control Mediterranean specimens. In the samples from the La Maddalena and Baltic areas two different track distributions were observed:-those homogeneously distributed over the surfaces examined; -groups (10 to over 500) of radially distributed alpha tracks (forming 'star' bursts, or 'hot spots') emanating from point sources. By comparing radionuclide activities measured by alpha spectroscopy with alpha track densities, we extrapolated Pu activities for all samples. About 74% of algae had Pu activities of less than 1Bq/kg and 0.25Bq/kg, 16% had accumulated Pu to levels between 1 and 2Bq/kg, and a very few specimens had concentrations between 2 and 6Bq/kg. Plots showed that alpha tracks and stars concentrate around the northern and eastern margins of the Rada (Basin) di Santo Stefano, sites facing the nuclear submarine base on the eastern shore of the island of Santo Stefano. What is the source of these nuclides: last century's atmospheric nuclear testing, Chernobyl or

Specific contributions of the Dutch progamme ''RAS'' towards accelerator-based transmutation

International Nuclear Information System (INIS)

Abrahams, K.; Franken, W.M.P.; Bultman, J.H.; Heil, J.A.; Koning, A.J.

1994-09-01

Accelerator-based transmutation is being studied by ECN within its general nuclear waste transmutation programme RAS. In this paper the following contributions are presented: (1) Evaluation of cross sections at intermediate energies, within an international frame given by NEA, (2) Cell calculations on the equilibration of transuranium actinides in thermal molten-salt transmuters, (3) Irradiation facilities at the European research reactor HFR in Petten, which have been constructed with the purpose to demonstrate and investigate the transmutation of waste in a high neutron flux, (4) Studies of accelerator-based neutron generating systems to transmute neptunium and technetium, (5) Comparison of several systems on the basis of criteria for successful nuclear waste-management. (orig.)

Specific contributions of the Dutch programme {open_quotes}RAS{close_quotes} towards accelerator-based transmutation

Energy Technology Data Exchange (ETDEWEB)

Abrahams, K.; Franken, W.M.P.; Bultman, J.H. [Netherlands Energy Research Foundation (ECN), Petten (Netherlands)] [and others

1995-10-01

Accelerator-based transmutation is being studied by ECN within its general nuclear waste transmutation programme RAS. In this paper the following contributions are presented: (1) Evaluation of cross sections at intermediate energies, within an international frame given by NEA, (2) Cell calculations on the equilibration of transuranium actinides in thermal molten-salt transmuters, (3) Irradiation facilities at the European research reactor HFR in Petten, which have been constructed with the purpose to demonstrate and investigate the transmutation of waste in a high neutron flux, (4) Studies of accelerator-based neutron generating systems to transmute neptunium and technetium, (5) Comparison of several systems on the basis of criteria for successful nuclear waste-management.

Chemical Technology Division annual progress report for period ending March 31, 1976

Energy Technology Data Exchange (ETDEWEB)

1976-09-01

The status is reported for various research programs including waste management, transuranium-element processing, isotopic separations, preparation of /sup 233/UO/sub 2/, separations chemistry, biomedical technology, environmental studies, coal technology program, actinide oxides and nitrides and carbides, chemical engineering, controlled thermonuclear program, iodine studies, reactor safety, NRC programs, and diffusion of adsorbed species in porous media. Details of these programs are given in topical reports and journal articles. (JSR)

Experimental evaluation of admission and disposition of artificial radionuclides including transuranium elements in agricultural plants

Energy Technology Data Exchange (ETDEWEB)

Kozhakhanov, T.; Lukashenko, S. [Institute of radiation safety and ecology (Kazakhstan)

2014-07-01

Processes of radionuclides migration and transfer to agricultural plants are quite well developed worldwide, but the information on character of accumulation of {sup 241}Am and {sup 239+240}Pu transuranium radionuclides in agricultural plants is still fragmentary. Even in generalized materials of worldwide studies, IAEA guide, accumulation coefficient (AC) can have wide range of values (5-6 orders), no data exists on radionuclides' distribution in different organs of plants and they are given for joined groups of plants and types of soils. That is why the main aim of this work was to obtain basic quantitative parameters of radionuclides' migration in 'soil-plant' system, and firs of all- for transuranium elements.. In 2010 a series of experiments with agricultural plants was started at the territory of the former Semipalatinsk Test Site aimed to investigate entry of artificial radionuclides by crop products in natural climatic conditions. To conduct the experiment for study of coefficient of radionuclides' accumulation by agricultural corps, there was chosen a land spot at the STS territory, characterized by high concentration of radionuclides: {sup 241}Am - n*10{sup 4} Bq/kg, {sup 137}Cs - n*10{sup 3} Bq/kg, {sup 90}Sr - n*10{sup 3} Bq/kg and {sup 239+240}Pu- n*10{sup 5} Bq/kg. As objects of investigation, cultures, cultivated in Kazakhstan have been selected: wheat (Triticum vulgare), barley (Hordeum vulgare), oat (Avena sativa L.), water melon (Citrullus vulgaris), melon (Cucumis melo), potato (Solanum tuberosum), eggplant (Solanum melongena), pepper (Capsicum annuum), tomato (Solanum lycopersicum), sunflower (Helianthus cultus), onion (Allium cepa), carrot (Daucus carota), parsley(Petroselinum vulgare)and cabbage (Brassica oleracea). Investigated plants have been planted within the time limits, recommended for selected types of agricultural plants. Cropping system included simple agronomic and amelioration measures. Fertilizers were not

Savannah River Laboratory dose-to-man model. Appendix A. Deterministic studies - SRL Model

International Nuclear Information System (INIS)

Root, R.W. Jr.

1981-01-01

Solid waste contaminated with radionuclides has been buried at the Savannah River Plant (SRP) burial ground since 1953. The radionuclides include alpha-emitting transuranium (TRU) nuclides, beta- and gamma-emitting activation and fission products, and tritium. To evaluate current operating limits for burial of this waste and to aid planning for the eventual decommissioning of the burial ground, the long-term dose to man from each type of waste must be estimated. The dose projections will provide guidance in choosing alternatives for a burial ground decommissioning plan. Such alternatives may include exhuming selected segments of the waste to reduce the long-lived radionuclide inventory or providing additional backfill over the waste trenches. The sensitivity of dose projections to the length of institutional control over the burial ground will provide an estimate of the minimum time period such control must be maintained

Transuranium Processing Plant semiannual report of production, status, and plans for period ending December 31, 1975

International Nuclear Information System (INIS)

King, L.J.; Bigelow, J.E.; Collins, E.D.

1976-10-01

Between July 1, 1975, and December 31, 1975, maintenance was conducted at TRU for a period of three months, 295 g of curium oxide (enough for approximately 26 HFIR targets) were prepared, 100 mg of high-purity 248 Cm, were separated from 252 Cf that had been purified during earlier periods, 11 HFIR targets were fabricated, and 28 product shipments were made. No changes were made in the chemical processing flowsheets normally used at TRU during this report period. However, three equipment racks were replaced (with two new racks) during this time. In Cubicle 6, the equipment replaced was that used to decontaminate the transplutonium elements from rare earth fission products and to separate curium from the heavier elements by means of the LiCl-based anion-exchange process. In Cubicle 5, the equipment used to separate the transcurium elements by high-pressure ion exchange and to purify berkelium by batch solvent extraction was replaced. Two neutron sources were fabricated, bringing the total fabricated to 79. One source that had been used in a completed project was returned to the TRU inventory and is available for reissue. Three sources, for which no further use was foreseen, were processed to isolate and recover the ingrown 248 Cm and the residual 252 Cf. Eight pellets, each containing 100 μg of high-purity 248 Cm were prepared for irradiation in HFIR to study the production of 250 Cm. The values currently being used for transuranium element decay data and for cross-section data in planning irradiation-processing cycles, calculating production forecasts, and assaying products are tabulated

Investigation of the solution properties of the transuranium elements. Final report, July 1, 1979-September 30, 1984

International Nuclear Information System (INIS)

Ensor, D.D.

1984-01-01

This final report summarizes the significant results obtained during our investigation of the fundamental solution properties of the transuranium elements for the period July 1, 1979 to September 30, 1984. Primary interest of the project was the development of improved separation methods for the trivalent actinide elements from each other and from the chemically similar trivalent lanthanide elements using solvent extraction techniques. Two different synergistic systems were investigated. The combination of dialkynaphthalenesulfonic acids with a crown ether or an oxime was an attempt to combine the excellent ion exchange properties of the sulfonic extractant with a synergistic agent which would improve the selectivity of the extraction system. The results showed that the presence of the crown ether improved the extraction of the light lanthanides by approximately 50% while the heavy lanthanides were unaffected. The use of the oxime in combination with the sulfonic acid extractant showed significant enhancement for all metal ions studied but little, if any, selectivity. The use of novel oxygen donors as synergistic agents in combination with thenoyltrifluoroacetone provided significant enhancement for the extraction of trivalent lanthanides and actinides. The data showed the best selectivity was obtained using a linear polyether as the synergistic agent. The crown ether and the cryptand showed significant synergistic capabilities but lacked selectivity due to their rigid cavities. The results of this study indicate that the linear polyether is more promising as a synergistic agent because of its flexibility and ease of chemical modification of the end groups. 10 figures, 5 tables

Twenty years of chemistry associated with the needs and utilization of nuclear reactors at the 'Boris Kidric' Institute of nuclear sciences, Vinca, Yugoslavia

International Nuclear Information System (INIS)

1969-01-01

This publication covers nine review papers on the following topics related to the needs and utilization of nuclear reactors in the Boris Kidric Institute of nuclear sciences during previous twenty years: radiochemistry, hot atom chemistry, isotope production, spent nuclear fuel reprocessing, chemistry of transuranium elements; liquid radioactive waste processing, purification of reactor coolant water by inorganic ion exchangers, research related to deuterium concentration processes, and chemical dosimetry at the RA reactor [sr

Chemistry Division: Annual progress report for period ending March 31, 1987

International Nuclear Information System (INIS)

1987-08-01

This report is divided into the following sections: coal chemistry; aqueous chemistry at high temperatures and pressures; geochemistry of crustal processes to high temperatures and pressures; chemistry of advanced inorganic materials; structure and dynamics of advanced polymeric materials; chemistry of transuranium elements and compounds; separations chemistry; reactions and catalysis in molten salts; surface science related to heterogeneous catalysis; electron spectroscopy; chemistry related to nuclear waste disposal; computational modeling of security document printing; and special topics

Cleanex process: a versatile solvent extraction process for recovery and purification of lanthanides, americium, and curium

International Nuclear Information System (INIS)

Bigelow, J.E.; Collins, E.D.; King, L.J.

1979-01-01

At a concentration of 1 M in straight-chain hydrocarbon diluent, HDEHP will extract americium, curium, and other trivalent actinide and lanthanide elements from dilute acid or salt solutions. The solute is back-extracted with more concentrated acid, either nitric or hydrochloric. The process has been used in the continuous, countercurrent mode, but its greatest advantage arises in batch extractions where the excess acid can be titrated with NaOH to produce a final acidity of about 0.03 M. Under these conditions, 99% recovery can be achieved, usually in one stage. Cleanex was used on the 50-liter scale at the Transuranium Processing Plant at Oak Ridge for 12 years to provide a broad spectrum cleanup to transuranium elements before applying more sophisticated techniques for separating individual products. The process is also used routinely to recover excessive losses of curium and/or californium from plant waste streams. The solvent system is relatively resistant to radiation damage, being usable up to 200 W-h/liter

Transmutation of transuranium elements in a gas-cooled accelerator-driven system

International Nuclear Information System (INIS)

Biss, Klaus Hendrik

2014-01-01

The peaceful usage of nuclear energy by light and boiling water reactors is connected with a buildup of long-lived high-level radioactive waste. Compared to the direct disposal, partitioning and transmutation (P and T) is considered as an effective way to reduce this waste in its quantity by converting it into short-lived radio nuclides. By that the long term radiotoxicity is reduced compared to direct disposal. Subcritical systems, which are powered by spallation processes for free neutron production to maintain the nuclear chain reaction, allow a target-oriented transmutation. As a subcritical system a gas-cooled accelerator driven system (ADS) for transmutation of transuranic elements has been modeled in this thesis to evaluate the reduction of the radio toxicity by P and T. The simulation of neutron-physical processes is based on the Monte Carlo computer program MCNPX. The development of an equilibrium core made it possible to study the transmutation and operating behavior for several fuel variations in a magnesium oxide matrix and develop a simplified burnup method. Americium as part of the fuel has a stabilizing effect on the neutron multiplication due to its conversion into plutonium during the operation. Thorium was investigated as an alternative matrix for the fuel in order to replicate the stabilizing effect of americium by the conversion of thorium in 233 U. By that a consistent operating cycle in the later P and T-process is ensured. Calculation of the nuclide composition at the end of a P and T-process leads to an expansion of the mathematical description of the mass reduction (transmutation efficiency) by the material located in the reactor. The achieved transmutation efficiency with the investigated ADS is 98.8 %. The transmutation time was examined with different operating strategies regarding the number, size and thermal power of use of transmutation facilities to determine the effort for the P and T-process depending on efficiency. It turns out

Chemistry Division: Annual progress report for period ending March 31, 1987

Energy Technology Data Exchange (ETDEWEB)

1987-08-01

This report is divided into the following sections: coal chemistry; aqueous chemistry at high temperatures and pressures; geochemistry of crustal processes to high temperatures and pressures; chemistry of advanced inorganic materials; structure and dynamics of advanced polymeric materials; chemistry of transuranium elements and compounds; separations chemistry; reactions and catalysis in molten salts; surface science related to heterogeneous catalysis; electron spectroscopy; chemistry related to nuclear waste disposal; computational modeling of security document printing; and special topics. (DLC)

Calibration of whole-body counters for transuranic radionuclides by using total-body donations to the United States Transuranium Registry

International Nuclear Information System (INIS)

Palmer, H.E.; Heid, K.R.; Breitenstein, B.D.; Durbin, P.W.; McInroy, J.F.

1985-01-01

One of the many benefits of the whole-body donation programme of the United States Transuranium Registry is the calibration of whole-body counters by measuring a donated body containing radioactivity before radiochemical analysis of the body occurs. These measurements have provided the best existing calibration factors for measuring 241 Am and 239 Pu in the skeleton of living people. In one case where the body contained an easily measurable quantity of 241 Am, the 241 Am content was found to be the same for identical bones on the right and left sides of the body. The bones from the right side of the body and every other vertebrae were radiochemically analysed and the bones from the left side were reserved. These latter have a known quantity of naturally distributed 241 Am based on the analysis of bones from the right side. These reserved bones are being incorporated into tissue equivalent body parts for future calibrations and interlaboratory comparisons. The measurements on the total body and the reserved bones have already been very useful in determining the contribution of skeletal activity to that of lung measurements and determining a calibration factor for measuring 239 Pu deposited in the skeleton. In the future it is planned to periodically make in vivo measurements on those people participating in the total-body donation programme so that calibration factors can be obtained for lung and liver content after subsequent analysis of these tissues. (author)

Composite reprocessing of spent nuclear fuel - is a way to low waste nuclear power

International Nuclear Information System (INIS)

Kosyakov, Valentin

2005-01-01

Further development of nuclear power in many respects depend on the solution of the problems connected to high level radioactive wastes (HLRW), containing highly toxic long-lived radionuclides. Long-term controlled storage of HLRW manages expensively and any advanced technology of reprocessing of spent nuclear fuel (SNF), besides recovery of the basic products, should be aimed at the reduction of this waste amount. However, the existing SNF reprocessing technology, using PUREX - process, is aimed only at extraction of uranium and plutonium, considering the remaining fraction (other transuranium elements and all fission products) as HLRW. In this work an attempt is made to give quantitative and qualitative characteristics to the isotopes and the elements which are included in the composition of HLRW after 15-years storage. Depending on the radiation properties of the isotopes included, these elements were divided into three categories: 1. The elements represented by only stable isotopes; 2. The elements represented by mostly low radioactive isotopes; 3. The elements represented by highly toxic long-lived radionuclides. As a result it appeared, that the weight percentage of the elements of the first, the second and the third categories in HLRW was: 60, 25 and 15% respectively. It means, that the amount of the real HLRW to be disposed in a deep geological repository could be reduced at least by a factor of 6, if to recover completely only 7 most dangerous elements (Sr, J, Cs, Sm, Np, Am and Cm) from the solution remaining after extraction of uranium and plutonium. Then it is meaningful to recover the elements of the first category from the remaining mix. As the main part of this fraction is represented by rare earth elements and noble metals, which can easily find many useful application. (author)

Experimental thermochemistry of neptunium oxides: Np2O5 and NpO2

Science.gov (United States)

Zhang, Lei; Dzik, Ewa A.; Sigmon, Ginger E.; Szymanowski, Jennifer E. S.; Navrotsky, Alexandra; Burns, Peter C.

2018-04-01

Neptunium (Np) compounds are important in the nuclear fuel cycle because of the buildup and long half-life (2.14 Ma) of Np-237 in nuclear waste, especially during long-term disposal in a geological repository. Neptunium in environmental conditions exists mainly in two oxidation states (+5 and + 4) and can substitute for uranium and/or rare earths in solid phases. Yet thermochemical data for solid neptunium compounds are scarce, despite being critical for evaluating the environmental transport of this radioactive and toxic element. Although high temperature oxide melt solution calorimetry has proven very useful in obtaining thermodynamic data for the formation of uranium and thorium oxide materials, it has not yet been applied to transuranium compounds. Continuing a program at Notre Dame to study the thermodynamics of transuranium compounds, we report the first determination of the enthalpies of drop solution of well-characterized neptunium oxides (Np2O5 and NpO2) using oxide melt solution calorimetry in molten sodium molybdate solvent at 973 K. The enthalpy of the decomposition reaction, Np2O5(cr) = 2NpO2(cr) + 1/2O2(g) at 298 K, is determined to be 7.70 ± 5.86 kJ/mol, and this direct measurement is consistent with existing thermodynamic data. The calorimetric methodology is straightforward and produces reliable data using milligram quantities of radioactive materials, and can be applied to many other transuranium compounds.

Chemistry of transuranium elements and compounds

International Nuclear Information System (INIS)

Anon.

1979-01-01

Half-wave potentials show no evidence for the existence of Md(I) in aqueous solution. Microchemical studies of anhydrous transplutonium halides used absorption spectroscopy and x-ray diffraction. Five transplutonium elements were prepared. Superconductivity was observed and characterzed in Am metal. The heats of vaporization of 243 Am and 249 Cf were determined to be 60 and 46.9 kcal/mol, respectively. The solution heat of Cm metal in 1 N Hcl at 298 0 K is 606.4 +- 1.8 kJ/mol. Some chalcogenides and pnictides of Cm, Bk, and Cf were prepared, and the crystal structure of Am Te/sub 2-x/ was refined. Behavior of 243 Am and several tellurides under high pressure was studied. Structure of a cryptate of Sm was studied; its formula is [Sm(No 3 )(C 18 H 36 N 2 O 6 )][Sm(NO 3 ) 5 ].H 2 O. X-ray fluorescence cross sections are given as function of atomic number, for the 59.6 keV photon from 2 4 1 Am. A sensitive micromagnetic susceptometer was constructed and calibrated for actinides. A spectroelectrochemical study (absorption spectra recorded at various applied potentials) was made of U and Eu in aqueous solution. Two studies were carried out in connection with nuclear waste isolation: adsorption of rare earths, actinides, and alkali metals on clay minerals and radiation damage to kaolin and attapulgite from 253 Es. A new method is being developed for U exploration. 13 figures, 5 tables

Sampling and analysis of the inactive waste tanks TH-2, WC-1, and WC-15

International Nuclear Information System (INIS)

Autrey, J.W.; Keller, J.M.; Griest, W.H.; Botts, J.L.; Schenley, R.L.; Sipe, M.A.

1992-02-01

Thirty-eight inactive liquid low-level radioactive waste tanks are currently managed by the Environmental Restoration Program of Oak Ridge National Laboratory. The contents of these tanks are to be characterized in preparation for future corrective actions and remediation activities as part of compliance with the pending Federal Facility Agreement for the Oak Ridge Reservation. Twenty-nine of these tanks were sampled and analyzed in 1989. Three of the tanks (TH-2, WC-1, and WC-15) were not accessible from the surface and thus were not sampled until 1990. This report presents the sampling and analytical results of that campaign. All three tanks in this report had negligible regulatory organic compounds in the samples that were collected. There were no US Environmental Protection Agency (EPA) Target Compound List (TCL) constituents for volatile organics detected in any of the aqueous samples. The only semivolatile organics detected were 2-chlorophenol (52 μg/L) in tank TH-2 and dichloroethane (14--15 μg/L) and diethyl either (15--17 μg/L) in tank WC-15. A thin oil layer was discovered floating on top of the aqueous contents in tank WC-15. The analysis of the oil layer detected no volatile organics and showed only one EPA TCL constituent, di-n-butylphthalate, at 1900 μg/L. Low levels of Resource Conservation and Recovery Act (RCRA) metals were observed in the samples from tank TH-2, but only the mercury level exceeded the RCRA limit. Samples from tank WC-1 had elevated levels of the RCRA metals barium, chromium, and lead. There were also finely suspended particles in one of the samples from tank WC-1, which was filtered and analyzed separately. This solid fines have levels of transuranium elements 238 Pu and 241 Am high enough to classified as transuranic waste

Evaluation of conceptual flowsheets for incorporating Light Water Reactor (LWR) fuel materials in an advanced nuclear fuel cycle

International Nuclear Information System (INIS)

Bell, J.T.; Burch, W.D.; Collins, E.D.; Forsberg, C.W.; Prince, B.E.; Bond, W.D.; Campbell, D.O.; Delene, J.G.; Mailen, J.C.

1990-08-01

A preliminary study by a group of experts at ORNL has generated and evaluated a number of aqueous and non-aqueous flowsheets for recovering transuranium actinides from LWR fuel for use as fuel in an LMR and, at the same time, for transmutation of the wastes to less hazardous materials. The need for proliferation resistance was a consideration in the flowsheets. The current state of development of the flowsheets was evaluated and recommendations for additional study were made. 3 refs., 6 figs

Spent fuel reprocessing method

International Nuclear Information System (INIS)

Shoji, Hirokazu; Mizuguchi, Koji; Kobayashi, Tsuguyuki.

1996-01-01

Spent oxide fuels containing oxides of uranium and transuranium elements are dismantled and sheared, then oxide fuels are reduced into metals of uranium and transuranium elements in a molten salt with or without mechanical removal of coatings. The reduced metals of uranium and transuranium elements and the molten salts are subjected to phase separation. From the metals of uranium and transuranium elements subjected to phase separation, uranium is separated to a solid cathode and transuranium elements are separated to a cadmium cathode by an electrolytic method. Molten salts deposited together with uranium to the solid cathode, and uranium and transuranium elements deposited to the cadmium cathode are distilled to remove deposited molten salts and cadmium. As a result, TRU oxides (solid) such as UO 2 , Pu 2 in spent fuels can be reduced to U and TRU by a high temperature metallurgical method not using an aqueous solution to separate them in the form of metal from other ingredients, and further, metal fuels can be obtained through an injection molding step depending on the purpose. (N.H.)

Waste management, waste resource facilities and waste conversion processes

International Nuclear Information System (INIS)

Demirbas, Ayhan

2011-01-01

In this study, waste management concept, waste management system, biomass and bio-waste resources, waste classification, and waste management methods have been reviewed. Waste management is the collection, transport, processing, recycling or disposal, and monitoring of waste materials. A typical waste management system comprises collection, transportation, pre-treatment, processing, and final abatement of residues. The waste management system consists of the whole set of activities related to handling, treating, disposing or recycling the waste materials. General classification of wastes is difficult. Some of the most common sources of wastes are as follows: domestic wastes, commercial wastes, ashes, animal wastes, biomedical wastes, construction wastes, industrial solid wastes, sewer, biodegradable wastes, non-biodegradable wastes, and hazardous wastes.

Improvements in or relating to the treatment of substances

International Nuclear Information System (INIS)

Hardwick, W.H.; Gayler, R.

1981-01-01

This relates to the treatment of substances, one application being the solidification and vitrification of radioactive wastes for the purposes of handling and storage. The process includes the use of microwave radiation to produce a fusible dried product from solution or slurry or to fuse this product or for both stages. Uranium, transuranium elements and fission products from reprocessing procedures can be incorporated into ceramic and glass-like solid materials using this method. Radioactive wastes containing neutron poisons can also be treated. An example given is for the treatment of a magnesium compound from fuel element cooling pond waters. Several variations, including drying the solution on a glass fibre tape or wick or in a stainless steel vessel are detailed. (U.K.)

About possibility of creation of ecologically pure, safe nuclear power plants on the basis of high-effective resonant neutron interaction with splitting substances

International Nuclear Information System (INIS)

Irdyncheyev, L.A.; Malofeyev, A.M.; Frid, E.S.; Abramov, E.P.

1993-01-01

Currently the most important problem in nuclear engineering is creation of ecologically pure, safe nuclear power plants in the context of real danger of global ecological pollution of the environment with long-lived fission products and the resultant transuranium nuclides. The problem can be solved by creating nuclear power plants on the basis of high-effective resonant interaction (HERI). Such power plants would provide the total cycle, including nuclear fuel production (Plutonium-239 from Uranium-238), combustion and waste products salvaging by way of transformation of radioactive nuclides into stable isotopes

Chemistry Division annual progress report for period ending April 30, 1993

Energy Technology Data Exchange (ETDEWEB)

Poutsma, M.L.; Ferris, L.M.; Mesmer, R.E.

1993-08-01

The Chemistry Division conducts basic and applied chemical research on projects important to DOE`s missions in sciences, energy technologies, advanced materials, and waste management/environmental restoration; it also conducts complementary research for other sponsors. The research are arranged according to: coal chemistry, aqueous chemistry at high temperatures and pressures, geochemistry, chemistry of advanced inorganic materials, structure and dynamics of advanced polymeric materials, chemistry of transuranium elements and compounds, chemical and structural principles in solvent extraction, surface science related to heterogeneous catalysis, photolytic transformations of hazardous organics, DNA sequencing and mapping, and special topics.

Waste management - sewage - special wastes

International Nuclear Information System (INIS)

1987-01-01

The 27 papers represent a cross-section of the subject waste management. Particular attention is paid to the following themes: waste avoidance, waste product utilization, household wastes, dumping technology, sewage sludge treatments, special wastes, seepage from hazardous waste dumps, radioactive wastes, hospital wastes, purification of flue gas from waste combustion plants, flue gas purification and heavy metals, as well as combined sewage sludge and waste product utilization. The examples given relate to plants in Germany and other European countries. 12 papers have been separately recorded in the data base. (DG) [de

Determination of 236U and transuranium elements in depleted uranium ammunition by α-spectrometry and ICP-MS

International Nuclear Information System (INIS)

Desideri, D.; Meli, M.A.; Roselli, C.; Testa, C.; Boulyga, S.F.; Becker, J.S.

2002-01-01

It is well known that ammunition containing depleted uranium (DU) was used by NATO during the Balkan conflict. To evaluate the origin of DU (the enrichment of natural uranium or the reprocessing of spent nuclear fuel) it is necessary to directly detect the presence of activation products ( 236 U, 239 Pu, 240 Pu, 241 Am, and 237 Np) in the ammunition. In this work the analysis of actinides by α-spectrometry was compared with that by inductively coupled plasma mass spectrometry (ICP-MS) after selective separation of ultratraces of transuranium elements from the uranium matrix. 242 Pu and 243 Am were added to calculate the chemical yield. Plutonium was separated from uranium by extraction chromatography, using tri-n-octylamine (TNOA), with a decontamination factor higher than 10 6 ; after elution plutonium was determined by ICP-MS ( 239 Pu and 240 Pu) and α-spectrometry ( 239+240 Pu) after electroplating. The concentration of Pu in two DU penetrator samples was 7 x 10 -12 g g -1 and 2 x 10 -11 g g -1 . The 240 Pu/ 239 Pu isotope ratio in one penetrator sample (0.12±0.04) was significantly lower than the 240 Pu/ 239 Pu ratios found in two soil samples from Kosovo (0.35±0.10 and 0.27±0.07). 241 Am was separated by extraction chromatography, using di(2-ethylhexyl)phosphoric acid (HDEHP), with a decontamination factor as high as 10 7 . The concentration of 241 Am in the penetrator samples was 2.7 x 10 -14 g g -1 and -15 g g -1 . In addition 237 Np was detected at ultratrace levels. In general, ICP-MS and α-spectrometry results were in good agreement.The presence of anthropogenic radionuclides ( 236 U, 239 Pu, 240 Pu, 241 Am, and 237 Np) in the penetrators indicates that at least part of the uranium originated from the reprocessing of nuclear fuel. Because the concentrations of radionuclides are very low, their radiotoxicological effect is negligible. (orig.)

Determination of (236)U and transuranium elements in depleted uranium ammunition by alpha-spectrometry and ICP-MS.

Science.gov (United States)

Desideri, D; Meli, M A; Roselli, C; Testa, C; Boulyga, S F; Becker, J S

2002-11-01

It is well known that ammunition containing depleted uranium (DU) was used by NATO during the Balkan conflict. To evaluate the origin of DU (the enrichment of natural uranium or the reprocessing of spent nuclear fuel) it is necessary to directly detect the presence of activation products ((236)U, (239)Pu, (240)Pu, (241)Am, and (237)Np) in the ammunition. In this work the analysis of actinides by alpha-spectrometry was compared with that by inductively coupled plasma mass spectrometry (ICP-MS) after selective separation of ultratraces of transuranium elements from the uranium matrix. (242)Pu and (243)Am were added to calculate the chemical yield. Plutonium was separated from uranium by extraction chromatography, using tri- n-octylamine (TNOA), with a decontamination factor higher than 10(6); after elution plutonium was determined by ICP-MS ((239)Pu and (240)Pu) and alpha-spectrometry ((239+240)Pu) after electroplating. The concentration of Pu in two DU penetrator samples was 7 x 10(-12) g g(-1) and 2 x 10(-11) g g(-1). The (240)Pu/(239)Pu isotope ratio in one penetrator sample (0.12+/-0.04) was significantly lower than the (240)Pu/(239)Pu ratios found in two soil samples from Kosovo (0.35+/-0.10 and 0.27+/-0.07). (241)Am was separated by extraction chromatography, using di(2-ethylhexyl)phosphoric acid (HDEHP), with a decontamination factor as high as 10(7). The concentration of (241)Am in the penetrator samples was 2.7 x 10(-14) g g(-1) and <9.4 x 10(-15) g g(-1). In addition (237)Np was detected at ultratrace levels. In general, ICP-MS and alpha-spectrometry results were in good agreement. The presence of anthropogenic radionuclides ((236)U, (239)Pu,(240)Pu, (241)Am, and (237)Np) in the penetrators indicates that at least part of the uranium originated from the reprocessing of nuclear fuel. Because the concentrations of radionuclides are very low, their radiotoxicological effect is negligible.

Specific sequestering agents for iron and the actinides

Energy Technology Data Exchange (ETDEWEB)

Raymond, K.N.

1983-06-01

The transuranium actinide ions represent one unique environmental hazard associated with the waste of the nuclear power industry. A major component associated with that waste and a potential hazard is plutonium. The synthesis of metal-ion-specific complexing agents for ions such as Pu(IV) potentially represents a powerful new approach to many of the problems posed by waste treatment. This document is a progress report of a rational approach to the synthesis of such chelating agents based on the similarities of Pu(IV) and Fe(III), the structures of naturally-occurring complexing agents which are highly specific for Fe(III), and the incorporation of the same kinds of ligating groups present in the iron complexes to make octadentate complexes highly specific for plutonium. Both thermodynamic and animal test results indicate that a relatively high degree of success has already been achieved in this aim.

Calculation of multidimensional potential energy surfaces for even-even transuranium nuclei: systematic investigation of the triaxiality effect on the fission barrier

Science.gov (United States)

Chai, Qing-Zhen; Zhao, Wei-Juan; Liu, Min-Liang; Wang, Hua-Lei

2018-05-01

Static fission barriers for 95 even-even transuranium nuclei with charge number Z = 94–118 have been systematically investigated by means of pairing self-consistent Woods-Saxon-Strutinsky calculations using the potential energy surface approach in multidimensional (β 2, γ, β 4) deformation space. Taking the heavier 252Cf nucleus (with the available fission barrier from experiment) as an example, the formation of the fission barrier and the influence of macroscopic, shell and pairing correction energies on it are analyzed. The results of the present calculated β 2 values and barrier heights are compared with previous calculations and available experiments. The role of triaxiality in the region of the first saddle is discussed. It is found that the second fission barrier is also considerably affected by the triaxial deformation degree of freedom in some nuclei (e.g., the Z=112–118 isotopes). Based on the potential energy curves, general trends of the evolution of the fission barrier heights and widths as a function of the nucleon numbers are investigated. In addition, the effects of Woods-Saxon potential parameter modifications (e.g., the strength of the spin-orbit coupling and the nuclear surface diffuseness) on the fission barrier are briefly discussed. Supported by National Natural Science Foundation of China (11675148, 11505157), the Project of Youth Backbone Teachers of Colleges and Universities of Henan Province (2017GGJS008), the Foundation and Advanced Technology Research Program of Henan Province (162300410222), the Outstanding Young Talent Research Fund of Zhengzhou University (1521317002) and the Physics Research and Development Program of Zhengzhou University (32410017)

Purification of alkaline solutions and wastes from actinides and technetium by coprecipitation with some carriers using the method of appearing reagents: Final Report

International Nuclear Information System (INIS)

Peretrukhin, V.F.; Silin, V.I.; Kareta, A.V.; Gelis, A.V.; Shilov, V.P.; German, K.E.; Firsova, E.V.; Maslennikov, A.G.; Trushina, V.E.

1998-09-01

The coprecipitation of transuranium elements (TRU) and technetium from alkaline solutions and from simulants of Hanford Site tank wastes has been studied in reducing and oxidizing conditions on uranium(IV,VI) hydroxocompounds, tetraalkylammonium perrhenate and perchlorate, and on hydroxides of Fe(III), Co(III), Mn(II), and Cr(III) using the method of appearing reagents (MAR). Coprecipitations in alkaline solution have been shown to give high decontamination factors (DF) at low content of carrier and in the presence of high salt concentrations. Uranium(IV) hydroxide in concentrations higher than 3 x 10 -3 M coprecipitates Pu and Cm in any oxidation state from 0.2 to 4 M NaOH with DFs of 110 to 1000 and Np and Tc with DFs of 51 to 176. Technetium (VII) coprecipitates with (5 to 8) x 10 -4 M tetrabutylammonium (TBA) perrhenate in 0.01 to 0.02 M TBA hydroxide from 0.5 to 1.5 M NaOH to give DFs of 150 to 200. Coprecipitations of Np and Pu with Co(OH) 3 , Fe(OH) 3 , Cr(OH) 3 , and Mn(OH) 2 obtained by the MAR from precursors in the range from pH 10.5 to 0.4 M NaOH give DFs from 80 to 400

Transuranium Removal from Hanford AN-107 Simulants using Sodium Permanganate and Calcium

International Nuclear Information System (INIS)

Wilmarth, W.

2000-01-01

Removal of strontium from the complexant-containing wastes (AN-102 and AN-107) had previously been acceptably accomplished by isotopic dilution. Actinide removal using ferric co-precipitation, however, was very problematic from both a processing and a decontamination standpoint. Therefore, a series of tests were performed to identify other potential actinide removal agents and to test these agents at various concentrations

The waste-to-energy framework for integrated multi-waste utilization: Waste cooking oil, waste lubricating oil, and waste plastics

Energy Technology Data Exchange (ETDEWEB)

Singhabhandhu, Ampaitepin; Tezuka, Tetsuo [Energy Economics Laboratory, Department of Socio-Environmental Energy Science, Graduate School of Energy Science, Kyoto University, Yoshida-honmachi, Sakyo-ku, Kyoto 606-8501 (Japan)

2010-06-15

Energy generation by wastes is considered one method of waste management that has the benefit of energy recovery. From the waste-to-energy point of view, waste cooking oil, waste lubricating oil, and waste plastics have been considered good candidates for feedstocks for energy conversion due to their high heating values. Compared to the independent management of these three wastes, the idea of co-processing them in integration is expected to gain more benefit. The economies of scale and the synergy of co-processing these wastes results in higher quality and higher yield of the end products. In this study, we use cost-benefit analysis to evaluate the integrated management scenario of collecting the three wastes and converting them to energy. We report the total heat of combustion of pyrolytic oil at the maximum and minimum conversion rates, and conduct a sensitivity analysis in which the parameters of an increase of the electricity cost for operating the process and increase of the feedstock transportation cost are tested. We evaluate the effects of economy of scale in the case of integrated waste management. We compare four cases of waste-to-energy conversion with the business as usual (BAU) scenario, and our results show that the integrated co-processing of waste cooking oil, waste lubricating oil, and waste plastics is the most profitable from the viewpoints of energy yield and economics. (author)

Application of annular centrifugal contactors in the hot test of the improved total partitioning process for high level liquid waste.

Science.gov (United States)

Duan, Wuhua; Chen, Jing; Wang, Jianchen; Wang, Shuwei; Feng, Xiaogui; Wang, Xinghai; Li, Shaowei; Xu, Chao

2014-08-15

High level liquid waste (HLLW) produced from the reprocessing of the spent nuclear fuel still contains moderate amounts of uranium, transuranium (TRU) actinides, (90)Sr, (137)Cs, etc., and thus constitutes a permanent hazard to the environment. The partitioning and transmutation (P&T) strategy has increasingly attracted interest for the safe treatment and disposal of HLLW, in which the partitioning of HLLW is one of the critical technical issues. An improved total partitioning process, including a TRPO (tri-alkylphosphine oxide) process for the removal of actinides, a CESE (crown ether strontium extraction) process for the removal of Sr, and a CECE (calixcrown ether cesium extraction) process for the removal of Cs, has been developed to treat Chinese HLLW. A 160-hour hot test of the improved total partitioning process was carried out using 72-stage 10-mm-dia annular centrifugal contactors (ACCs) and genuine HLLW. The hot test results showed that the average DFs of total α activity, Sr and Cs were 3.57 × 10(3), 2.25 × 10(4) and 1.68 × 10(4) after the hot test reached equilibrium, respectively. During the hot test, 72-stage 10-mm-dia ACCs worked stable, continuously with no stage failing or interruption of the operation. Copyright © 2014 Elsevier B.V. All rights reserved.

Transuranium processing plant report of production, status, and plans for the period October 1, 1978-September 30, 1980

International Nuclear Information System (INIS)

King, L.J.; Bigelow, J.E.; Collins, E.D.

1981-08-01

During this period, transuranium elements were obtained from 26 irradiated HFIT targets. The products included 86 mg of 249 Bk, 686 mg of 252 Cf, 3.1 mg of 253 Es, and an estimated 1.4 pg of 257 Fm. In addition, about 326 mg of high-purity 248 Cm was separated from previously purified 252 Cf. One hundred seven product shipments were made from TRU; recipients and the amounts of nuclides shipped are listed in a table. Forty-two standard and two special HFIR targets were fabricated. During the next 18 months, production totals of 110 mg of 249 Bk, 1200 mg of 252 Cf, 5.5 mg of 253 Es, and 2 pg of 257 Fm are anticipated. Also, a total of 225 mg of 248 Cm is expected to be made available. During this report period, a charcoal adsorber system for radioiodine removal was installed, tested, and placed in service. This system serves as a backup to the Hopcalite-charcoal system for adsorption of 131 I from the VOG stream. Seven 252 Cf neutron sources were fabricated during this report period. A total of 100 neutron sources have been fabricated previously at TRU. The original and current contents ( 252 Cf and 248 Cm) of the existing sources and the individuals to whom the sources are currently loaned are listed in a table. In addition to neutron sources, nine fission sources were prepared by electroplating 252 Cf onto platinum disks or foils.Special projects during this report period included (1) purification of two batches of isotopically pure 240 Pu, (2) fabrication of two special HFIR targets, (3) repurification of the residues of the einsteinium product from Campaign 56, (4) production of approx. 235 μg of 250 Cf by irradiation of 249 Bk, (5) radiography of 28 irradiated, stainless steel alloy, fracture-strain specimens, and (6) preparations for the production of 40 μg of 245 Es by irradiation of 253 Es

Waste Sites - Municipal Waste Operations

Data.gov (United States)

NSGIC Education | GIS Inventory — A Municipal Waste Operation is a DEP primary facility type related to the Waste Management Municipal Waste Program. The sub-facility types related to Municipal Waste...

Measurement of penetration depths of plutonium and americium in sediment from the ocean floor

International Nuclear Information System (INIS)

Fried, S.; Friedman, A.; Hines, J.; Sjoblom, R.; Schmitz, G.; Schreiner, F.

1979-01-01

The clay-like sediment covering the ocean floor constitutes the last barrier that shields the biosphere from contamination by radionuclides stemming from the nuclear wastes of a subseabed repository. In the event of a failure of the engineered barriers the mobility of the released radionuclides in the sediment determines the rate and the extent of entry into the water of the ocean. The initial results of measurements designed to determine the mobility of transuranium elements in sediment from the ocean floor are presented. Data indicate very low migration rates and imply strong chemisorptive interaction with the sediment

The synthesis and characterisation of some aliphatic monoamides and diamides

International Nuclear Information System (INIS)

Ruikar, P.B.; Prabhu, D.R.; Mahajan, G.R.; Nagar, M.S.; Nair, G.M.; Subramanian, M.S.

1992-01-01

This report summarises the synthesis and characterisation of several symmetrical, unsymmetrical and branched chain amides which have potential application as alternate extractants to TBP in the Purex Process. Some substituted diamides which have importance in the removal of actinides from transuranium waste have also been synthesised and characterised. The amides contents determined by nonaqueous potentiometric titration indicate a purity of 97-100%. The relative basicity of these amides and diamides have been determined by measuring the equilibrium constants for the uptake of nitric acid by them. The streching frequency of their carbonyl bond has also been listed. (author). 26 refs., 3 tabs

Transmutations of nuclear waste. Progress report RAS programme 1995: Recycling and transmutation of actinides and fission products

International Nuclear Information System (INIS)

Gruppelaar, H.; Cordfunke, E.H.P.; Konings, R.J.M.; Bultman, J.H.; Dodd, D.H.; Franken, W.M.P.; Kloosterman, J.L.; Koning, A.J.; Wichers, V.A.

1996-04-01

This report describes the progress of the Dutch RAS programme on 'Recycling and Transmutation of Actinides and Fission Products' over the year 1995, which is the second year of the 4-year programme 1994-1997. An extensive listing of reports and publications from 1991 to 1995 is given. Highlights in 1995 were: -The completion of the European Strategy Study on Nuclear Waste Transmutation as a result of which the understanding of transmutation of plutonium, minor actinides and long-lived fission products in thermal and fast reactors has been increased significantly. Important ECN contributions were given on Am, 99 Tc and 129 I transmutation options. Follow-up contracts have been obtained for the study of 100% MOX cores and accelerator-based transmutation. - Important progress in the evaluation of CANDU reactors for burning very large amounts of transuranium mixtures in inert matrices. - The first RAS irradiation experiment in the HFR, in which the transmutation of technetium and iodine was examined, has been completed and post-irradiation examination has been started. - A joint proposal of the EFTTRA cooperation for the 4 th Framework Programme of the EU, to demonstrate the feasibility of the transmutation of americium in an inert matrix by an irradiation in the HFR, has been granted. - A bilateral contract with CEA has been signed to participate in the CAPRA programme, and the work in this field has been started. - The thesis work on Actinide Transmutation in Nuclear Reactor Systems was succesfully defended. New PhD studies on Pu burning in HTGR, on nuclear data for accelerator-based systems, and on the SLM-technique for separation of actinides were started. - A review study of the use of the thorium cycle as a means for nuclear waste reduction, has been completed. A follow-up of this work is embedded in an international project for the 4th Framework Programme of the EU. (orig./DG)

Conceptual design study and evaluation of an advanced treatment process applying a submerged combustion technique for spent solvents

International Nuclear Information System (INIS)

Uchiyama, Gunzo; Maeda, Mitsuru; Fijine, Sachio; Chida, Mitsuhisa; Kirishima, Kenji.

1993-10-01

An advanced treatment process based on a submerged combustion technique was proposed for spent solvents and the distillation residues containing transuranium (TRU) nuclides. A conceptual design study and the preliminary cost estimation of the treatment facility applying the process were conducted. Based on the results of the study, the process evaluation on the technical features, such as safety, volume reduction of TRU waste and economics was carried out. The key requirements for practical use were also summarized. It was shown that the process had the features as follows: the simplified treatment and solidification steps will not generate secondary aqueous wastes, the volume of TRU solid waste will be reduced less than one tenth of that of a reference technique (pyrolysis process), and the facility construction cost is less than 1 % of the total construction cost of a future large scale reprocessing plant. As for the low level wastes of calcium phosphate, it was shown that the further removal of β · γ nuclides with TRU nuclides from the wastes would be required for the safety in interim storage and transportation and for the load of shielding. (author)

Waste acceptance and waste loading for vitrified Oak Ridge tank waste

International Nuclear Information System (INIS)

Harbour, J.R.; Andrews, M.K.

1997-01-01

The Office of Science and Technology of the DOE has funded a joint project between the Oak Ridge National Laboratory (ORNL) and the Savannah River Technology Center (SRTC) to evaluate vitrification and grouting for the immobilization of sludge from ORNL tank farms. The radioactive waste is from the Gunite and Associated Tanks (GAAT), the Melton Valley Storage Tanks (MVST), the Bethel Valley Evaporator Service Tanks (BVEST), and the Old Hydrofractgure Tanks (OHF). Glass formulation development for sludge from these tanks is discussed in an accompanying article for this conference (Andrews and Workman). The sludges contain transuranic radionuclides at levels which will make the glass waste form (at reasonable waste loadings) TRU. Therefore, one of the objectives for this project was to ensure that the vitrified waste form could be disposed of at the Waste Isolation Pilot Plant (WIPP). In order to accomplish this, the waste form must meet the WIPP Waste Acceptance Criteria (WAC). An alternate pathway is to send the glass waste forms for disposal at the Nevada Test Site (NTS). A sludge waste loading in the feed of 6 wt percent will lead to a waste form which is non-TRU and could potentially be disposed of at NTS. The waste forms would then have to meet the requirements of the NTS WAC. This paper presents SRTC''s efforts at demonstrating that the glass waste form produced as a result of vitrification of ORNL sludge will meet all the criteria of the WIPP WAC or NTS WAC

Demonstration of innovative partitioning processes for minor actinide recycling from high active waste solutions

International Nuclear Information System (INIS)

Modolo, G.; Wilden, A.; Geist, A.; Malmbeck, R.; Taylor, R.

2014-01-01

The recycling of the minor actinides (MA) using the Partitioning and Transmutation strategy (P and T) could contribute significantly to reducing the volume of high level waste in a geological repository and to decreasing the waste's longterm hazards originating from the long half-life of the actinides. Several extraction processes have been developed worldwide for the separation and recovery of MA from highly active raffinates (HAR, e.g. the PUREX raffinate). A multi-cycle separation strategy has been developed within the framework of European collaborative projects. The multi-cycle processes, on the one hand, make use of different extractants for every single process. Within the recent FP7 European research project ACSEPT (Actinide reCycling by SEParation and Transmutation), the development of new innovative separation processes with a reduced number of cycles was envisaged. In the so-called 'innovative SANEX' concept, the trivalent actinides and lanthanides are co-extracted from the PUREX raffinate by a DIAMEX like process (e.g. TODGA). Then, the loaded solvent is subjected to several stripping steps. The first one concerns selectively stripping the actinides(III) with selective water-soluble ligands (SO3-Ph-BTB), followed by the subsequent stripping of trivalent lanthanides. A more challenging route studied also within our laboratories is the direct actinide(III) separation from a PUREX-type raffinate using a mixture of CyMe 4 BTBP and TODGA as extractants, the so-called One cycle SANEX process. A new approach, which was also studied within the ACSEPT project, is the GANEX (Grouped ActiNide EXtraction) concept addressing the simultaneous partitioning of all transuranium (TRU) elements for their homogeneous recycling in advanced generation IV reactor systems. Bulk uranium is removed in the GANEX 1st cycle, e.g. using a monoamide extractant and the GANEX 2nd cycle then separates the TRU. A solvent composed of TODGA + DMDOHEMA in kerosene has been shown to

TSA waste stream and final waste form composition

International Nuclear Information System (INIS)

Grandy, J.D.; Eddy, T.L.; Anderson, G.L.

1993-01-01

A final vitrified waste form composition, based upon the chemical compositions of the input waste streams, is recommended for the transuranic-contaminated waste stored at the Transuranic Storage Area of the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. The quantities of waste are large with a considerable uncertainty in the distribution of various waste materials. It is therefore impractical to mix the input waste streams into an ''average'' transuranic-contaminated waste. As a result, waste stream input to a melter could vary widely in composition, with the potential of affecting the composition and properties of the final waste form. This work examines the extent of the variation in the input waste streams, as well as the final waste form under conditions of adding different amounts of soil. Five prominent Rocky Flats Plant 740 waste streams are considered, as well as nonspecial metals and the ''average'' transuranic-contaminated waste streams. The metals waste stream is the most extreme variation and results indicate that if an average of approximately 60 wt% of the mixture is soil, the final waste form will be predominantly silica, alumina, alkaline earth oxides, and iron oxide. This composition will have consistent properties in the final waste form, including high leach resistance, irrespective of the variation in waste stream. For other waste streams, much less or no soil could be required to yield a leach resistant waste form but with varying properties

Classification of solid wastes as non-radioactive wastes

International Nuclear Information System (INIS)

Suzuki, Masahiro; Tomioka, Hideo; Kamike, Kozo; Komatu, Junji

1995-01-01

The radioactive wastes generally include nuclear fuels, materials contaminated with radioactive contaminants or neutron activation to be discarded. The solid wastes arising from the radiation control area in nuclear facilities are used to treat and stored as radioactive solid wastes at the operation of nuclear facilities in Japan. However, these wastes include many non-radioactive wastes. Especially, a large amount of wastes is expected to generate at the decommissioning of nuclear facilities in the near future. It is important to classify these wastes into non-radioactive and radioactive wastes. The exemption or recycling criteria of radioactive solid wastes is under discussion and not decided yet in Japan. Under these circumstances, the Nuclear Safety Committee recently decided the concept on the category of non-radioactive waste for the wastes arising from decommissioning of nuclear facilities. The concept is based on the separation and removal of the radioactively contaminated parts from radioactive solid wastes. The residual parts of these solid wastes will be treated as non-radioactive waste if no significant difference in radioactivity between the similar natural materials and materials removed the radioactive contaminants. The paper describes the procedures of classification of solid wastes as non-radioactive wastes. (author)

Determination of {sup 236}U and transuranium elements in depleted uranium ammunition by {alpha}-spectrometry and ICP-MS

Energy Technology Data Exchange (ETDEWEB)

Desideri, D.; Meli, M.A.; Roselli, C.; Testa, C. [General Chemistry Institute, Urbino University, Urbino (Italy); Boulyga, S.F.; Becker, J.S. [Central Department of Analytical Chemistry, Research Centre Juelich, Juelich (Germany)

2002-11-01

It is well known that ammunition containing depleted uranium (DU) was used by NATO during the Balkan conflict. To evaluate the origin of DU (the enrichment of natural uranium or the reprocessing of spent nuclear fuel) it is necessary to directly detect the presence of activation products ({sup 236}U, {sup 239}Pu, {sup 240}Pu, {sup 241}Am, and {sup 237}Np) in the ammunition. In this work the analysis of actinides by {alpha}-spectrometry was compared with that by inductively coupled plasma mass spectrometry (ICP-MS) after selective separation of ultratraces of transuranium elements from the uranium matrix. {sup 242}Pu and {sup 243}Am were added to calculate the chemical yield. Plutonium was separated from uranium by extraction chromatography, using tri-n-octylamine (TNOA), with a decontamination factor higher than 10{sup 6}; after elution plutonium was determined by ICP-MS ({sup 239}Pu and {sup 240}Pu) and {alpha}-spectrometry ({sup 239+240}Pu) after electroplating. The concentration of Pu in two DU penetrator samples was 7 x 10{sup -12} g g{sup -1} and 2 x 10{sup -11} g g{sup -1}. The {sup 240}Pu/{sup 239}Pu isotope ratio in one penetrator sample (0.12{+-}0.04) was significantly lower than the {sup 240}Pu/{sup 239}Pu ratios found in two soil samples from Kosovo (0.35{+-}0.10 and 0.27{+-}0.07). {sup 241}Am was separated by extraction chromatography, using di(2-ethylhexyl)phosphoric acid (HDEHP), with a decontamination factor as high as 10{sup 7}. The concentration of {sup 241}Am in the penetrator samples was 2.7 x 10{sup -14} g g{sup -1} and <9.4 x 10{sup -15} g g{sup -1}. In addition {sup 237}Np was detected at ultratrace levels. In general, ICP-MS and {alpha}-spectrometry results were in good agreement.The presence of anthropogenic radionuclides ({sup 236}U, {sup 239}Pu,{sup 240}Pu, {sup 241}Am, and {sup 237}Np) in the penetrators indicates that at least part of the uranium originated from the reprocessing of nuclear fuel. Because the concentrations of

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

International Nuclear Information System (INIS)

1991-10-01

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

Water reactor fuel research at the Joint Research Centre of the Commission of the European Union

Energy Technology Data Exchange (ETDEWEB)

Markgraf, J [HFR Unit, Inst. for Advanced Materials, Petten (Netherlands)

1997-12-01

The JRC programmes 1995-1998 are in progress within 8 JRC Institutes located within different research centres situated in five member states of the European Union. Except for the area of reactor safety and waste management, there are no JRC research programmes related to water reactor fuel directly. However, the JRC is providing support on basis of contracts and cooperations to bilateral and international R and D programmes through access to its large test facilities like the High Flux Reactor at the JRC Petten and the hot cell facilities of the Transuranium Institute at the JRC Karlsruhe. Access is available to customers from all over the world. 3 tabs.

General survey of applications which require actinide nuclear data

International Nuclear Information System (INIS)

Raman, S.

1976-01-01

This review paper discusses the actinide waste problem, the buildup of toxic isotopes in the fuel, the neutron activity associated with irradiated fuel, the 252 Cf buildup problem, and the production of radioisotope power sources as broad areas that require actinide cross-section data. Decay data enter into the area of radiological safety and health physics. This paper also discusses a few cross-section measurements in progress at the Oak Ridge Electron Linear Accelerator. The availability of actinide samples through the Transuranium Program at Oak Ridge is discussed in considerable detail. The present data status with respect to the various applications is reviewed along with recommendations for improving the data base

Hanford Central Waste Complex: Waste Receiving and Processing Facility dangerous waste permit application

International Nuclear Information System (INIS)

1991-10-01

The Hanford Central Waste Complex is an existing and planned series of treatment, and/or disposal (TSD) unites that will centralize the management of solid waste operations at a single location on the Hanford Facility. The Complex includes two units: the WRAP Facility and the Radioactive Mixed Wastes Storage Facility (RMW Storage Facility). This Part B permit application addresses the WRAP Facility. The Facility will be a treatment and storage unit that will provide the capability to examine, sample, characterize, treat, repackage, store, and certify radioactive and/or mixed waste. Waste treated and stored will include both radioactive and/or mixed waste received from onsite and offsite sources. Certification will be designed to ensure and demonstrate compliance with waste acceptance criteria set forth by onsite disposal units and/or offsite facilities that subsequently are to receive waste from the WRAP Facility. This permit application discusses the following: facility description and general provisions; waste characterization; process information; groundwater monitoring; procedures to prevent hazards; contingency plant; personnel training; exposure information report; waste minimization plan; closure and postclosure requirements; reporting and recordkeeping; other relevant laws; certification

Solid waste

International Nuclear Information System (INIS)

1995-01-01

The article drawn up within the framework of 'the assessment of the state of the environment in Lebanon' provides an overview of solid waste management, and assesses future wastes volume and waste disposal issues.In particular it addresses the following concerns: - Long term projections of solid waste arisings (i.e. domestic, industrial, such commercial wastes, vehicle types, construction waste, waste oils, hazardous toxic wastes and finally hospital and clinical wastes) are described. - Appropriate disposal routes, and strategies for reducing volumes for final disposal - Balance between municipal and industrial solid waste generation and disposal/treatment and - environmental impacts (aesthetics, human health, natural environment )of existing dumps, and the potential impact of government plans for construction of solid waste facilities). Possible policies for institutional reform within the waste management sector are proposed. Tables provides estimations of generation rates and distribution of wastes in different regions of Lebanon. Laws related to solid waste management are summarized

Transuranic waste management program waste form development

International Nuclear Information System (INIS)

Bennett, W.S.; Crisler, L.R.

1981-01-01

To ensure that all technology necessary for long term management of transuranic (TRU) wastes is available, the Department of Energy has established the Transuranic Waste Management Program. A principal focus of the program is development of waste forms that can accommodate the very diverse TRU waste inventory and meet geologic isolation criteria. The TRU Program is following two approaches. First, decontamination processes are being developed to allow removal of sufficient surface contamination to permit management of some of the waste as low level waste. The other approach is to develop processes which will allow immobilization by encapsulation of the solids or incorporate head end processes which will make the solids compatible with more typical waste form processes. The assessment of available data indicates that dewatered concretes, synthetic basalts, and borosilicate glass waste forms appear to be viable candidates for immobilization of large fractions of the TRU waste inventory in a geologic repository

Secondary Waste Cast Stone Waste Form Qualification Testing Plan

Energy Technology Data Exchange (ETDEWEB)

Westsik, Joseph H.; Serne, R. Jeffrey

2012-09-26

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone – a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptable for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF

Low-level radioactive waste, mixed low-level radioactive waste, and biomedical mixed waste

International Nuclear Information System (INIS)

Anon.

1994-01-01

This document describes the proceedings of a workshop entitled: Low-Level Radioactive Waste, Mixed Low-Level Radioactive Waste, and Biomedical Mixed Waste presented by the National Low-Level Waste Management Program at the University of Florida, October 17-19, 1994. The topics covered during the workshop include technical data and practical information regarding the generation, handling, storage and disposal of low-level radioactive and mixed wastes. A description of low-level radioactive waste activities in the United States and the regional compacts is presented

Certification Plan, Radioactive Mixed Waste Hazardous Waste Handling Facility

International Nuclear Information System (INIS)

Albert, R.

1992-01-01

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

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

International Nuclear Information System (INIS)

1994-01-01

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

Long-term program for research and development of group separation and disintegration techniques

International Nuclear Information System (INIS)

1988-01-01

In Japan, the basic guidelines state that high-level radioactive wastes released from reprocessing of spent fuel should be processed into stable solid material, followed by storage for cooling for 30-50 years and disposal in the ground at a depth of several hundreds of meters. The Long-Term Program for Research and Development of Group Separation and Disintegration Techniques is aimed at efficient disposal of high-level wastes, reutilization of useful substances contained, and improved safety. Important processes include separation of nuclides (group separation, individual nuclide separation) and conversion (disintegration) of long-lived nuclides into short-lived or non-radioactive one. These processes can reduce the volume of high-level wastes to be left for final disposal. Research and development projects have been under way to provide techniques to separate high-level waste substances into four groups (transuranic elements, strontium/cesium, technetium/platinum group elements, and others). These projects also cover recovery of useful metals and efficient utilization of separated substances. For disintegration, conceptual studies have been carried out for the application of fast neutron beams to conversion of long half-life transuranium elements into short half-life or non-radioactive elements. (N.K.)

Liquid secondary waste: Waste form formulation and qualification

Energy Technology Data Exchange (ETDEWEB)

Cozzi, A. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, K. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hill, K. A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nichols, R. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2017-07-31

The Hanford Site Effluent Treatment Facility (ETF) currently treats aqueous waste streams generated during site cleanup activities. When the Hanford Tank Waste Treatment and Immobilization Plant (WTP) begins operations, including Direct Feed Low Activity Waste (DFLAW) vitrification, a liquid secondary waste (LSW) stream from the WTP will need to be treated. The volume of effluent for treatment at the ETF will increase significantly. The powdered salt waste form produced by the ETF will be replaced by a stabilized solidified waste form for disposal in Hanford’s Integrated Disposal Facility (IDF). Washington River Protection Solutions is implementing a Secondary Liquid Waste Immobilization Technology Development Plan to address the technology needs for a waste form and solidification process to treat the increased volume of waste planned for disposal at the IDF. Waste form testing to support this plan is composed of work in the near term to provide data as input to a performance assessment (PA) for Hanford’s IDF. In 2015, three Hanford Liquid Secondary Waste simulants were developed based on existing and projected waste streams. Using these waste simulants, fourteen mixes of Hanford Liquid Secondary Waste were prepared and tested varying the waste simulant, the water-to-dry materials ratio, and the dry materials blend composition.1 In FY16, testing was performed using a simulant of the EMF process condensate blended with the caustic scrubber—from the Low Activity Waste (LAW) melter—, processed through the ETF. The initial EMF-16 simulant will be based on modeling efforts performed to determine the mass balance of the ETF for the DFLAW.2 The compressive strength of all of the mixes exceeded the target of 3.4 MPa (500 psi) to meet the requirements identified as potential IDF Waste Acceptance Criteria in Table 1 of the Secondary Liquid Waste Immobilization Technology Development Plan.3 The hydraulic properties of the waste forms tested (hydraulic conductivity

TRU Waste Sampling Program: Volume I. Waste characterization

International Nuclear Information System (INIS)

Clements, T.L. Jr.; Kudera, D.E.

1985-09-01

Volume I of the TRU Waste Sampling Program report presents the waste characterization information obtained from sampling and characterizing various aged transuranic waste retrieved from storage at the Idaho National Engineering Laboratory and the Los Alamos National Laboratory. The data contained in this report include the results of gas sampling and gas generation, radiographic examinations, waste visual examination results, and waste compliance with the Waste Isolation Pilot Plant-Waste Acceptance Criteria (WIPP-WAC). A separate report, Volume II, contains data from the gas generation studies

Spent fuel pyroprocessing demonstration

International Nuclear Information System (INIS)

McFarlane, L.F.; Lineberry, M.J.

1995-01-01

A major element of the shutdown of the US liquid metal reactor development program is managing the sodium-bonded spent metallic fuel from the Experimental Breeder Reactor-II to meet US environmental laws. Argonne National Laboratory has refurbished and equipped an existing hot cell facility for treating the spent fuel by a high-temperature electrochemical process commonly called pyroprocessing. Four products will be produced for storage and disposal. Two high-level waste forms will be produced and qualified for disposal of the fission and activation products. Uranium and transuranium alloys will be produced for storage pending a decision by the US Department of Energy on the fate of its plutonium and enriched uranium. Together these activities will demonstrate a unique electrochemical treatment technology for spent nuclear fuel. This technology potentially has significant economic and technical advantages over either conventional reprocessing or direct disposal as a high-level waste option

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.

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.

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

International Nuclear Information System (INIS)

1994-01-01

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

Re-defining the concepts of waste and waste management:evolving the Theory of Waste Management

OpenAIRE

Pongrácz, E. (Eva)

2002-01-01

Abstract In an attempt to construct a new agenda for waste management, this thesis explores the importance of the definition of waste and its impact on waste management, and the role of ownership in waste management. It is recognised that present legal waste definitions are ambiguous and do not really give an insight into the concept of waste. Moreover, despite its explicit wish of waste prevention, when according to present legislation a thing is assigned the label...

Central Waste Complex (CWC) Waste Analysis Plan

International Nuclear Information System (INIS)

ELLEFSON, M.D.

2000-01-01

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for waste accepted for storage at the Central Waste Complex (CWC), which is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include the source special nuclear and by-product material components of mixed waste, radionuclides are not within the scope of this document. The information on radionuclides is provided only for general knowledge. This document has been revised to meet the interim status waste analysis plan requirements of Washington Administrative Code (WAC) 173 303-300(5). When the final status permit is issued, permit conditions will be incorporated and this document will be revised accordingly

Verifying generator waste certification: NTS waste characterization QA requirements

International Nuclear Information System (INIS)

Williams, R.E.; Brich, R.F.

1988-01-01

Waste management activities managed by the US Department of Energy (DOE) at the Nevada Test Site (NTS) include the disposal of low-level wastes (LLW) and mixed waste (MW), waste which is both radioactive and hazardous. A majority of the packaged LLW is received from offsite DOE generators. Interim status for receipt of MW at the NTS Area 5 Radioactive Waste Management Site (RWMS) was received from the state of Nevada in 1987. The RWMS Mixed Waste Management Facility (MWMF) is expected to be operational in 1988 for approved DOE MW generators. The Nevada Test Site Defense Waste Acceptance Criteria and Certification Requirements (NVO-185, Revision 5) delineates waste acceptance criteria for waste disposal at the NTS. Regulation of the hazardous component of mixed waste requires the implementation of US Environmental Protection Agency (EPA) requirements pursuant to the Resource Conservation and Recovery Act (RCRA). Waste generators must implement a waste certification program to provide assurance that the disposal site waste acceptance criteria are met. The DOE/Nevada Operations Office (NV) developed guidance for generator waste certification program plans. Periodic technical audits are conducted by DOE/NV to assess performance of the waste certification programs. The audit scope is patterned from the waste certification program plan guidance as it integrates and provides a common format for the applicable criteria. The criteria focus on items and activities critical to processing, characterizing, packaging, certifying, and shipping waste

Certification Plan, low-level waste Hazardous Waste Handling Facility

International Nuclear Information System (INIS)

Albert, R.

1992-01-01

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. This plan provides guidance from the HWHF to waste generators, waste handlers, and the Waste Certification Specialist to enable them to conduct their activities and carry out their responsibilities in a manner that complies with the requirements of WHC-WAC. Waste generators have the primary responsibility for the proper characterization of LLW. The Waste Certification Specialist verifies and certifies that LBL LLW is characterized, handled, and shipped in accordance with the requirements of WHC-WAC. Certification is the governing process in which LBL personnel conduct their waste generating and waste handling activities in such a manner that the Waste Certification Specialist can verify that the requirements of WHC-WAC are met

Wastes options

International Nuclear Information System (INIS)

Maes, M.

1992-01-01

After a description of the EEC environmental policy, some wastes families are described: bio-contaminant wastes (municipal and industrial), hospitals wastes, toxic wastes in dispersed quantities, nuclear wastes (radioactive and thermal), plastics compounds wastes, volatiles organic compounds, hydrocarbons and used solvents. Sources, quantities and treatments are given. (A.B.). refs., figs., tabs

Effects of waste content of glass waste forms on Savannah River high-level waste disposal costs

International Nuclear Information System (INIS)

McDonell, W.R.; Jantzen, C.M.

1985-01-01

Effects of the waste content of glass waste forms of Savannah River high-level waste disposal costs are evaluated by their impact on the number of waste canisters produced. Changes in waste content affect onsite Defense Waste Processing Facility (DWPF) costs as well as offsite shipping and repository emplacement charges. A nominal 1% increase over the 28 wt % waste loading of DWPF glass would reduce disposal costs by about $50 million for Savannah River wastes generated to the year 2000. Waste form modifications under current study include adjustments of glass frit content to compensate for added salt decontamination residues and increased sludge loadings in the DWPF glass. Projected cost reductions demonstrate significant incentives for continued optimization of the glass waste loadings. 13 refs., 3 figs., 3 tabs

Liquid secondary waste. Waste form formulation and qualification

Energy Technology Data Exchange (ETDEWEB)

Cozzi, A. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Dixon, K. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hill, K. A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); King, W. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nichols, R. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2016-03-01

The Hanford Site Effluent Treatment Facility (ETF) currently treats aqueous waste streams generated during Site cleanup activities. When the Hanford Tank Waste Treatment and Immobilization Plant (WTP) begins operations, a liquid secondary waste (LSW) stream from the WTP will need to be treated. The volume of effluent for treatment at the ETF will increase significantly. Washington River Protection Solutions is implementing a Secondary Liquid Waste Immobilization Technology Development Plan to address the technology needs for a waste form and solidification process to treat the increased volume of waste planned for disposal at the Integrated Disposal Facility IDF). Waste form testing to support this plan is composed of work in the near term to demonstrate the waste form will provide data as input to a performance assessment (PA) for Hanford’s IDF.

Hanford Site annual dangerous waste report: Volume 3, Part 2, Waste Management Facility report, dangerous waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1944-12-31

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

Hanford Site annual dangerous waste report: Volume 3, Part 1, Waste Management Facility report, dangerous waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

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

Hanford Site annual dangerous waste report: Volume 3, Part 1, Waste Management Facility report, dangerous waste

International Nuclear Information System (INIS)

1994-01-01

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

Waste management

International Nuclear Information System (INIS)

Chmielewska, E.

2010-01-01

In this chapter formation of wastes and basic concepts of non-radioactive waste management are explained. This chapter consists of the following parts: People in Peril; Self-regulation of nature as a guide for minimizing and recycling waste; The current waste management situation in the Slovak Republic; Categorization and determination of the type of waste in legislative of Slovakia; Strategic directions waste management in the Slovak Republic.

Hanford Waste Vitrification Plant: Preliminary description of waste form and canister

International Nuclear Information System (INIS)

Mitchell, D.E.

1986-01-01

In July 1985, the US Department of Energy's Office of Civilian Radioactive Waste Management established the Waste Acceptance Process as the means by which defense high-level waste producers, such as the Hanford Waste Vitrification Plant, will develop waste acceptance requirements with the candidate geologic repositories. A complete description of the Waste Acceptance Process is contained in the Preliminary Hanford Waste Vitrification Plant Waste Form Qualification Plan. The Waste Acceptance Process defines three documents that high-level waste producers must prepare as a part of the process of assuming that a high-level waste product will be acceptable for disposal in a geologic repository. These documents are the Description of Waste Form and Canister, Waste Compliance Plan, and Waste Qualification Report. This document is the Hanford Waste Vitrification Plant Preliminary Description of Waste Form and Canister for disposal of Neutralized Current Acid Waste. The Waste Acceptance Specifications for the Hanford Waste Vitrification Plant have not yet been developed, therefore, this document has been structured to corresponds to the Waste Acceptance Preliminary Specifications for the Defense Waste Processing Facility High-Level Waste Form. Not all of the information required by these specifications is appropriate for inclusion in this Preliminary Description of Waste Form and Canister. Rather, this description is limited to information that describes the physical and chemical characteristics of the expected high-level waste form. The content of the document covers three major areas: waste form characteristics, canister characteristics, and canistered waste form characteristics. This information will be used by the candidate geologic repository projects as the basis for preliminary repository design activities and waste form testing. Periodic revisions are expected as the Waste Acceptance Process progresses

Waste incineration

International Nuclear Information System (INIS)

Rumplmayr, A.; Sammer, G.

2001-01-01

Waste incineration can be defined as the thermal conversion processing of solid waste by chemical oxidation. The types of wastes range from solid household waste and infectious hospital waste through to toxic solid, liquid and gaseous chemical wastes. End products include hot incineration gases, composed primarily of nitrogen, carbon dioxide, water vapor and to a smaller extend of non-combustible residue (ash) and air pollutants (e. g. NO x ). Energy can be recovered by heat exchange from the hot incineration gases, thus lowering fossil fuel consumption that in turn can reduce emissions of greenhouse gases. Burning of solid waste can fulfil up to four distinctive objectives (Pera, 2000): 1. Volume reduction: volume reduction of about 90 %, weight reduction of about 70 %; 2. Stabilization of waste: oxidation of organic input; 3. Recovery of energy from waste; 4. Sanitization of waste: destruction of pathogens. Waste incineration is not a means to make waste disappear. It does entail emissions into air as well as water and soil. The generated solid residues are the topic of this task force. Unlike other industrial processes discussed in this platform, waste incineration is not a production process, and is therefore not generating by-products, only residues. Residues that are isolated from e. g. flue gas, are concentrated in another place and form (e. g. air pollution control residues). Hence, there are generally two groups of residues that have to be taken into consideration: residues generated in the actual incineration process and others generated in the flue gas cleaning system. Should waste incineration finally gain public acceptance, it will be necessary to find consistent regulations for both sorts of residues. In some countries waste incineration is seen as the best option for the treatment of waste, whereas in other countries it is seen very negative. (author)

Residential Waste

DEFF Research Database (Denmark)

Christensen, Thomas Højlund; Fruergaard, Thilde; Matsufuji, Y.

2011-01-01

are discussed in this chapter. Characterizing residential waste is faced with the problem that many residences already divert some waste away from the official collection systems, for example performing home composting of vegetable waste and garden waste, having their bundled newspaper picked up by the scouts...... twice a year or bringing their used furniture to the flea markets organized by charity clubs. Thus, much of the data available on residential waste represents collected waste and not necessarily all generated waste. The latter can only be characterized by careful studies directly at the source......, but such studies are very expensive if fair representation of both spatial and temporal variations should be obtained. In addition, onsite studies may affect the waste generation in the residence because of the increased focus on the issue. Residential waste is defined in different ways in different countries...

Training waste generators: The first responder in proper waste management

International Nuclear Information System (INIS)

Jones, E.

1989-01-01

Dealing with waste effectively requires a ''cradle to grave'' approach to waste management. The first step in that chain of custody is the waste generator. The waste generator plays the key role in the correct identification, packaging, and disposal of waste. The Technical Resources and Training Section at the Oak Ridge National Laboratory (ORNL) has developed several short training programs for waste generators. This training presents a consistent approach to proper handling of waste within the ORNL waste management system. This training has been developed for generators of solid low-level radioactive waste, hazardous and mixed waste, and transuranic waste. In addition to the above, a Waste Minimization training program has been developed for use by all organizations at ORNL who generate any type of hazardous waste. These training programs represent a combined effort of the training staff and the technical staff to assure that all ORNL staff accept their responsibility for handling all types of radioactive and hazardous wastes correctly from its generation to its disposal. 4 refs

Preliminary Hanford Waste Vitrification Plan Waste Form Qualification Plan

International Nuclear Information System (INIS)

Nelson, J.L.

1987-09-01

This Waste Form Qualification Plan describes the waste form qualification activities that will be followed during the design and operation of the Hanford Waste Vitrification Plant to ensure that the vitrified Hanford defense high-level wastes will meet the acceptance requirements of the candidate geologic repositories for nuclear waste. This plan is based on the defense waste processing facility requirements. The content of this plan is based on the assumption that the Hanford Waste Vitrification Plant high-level waste form will be disposed of in one of the geologic repository projects. Proposed legislation currently under consideration by Congress may change or delay the repository site selection process. The impacts of this change will be assessed as details of the new legislation become available. The Plan describes activities, schedules, and programmatic interfaces. The Waste Form Qualification Plan is updated regularly to incorporate Hanford Waste Vitrification Plant-specific waste acceptance requirements and to serve as a controlled baseline plan from which changes in related programs can be incorporated. 10 refs., 5 figs., 5 tabs

Chemistry of transuranium elements in salt-base repository

Energy Technology Data Exchange (ETDEWEB)

Borkowski, Marian [Los Alamos National Laboratory; Reed, Donald T [Los Alamos National Laboratory; Lucchini, Jean - Francois [Los Alamos National Laboratory; Richmann, Michael K [Los Alamos National Laboratory; Khaing, H [Los Alamos National Laboratory; Swanson, J [Los Alamos National Laboratory; Ams, D [Los Alamos National Laboratory

2010-12-02

The mobility and potential release of actinides into the accessible environment continues to be the key performance assessment concern of nuclear repositories. Actinide, in particular plutonium speciation under the wide range of conditions that can exist in the subsurface is complex and depends strongly on the coupled effects of redox conditions, inorganic/organic complexation, and the extent/nature of aggregation. Understanding the key factors that define the potential for actinide migration is, in this context, an essential and critical part of making and sustaining a licensing case for a nuclear repository. Herein we report on recent progress in a concurrent modeling and experimental study to determine the speciation of plutonium, uranium and americium in high ionic strength Na-CI-Mg brines. This is being done as part of the ongomg recertification effort m the Waste Isolation Pilot Plant (WIPP). The oxidation-state specific solubility of actinides were established in brine as function of pC{sub H+}, brine composition and the presence and absence of organic chelating agents and carbonate. An oxidation-state invariant analog approach using Nd{sup 3+} and Th{sup 4+} was used for An{sup 3+} and An{sup 4+} respectively. These results show that organic ligands and hydrolysis are key factors for An(III) solubility, hydrolysis at pC{sub H+} above 8 is predominate for An(IV) and carbonates are the key factor for U(VI) solubility. The effect of high ionic strength and brine components measured in absence of carbonates leads to measurable increased in overall solubility over analogous low ionic strength groundwater. Less is known about the bioreduction of actinides by halo-tolerant microorganisms, but there is now evidence that bioreduction does occur and is analogous, in many ways, to what occurs with soil bacteria. Results of solubility studies that focus on Pitzer parameter corrections, new species (e.g. borate complexation), and the thermodynamic parameters for

Radiation state of environment in the 30-km zone of Chernobyl NPP, water objects

International Nuclear Information System (INIS)

Sukhoruchkin, A.K.

1994-01-01

The level of radioactivity in the zone of Chernobyl NPP before the accident is shown. The extremely high level of radioactive contamination produced by the release from the ChNPP at the accident declined as short-lived nuclides decayed. The aerial γ surveys of the 5 km zone of the ChNPP in October, 1986 and September, 1987 are shown. The radiation hygienic parameters of long-lived nuclides at the moment of release are presented. The main contribution to the dose in inhalation is expected from transuranium nuclides, and in ingestion, 90 Sr. The radiation situation in the 30 km zone is at present determined by 137 Cs, 90 Sr and transuranium nuclides, and such nuclide mixture is very unfavorable from the radiobiological point of view. The dosimetric monitoring of them is discussed. The soil contamination density in the 5 km zone is shown. The circumstances of the rich water resources in the region are explained, and the state of contamination is shown. The observation of radioactive contamination of the surface water of Pripyat River is described, and the results are shown. Much concern in the 30 km zone was aroused by the radiation state of groundwater at the places of the forced temporary burial of solid radioactive waste. The state of the cooling water pond in relation to Pripyat River is reported. (K.I.)

Certification plan transuranic waste: Hazardous Waste Handling Facility

International Nuclear Information System (INIS)

1992-06-01

The purpose of this plan is to describe the organization and methodology for the certification of transuranic (TRU) waste handled in the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory (LBL). The plan incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Quality Assurance Implementing Management Plan (QAIMP) for the HWBF; and a list of the current and planned implementing procedures used in waste certification

Integrated waste management - Looking beyond the solid waste horizon

International Nuclear Information System (INIS)

Seadon, J.K.

2006-01-01

Waste as a management issue has been evident for over four millennia. Disposal of waste to the biosphere has given way to thinking about, and trying to implement, an integrated waste management approach. In 1996 the United Nations Environmental Programme (UNEP) defined 'integrated waste management' as 'a framework of reference for designing and implementing new waste management systems and for analysing and optimising existing systems'. In this paper the concept of integrated waste management as defined by UNEP is considered, along with the parameters that constitute integrated waste management. The examples used are put into four categories: (1) integration within a single medium (solid, aqueous or atmospheric wastes) by considering alternative waste management options (2) multi-media integration (solid, aqueous, atmospheric and energy wastes) by considering waste management options that can be applied to more than one medium (3) tools (regulatory, economic, voluntary and informational) and (4) agents (governmental bodies (local and national), businesses and the community). This evaluation allows guidelines for enhancing success: (1) as experience increases, it is possible to deal with a greater complexity; and (2) integrated waste management requires a holistic approach, which encompasses a life cycle understanding of products and services. This in turn requires different specialisms to be involved in the instigation and analysis of an integrated waste management system. Taken together these advance the path to sustainability

Calculation of projected waste loads for transuranic waste management alternatives

International Nuclear Information System (INIS)

Hong, K.; Kotek, T.; Koebnick, B.; Wang, Y.; Kaicher, C.

1995-01-01

The level of treatment and the treatment and interim storage site configurations (decentralized, regional, or centralized) impact transuranic (TRU) waste loads at and en route to sites in the US Department of Energy (DOE) complex. Other elements that impact waste loads are the volume and characteristics of the waste and the unit operation parameters of the technologies used to treat it. Projected annual complexwide TRU waste loads under various TRU waste management alternatives were calculated using the WASTEunderscoreMGMT computational model. WASTEunderscoreMGMT accepts as input three types of data: (1) the waste stream inventory volume, mass, and contaminant characteristics by generating site and waste stream category; (2) unit operation parameters of treatment technologies; and (3) waste management alternative definitions. Results indicate that the designed capacity of the Waste Isolation Pilot Plant, identified under all waste management alternatives as the permanent disposal facility for DOE-generated TRU waste, is sufficient for the projected complexwide TRU waste load under any of the alternatives

Waste inventory, waste characteristics and waste repositories in Japan

International Nuclear Information System (INIS)

Shimooka, K.

1997-01-01

There are two types of repositories for the low level radioactive wastes in Japan. One is a trench type repository only for concrete debris generated from the dismantling of the research reactor. According to the safety assurance system, Japan Atomic Energy Research Institute (JAERI) has disposed of the concrete debris arose from the dismantling of the Japan Power Demonstration Reactor (JPDR). The other type is the concreted pit with engineered barriers. Rokkasho Low Level Radioactive Waste Disposal Center has this type of repository mainly for the power plant wastes. Japan Nuclear Fuel Ltd. (JNFL) established by electric power companies is the operator of the LLW disposal project. JNFL began the storage operation in 1992 and buried approximately 60,000 drums there. Two hundred thousand drums of uniformly solidified, waste may be buried ultimately. 4 refs, 3 tabs

Hanford Site annual dangerous waste report: Volume 1, Part 1, Generator dangerous waste report, dangerous waste

International Nuclear Information System (INIS)

1994-01-01

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

Hanford Site annual dangerous waste report: Volume 1, Part 1, Generator dangerous waste report, dangerous waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

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

Biogeochemistry of radionuclides in aquatic environments. Annual progress report, 1975--1976

International Nuclear Information System (INIS)

Schell, W.R.

1976-01-01

The present work is a combination of studies on natural radionuclides 210 Po and 210 Pb in aquatic environments and on the biogeochemistry of the transuranium elements 239 Pu, 240 Pu, and 241 Am, in the Bikini Lagoon. The objectives of the biogeochemical studies are to evaluate the cycling of the radionuclides in the aquatic environment from their sources, their distribution within ecosystems, their uptake by biota, and their sinks. Detailed studies of the conditions which now exist some 17 years since the last nuclear detonations at Bikini should give a basis for predicting the effects of large-scale or low-level continuous releases of nuclear waste products in the marine environment

Radioactive waste management

International Nuclear Information System (INIS)

2013-01-01

This eighth chapter presents the radioactive wastes and waste disposal; classification of radioactive wastes; basis requests of the radioactive waste management; conditions for a radioactive waste disposal; registers and inventories; transport of radioactive wastes from a facility to another and the radioactive waste management plan

Waste management, final waste disposal, fuel cycle

International Nuclear Information System (INIS)

Rengeling, H.W.

1991-01-01

Out of the legal poblems that are currently at issue, individual questions from four areas are dealt with: privatization of ultimate waste disposal; distribution of responsibilities for tasks in the field of waste disposal; harmonization and systematization of regulations; waste disposal - principles for making provisions for waste disposal - proof of having made provisions for waste disposal; financing and fees. A distinction has to be made between that which is legally and in particular constitutionally imperative or, as the case may be, permissible, and issues where there is room for political decision-making. Ultimately, the deliberations on the amendment are completely confined to the sphere of politics. (orig./HSCH) [de

Mining wastes

International Nuclear Information System (INIS)

Pradel, J.

1981-01-01

In this article mining wastes means wastes obtained during extraction and processing of uranium ores including production of uraniferous concentrates. The hazards for the population are irradiation, ingestion, dust or radon inhalation. The different wastes produced are reviewed. Management of liquid effluents, water treatment, contamined materials, gaseous wastes and tailings are examined. Environmental impact of wastes during and after exploitation is discussed. Monitoring and measurements are made to verify that ICRP recommendations are met. Studies in progress to improve mining waste management are given [fr

The impact of alcohol om 241Am gastrointestinal absorption, distribution and metabolism kinetics in rats

International Nuclear Information System (INIS)

Zalikin, G.A.; Moskalev, Yu.I.; Nisimov, P.G.

1986-01-01

It is shown that alcohol may intensify gastrointestinal absorption of transuranium nuclides. Some intensification of 241 Am metabolism kinetics in rats and accelerated radionuclide excretion from skeleton are noticed that is due to toxic ethanol effect. Investigations in the above direction are thought to be interesting for development under conditions of chronic effect of different alcohol doses and transuranium nuclide incorporation

Waste acceptance product specifications for vitrified high-level waste forms

International Nuclear Information System (INIS)

Applewhite-Ramsey, A.; Sproull, J.F.

1993-01-01

The Nuclear Waste Policy Act of 1982 mandated that all high-level waste (HLW) be sent to a federal geologic repository for permanent disposal. DOE published the Environmental Assessment in 1982 which identified borosilicate glass as the chosen HLW form. 1 In 1985 the Department of Energy instituted a Waste Acceptance Process to assure that DWPF glass waste forms would be acceptable to such a repository. This assurance was important since production of waste forms will precede repository construction and licensing. As part of this Waste Acceptance Process, the DOE Office of Civilian Radioactive Waste Management (RW) formed the Waste Acceptance Committee (WAC). The WAC included representatives from the candidate repository sites, the waste producing sites and DOE. The WAC was responsible for developing the Waste Acceptance Preliminary Specifications (WAPS) which defined the requirements the waste forms must meet to be compatible with the candidate repository geologies

Waste Receiving and Processing Module 2A waste certification strategy

International Nuclear Information System (INIS)

LeClair, M.D.; Pottmeyer, J.A.; Hyre, R.A.

1994-01-01

This document addresses the certification of Mixed Low Level Waste (MLLW) that will be treated in the Waste Receiving and Processing Facility Module 2A (WRAP 2A) and is destined for disposal in the MLLW trench of the Low Level Burial Grounds (LLBG). The MLLW that will be treated in WRAP 2A contains land disposal restricted and radioactive constituents. Certification of the treated waste is dependent on numerous waste management activities conducted throughout the WRAP 2A operation. These activities range from waste treatability testing conducted prior to WRAP 2A waste acceptance to overchecking final waste form quality prior to transferring waste to disposal. This document addresses the high level strategies and methodologies for certifying the final waste form. Integration among all design and verification activities that support final waste form quality assurance is also discussed. The information generated from this effort may directly support other ongoing activities including the WRAP 2A Waste Characterization Study, WRAP 2A Waste Analysis Plan development, Sample Plan development, and the WRAP 2A Data Management System functional requirements definition

Other Special Waste

DEFF Research Database (Denmark)

Brogaard, Line Kai-Sørensen; Christensen, Thomas Højlund

2011-01-01

In addition to the main types of special waste related to municipal solid waste (MSW) mentioned in the previous chapters (health care risk waste, WEEE, impregnated wood, hazardous waste) a range of other fractions of waste have in some countries been defined as special waste that must be handled...... separately from MSW. Some of these other special wastes are briefly described in this chapter with respect to their definition, quantity and composition, and management options. The special wastes mentioned here are batteries, tires, polyvinylchloride (PVC) and food waste....

Mixed Waste Focus Area - Waste form initiative

International Nuclear Information System (INIS)

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

1998-01-01

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

Radioactive wastes

International Nuclear Information System (INIS)

Grass, F.

1982-01-01

Following a definition of the term 'radioactive waste', including a discussion of possible criteria allowing a delimitation of low-level radioactive against inactive wastes, present techniques of handling high-level, intermediate-level and low-level wastes are described. The factors relevant for the establishment of definitive disposals for high-level wastes are discussed in some detail. Finally, the waste management organization currently operative in Austria is described. (G.G.)

Shipment and Disposal of Solidified Organic Waste (Waste Type IV) to the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

D'Amico, E. L; Edmiston, D. R.; O'Leary, G. A.; Rivera, M. A.; Steward, D. M.

2006-01-01

In April of 2005, the last shipment of transuranic (TRU) waste from the Rocky Flats Environmental Technology Site to the WIPP was completed. With the completion of this shipment, all transuranic waste generated and stored at Rocky Flats was successfully removed from the site and shipped to and disposed of at the WIPP. Some of the last waste to be shipped and disposed of at the WIPP was waste consisting of solidified organic liquids that is identified as Waste Type IV in the Contact-Handled Transuranic Waste Authorized Methods for Payload Control (CH-TRAMPAC) document. Waste Type IV waste typically has a composition, and associated characteristics, that make it significantly more difficult to ship and dispose of than other Waste Types, especially with respect to gas generation. This paper provides an overview of the experience gained at Rocky Flats for management, transportation and disposal of Type IV waste at WIPP, particularly with respect to gas generation testing. (authors)

Household hazardous waste

DEFF Research Database (Denmark)

Fjelsted, Lotte; Christensen, Thomas Højlund

2007-01-01

.) comprised 15-25% and foreign items comprised 10-20%. Water-based paint was the dominant part of the paint waste. The chemical composition of the paint waste and the paint-like waste was characterized by an analysis of 27 substances in seven waste fractions. The content of critical substances was tow......'Paint waste', a part of the 'household hazardous waste', amounting to approximately 5 tonnes was collected from recycling stations in two Danish cities. Sorting and analyses of the waste showed paint waste comprised approximately 65% of the mass, paint-like waste (cleaners, fillers, etc...... and the paint waste was less contaminated with heavy metals than was the ordinary household waste. This may suggest that households no longer need to source-segregate their paint if the household waste is incinerated, since the presence of a small quantity of solvent-based paint will not be harmful when...

Defense Waste Management Plan for buried transuranic-contaminated waste, transuranic-contaminated soil, and difficult-to-certify transuranic waste

International Nuclear Information System (INIS)

1987-06-01

GAO recommended that DOE provide specific plans for permanent disposal of buried TRU-contaminated waste, TRU-contaminated soil, and difficult-to-certify TRU waste; cost estimates for permanent disposal of all TRU waste, including the options for the buried TRU-contaminated waste, TRU-contaminated soil, and difficult-to-certify TRU waste; and specific discussions of environmental and safety issues for the permanent disposal of TRU waste. Purpose of this document is to respond to the GAO recommendations by providing plans and cost estimates for the long-term isolation of the buried TRU-contaminated waste, TRU-contaminated soil, and difficult-to-certify TRU waste. This report also provides cost estimates for processing and certifying stored and newly generated TRU waste, decontaminating and decommissioning TRU waste processing facilities, and interim operations

Treatment of radioactive mixed wastes in commercial low-level wastes

International Nuclear Information System (INIS)

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

1985-01-01

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

Waste minimisation. Home digestion trials of biodegradable waste

Energy Technology Data Exchange (ETDEWEB)

Bench, M.L.; Woodard, R.; Harder, M.K.; Stantzos, N. [Waste and Energy Research Group (WERG), Faculty of Science and Engineering, University of Brighton, East Sussex BN2 4GJ (United Kingdom)

2005-09-01

Minimisation of municipal solid waste and diversion from landfill are necessary for the UK to manage waste sustainably and achieve legislative compliance. A survey of householder attitudes and experiences of a trial for minimising household food waste from waste collection in the county of West Sussex, UK is described. The minimisation method used the Green Cone food digester, designed for garden installation. A postal questionnaire was distributed to 1000 householders who had bought a cone during the trial and a total of 433 responses were received. The main reason for people buying the Green Cone had been concerns about waste (88%), with 78% and 67% of respondents, respectively, claiming to have participated in recycling and home composting in the last 30 days. The waste material most frequently put in the digester was cooked food (91%), followed by fruit waste, vegetable matter and bones/meat. Some respondents were using it for garden and animal waste from pets. Most users found the Green Cone performed satisfactorily. Approximately, 60% of respondents had seen a reduction of 25-50% in the amount of waste they normally put out for collection, with analysis showing reported levels of reduction to be significant (p<0.05). Additional weight surveys by householders recorded an average of 2.7kg/(hweek) diverted to the food digester.

Radioactive wastes. The management of nuclear wastes. Waste workshop, first half-year - Year 2013-2014

International Nuclear Information System (INIS)

Esteoulle, Lucie; Rozwadowski, Elodie; Duverger, Clara

2014-01-01

The first part of this report first presents radioactive wastes with their definition, and their classification (radioactivity level, radioactive half-life). It addresses the issue of waste storage by presenting the different types of storage used since the 1950's (offshore storage, surface warehousing, storage in deep geological layer), and by discussing the multi-barrier approach used for storage safety. The authors then present the French strategy which is defined in the PNGMDR to develop new management modes on the long term, to improve existing management modes, and to take important events which occurred between 2010 and 2012 into account. They also briefly present the Cigeo project (industrial centre of geological storage), and evoke controversies related to the decision to locate this project in Bure (existence of geological cracks and defects, stability and tightness of the clay layer, geothermal potential of the region, economic cost). The second part proposes an overview of the issue of nuclear waste management. The author recalls the definition of a radioactive waste, indicates the origins of these wastes and their classification. She proposes a history of the radioactive waste: discovery of radioactivity, military industrialisation and awareness of the dangerousness of radioactive wastes, nuclear wastes and recent incidents (West Valley, La Hague, Windscale). An overview of policies of nuclear waste management is given: immersion of radioactive wastes, major accidental releases, solutions on the short term and on the medium term

Waste container and method for containing waste

International Nuclear Information System (INIS)

Ono, Akira; Matsushita, Mitsuhiro; Doi, Makoto; Nakatani, Seiichi.

1990-01-01

In a waste container, water-proof membranes and rare earth element layers are formed on the inner surface of a steel plate concrete container in which steel plates are embedded. Further, rear earth element detectors are disposed each from the inner side of the steel plate concrete container by way of a pressure pipe to the outer side of the container. As a method for actually containing wastes, when a plurality of vessels in which wastes are fixed are collectively enhoused to the waste container, cussioning materials are attached to the inner surface of the container and wastes fixing containers are stacked successively in a plurality of rows in a bag made of elastic materials. Subsequently, fixing materials are filled and tightly sealed in the waste container. When the waste container thus constituted is buried underground, even if it should be deformed to cause intrusion of rain water to the inside of the container, the rare earth elements in the container dissolved in the rain water can be detected by the detectors, the containers are exchanged before the rain water intruding to the inner side is leached to the surrounding ground, to previously prevent the leakage of radioactive nuclides. (K.M.)

Final waste classification and waste form technical position papers

International Nuclear Information System (INIS)

1983-05-01

The waste classification technical position paper describes overall procedures acceptable to NRC staff which may be used by licensees to determine the presence and concentrations of the radionuclides listed in section 61.55, and thereby classifying waste for near-surface disposal. This technical position paper also provides guidance on the types of information which should be included in shipment manifests accompanying waste shipments to near-surface disposal facilities. The technical position paper on waste form provides guidance to waste generators on test methods and results acceptable to NRC staff for implementing the 10 CFR Part 61 waste form requirements. It can be used as an acceptable approach for demonstrating compliance with the 10 CFR Part 61 waste structural stability criteria. This technical position paper includes guidance on processing waste into an acceptable stable form, designing acceptable high-integrity containers, packaging cartridge filters, and minimizing radiation effects on organic ion-exchange resins. The guidance in the waste form technical position paper may be used by licensees as the basis for qualifying process control programs to meet the waste form stability requirements, including tests which can be used to demonstrate resistance to degradation arising from the effects of compression, moisture, microbial activity, radiation, and chemical changes. Generic test data (e.g., topical reports prepared by vendors who market solidification technology) may be used for process control program qualification where such generic data is applicable to the particular types of waste generated by a licensee

Nuclear power technology system with molten salt reactor for transuranium nuclides burning in closed fuel cycle

International Nuclear Information System (INIS)

Alekseev, P.N.; Dudnikov, A.A.; Ignatiev, V.V.; Prusakov, V.N.; Ponomarev-Stepnoy, N.N.; Subbotin, S.A.

2000-01-01

A concept of nuclear power technology system with homogeneous molten salt reactors for burning and transmutation of long-lived radioactive toxic nuclides is considered in the paper. Disposition of such reactors in enterprises of fuel cycle allows to provide them with power and facilitate solution of problems with rad waste with minimal losses. (Authors)

Solid waste management

OpenAIRE

Srebrenkoska, Vineta; Golomeova, Saska; Zhezhova, Silvana

2013-01-01

Waste is unwanted or useless materials from households, industry, agriculture, hospitals. Waste materials in solid state are classified as solid waste. Increasing of the amount of solid waste and the pressure what it has on the environment, impose the need to introduce sustainable solid waste management. Advanced sustainable solid waste management involves several activities at a higher level of final disposal of the waste management hierarchy. Minimal use of material and energy resources ...

Harmful Waste Process

International Nuclear Information System (INIS)

Ki, Mun Bong; Lee, Shi Jin; Park, Jun Seok; Yoon, Seok Pyo; Lee, Jae Hyo; Jo, Byeong Ryeol

2008-08-01

This book gives descriptions of processing harmful waste, including concerned law and definition of harmful waste, current conditions and generation of harmful waste in Korea, international condition of harmful waste, minimizing of generation of harmful waste, treatment and storage. It also tells of basic science for harmful waste disposal with physics, chemistry, combustion engineering, microbiology and technique of disposal such as physical, chemical, biological process, stabilizing and solidification, incineration and waste in landfill.

WASTES: a waste management logistics/economics model

International Nuclear Information System (INIS)

McNair, G.W.; Shay, M.R.; Fletcher, J.F.; Cashwell, J.W.

1985-01-01

The WASTES logistics model is a simulation language based model for analyzing the logistic flow of spent fuel/nuclear waste throughout the waste management system. The model tracks the movement of spent fuel/nuclear waste from point of generation to final destination. The model maintains inventories of spent fuel/nuclear waste at individual reactor sites as well as at various facilities within the waste management system. A maximum of 14 facilities may be utilized within a single run. These 14 facilities may include any combination of the following facilities: (1) federal interim storage (FIS), (2) reprocessing (REP), (3) monitored retrievable storage (MRS), (4) geological disposal facilities (GDF). The movement of spent fuel/nuclear waste between these facilities is controlled by the user specification of loading and unloading rates, annual and maximum capacities and commodity characteristics (minimum age or heat constraints) for each individual facility. In addition, the user may specify varying levels of priority on the spent fuel/nuclear waste that will be eligible for movement within a given year. These levels of priority allow the user to preferentially move spent fuel from reactor sites that are experiencing a loss of full-core-reserve (FCR) margin in a given year or from reactors that may be in the final stages of decommissioning. The WASTES model utilizes the reactor specific data available from the PNL spent fuel database. This database provides reactor specific information on items such as spent fuel basin size, reactor location, and transportation cask preference (i.e., rail or truck cask). In addition, detailed discharge data is maintained that provides the number of assemblies, metric tons, and exposure for both historic and projected discharges at each reactor site

Technical liaison with the Institute of Physical Chemistry (Russian Academy of Sciences)

International Nuclear Information System (INIS)

Delegard, C.H.

1997-01-01

DOE has engaged the IPC/RAS to study the fundamental and applied chemistry of the transuranium actinide elements (primarily neptunium, plutonium, and americium) and technetium in alkaline media. This work is supported by DOE because the alkaline radioactive wastes stored in underground tanks at DOE sites (Hanford, Savannah River, and Oak Ridge) contain TRUs and technetium, and these radioelements must be partitioned to the HLW fraction in planned waste processing operations. The chemistries of the TRUs and technetium are not well developed in this system. Previous studies at the IPC/RAS centered on the fundamental chemistry of the TRUs and technetium in alkaline media, and on their coprecipitation reactions. During FY 1996, further studies of fundamental and candidate process chemistries were pursued with continuing effort on coprecipitation. The technical liaison was established at Westinghouse Hanford Company to provide information to the IPC/RAS on the Hanford Site waste system, define and refine the work scope, publish IPC/RAS reports in open literature documents and presentations, provide essential materials and equipment to the IPC/RAS, compare IPC/RAS results with results from other sources, and test chemical reactions or processes proposed by the IPC/RAS with actual Hanford Site tank waste. The liaison task was transferred to the Pacific Northwest Laboratory (PNNL) in October 1996

Technical liaison with the Institute of Physical Chemistry (Russian Academy of Sciences)

Energy Technology Data Exchange (ETDEWEB)

Delegard, C.H. [Pacific Northwest National Lab., Richland, WA (United States)

1997-10-01

DOE has engaged the IPC/RAS to study the fundamental and applied chemistry of the transuranium actinide elements (primarily neptunium, plutonium, and americium) and technetium in alkaline media. This work is supported by DOE because the alkaline radioactive wastes stored in underground tanks at DOE sites (Hanford, Savannah River, and Oak Ridge) contain TRUs and technetium, and these radioelements must be partitioned to the HLW fraction in planned waste processing operations. The chemistries of the TRUs and technetium are not well developed in this system. Previous studies at the IPC/RAS centered on the fundamental chemistry of the TRUs and technetium in alkaline media, and on their coprecipitation reactions. During FY 1996, further studies of fundamental and candidate process chemistries were pursued with continuing effort on coprecipitation. The technical liaison was established at Westinghouse Hanford Company to provide information to the IPC/RAS on the Hanford Site waste system, define and refine the work scope, publish IPC/RAS reports in open literature documents and presentations, provide essential materials and equipment to the IPC/RAS, compare IPC/RAS results with results from other sources, and test chemical reactions or processes proposed by the IPC/RAS with actual Hanford Site tank waste. The liaison task was transferred to the Pacific Northwest Laboratory (PNNL) in October 1996.

Waste management

International Nuclear Information System (INIS)

Soule, H.F.

1975-01-01

Current planning for the management of radioactive wastes, with some emphasis on plutonium contaminated wastes, includes the provision of re-positories from which the waste can be safely removed to permanent disposal. A number of possibilities for permanent disposal are under investigation with the most favorable, at the present time, apparently disposal in a stable geological formation. However, final choice cannot be made until all studies are completed and a pilot phase demonstrates the adequacy of the chosen method. The radioactive wastes which result from all portions of the fuel cycle could comprise an important source of exposure to the public if permitted to do so. The objectives of the AEC waste management program are to provide methods of treating, handling and storing these wastes so that this exposure will not occur. This paper is intended to describe some of the problems and current progress of waste management programs, with emphasis on plutonium-contaminated wastes. Since the technology in this field is advancing at a rapid pace, the descriptions given can be regarded only as a snapshot at one point in time. (author)

Evaluation of Waste-to-Energy Potential of Domestic Solid Wastes in ...

African Journals Online (AJOL)

ADOWIE PERE

waste in the metropolis ends up on illegal waste dumpsites. The aim of this paper was to investigate the waste-to-energy potentials of domestic solid wastes in Benin metropolis, Nigeria using a three-phase study plan - study of current waste management activities, characterization of domestic solid waste and determination ...

Waste Encapsulation and Storage Facility (WESF) Waste Analysis Plan

International Nuclear Information System (INIS)

SIMMONS, F.M.

2000-01-01

The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Waste Encapsulation and Storage Facility (WESF) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (3), (4), (5), and (6). WESF is an interim status other storage-miscellaneous storage unit. WESF stores mixed waste consisting of radioactive cesium and strontium salts. WESF is located in the 200 East Area on the Hanford Facility. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

Understanding radioactive waste

International Nuclear Information System (INIS)

Murray, R.L.

1981-12-01

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

Understanding radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Murray, R.L.

1981-12-01

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

Hanford Waste Vitrification Plant Dangerous Waste Permit Application

International Nuclear Information System (INIS)

1991-10-01

The Hanford Facility currently stores mixed waste, resulting from various processing operations, in underground storage tanks. The Hanford Waste Vitrification Plant will be constructed and operated to process the high-activity fraction of mixed waste stored in these underground tanks. The Hanford Waste Vitrification Plant will solidify pretreated tank waste into a glass product that will be packaged for disposal in a national repository. This Vitrification Plant Dangerous Waste Permit Application, Revision 2, consists of both a Part A and a Part B permit application. An explanation of the Part A revisions, including Revision 4 submitted with this application, is provided at the beginning of the Part A section. The Part B consists of 15 chapters addressing the organization and content of the Part B Checklist prepared by the Washington State Department of Ecology (Ecology 1987)

Influence of assumptions about household waste composition in waste management LCAs

International Nuclear Information System (INIS)

Slagstad, Helene; Brattebø, Helge

2013-01-01

Highlights: ► Uncertainty in waste composition of household waste. ► Systematically changed waste composition in a constructed waste management system. ► Waste composition important for the results of accounting LCA. ► Robust results for comparative LCA. - Abstract: This article takes a detailed look at an uncertainty factor in waste management LCA that has not been widely discussed previously, namely the uncertainty in waste composition. Waste composition is influenced by many factors; it can vary from year to year, seasonally, and with location, for example. The data publicly available at a municipal level can be highly aggregated and sometimes incomplete, and performing composition analysis is technically challenging. Uncertainty is therefore always present in waste composition. This article performs uncertainty analysis on a systematically modified waste composition using a constructed waste management system. In addition the environmental impacts of several waste management strategies are compared when applied to five different cities. We thus discuss the effect of uncertainty in both accounting LCA and comparative LCA. We found the waste composition to be important for the total environmental impact of the system, especially for the global warming, nutrient enrichment and human toxicity via water impact categories.

Greening waste management

CSIR Research Space (South Africa)

Godfrey, Linda K

2014-11-01

Full Text Available ). Countries are moving waste up the waste management hierarchy away from landfilling towards waste prevention, reuse, recycling and recovery. According to the International Solid Waste Association (ISWA, 2012:5), around “70% of the municipal waste produced...

Waste management of ENM-containing solid waste in Europe

DEFF Research Database (Denmark)

Heggelund, Laura Roverskov; Boldrin, Alessio; Hansen, Steffen Foss

2015-01-01

the Danish nanoproduct inventory (www.nanodb.dk) to get a general understanding of the fate of ENM during waste management in the European context. This was done by: 1. assigning individual products to an appropriate waste material fraction, 2. identifying the ENM in each fraction, 3. comparing identified...... waste fractions with waste treatment statistics for Europe, and 4. illustrating the general distribution of ENM into incineration, recycling and landfilling. Our results indicate that ╲plastic from used product containers╡ is the most abundant and diverse waste fraction, comprising a variety of both...... nanoproducts and materials. While differences are seen between individual EU countries/regions according to the local waste management system, results show that all waste treatment options are significantly involved in nanowaste handling, suggesting that research activities should cover different areas...

Waste Transfer Stations

DEFF Research Database (Denmark)

Christensen, Thomas Højlund

2011-01-01

tion and transport is usually the most costly part of any waste management system; and when waste is transported over a considerable distance or for a long time, transferring the waste from the collection vehicles to more efficient transportation may be economically beneficial. This involves...... a transfer station where the transfer takes place. These stations may also be accessible by private people, offering flexibility to the waste system, including facilities for bulky waste, household hazardous waste and recyclables. Waste transfer may also take place on the collection route from small...... describes the main features of waste transfer stations, including some considerations about the economical aspects on when transfer is advisable....

Mechanical compaction of Waste Isolation Pilot Plant simulated waste

International Nuclear Information System (INIS)

Butcher, B.M.; Thompson, T.W.; VanBuskirk, R.G.; Patti, N.C.

1991-06-01

The investigation described in this report acquired experimental information about how materials simulating transuranic (TRU) waste compact under axial compressive stress, and used these data to define a model for use in the Waste Isolation Pilot Plant (WIPP) disposal room analyses. The first step was to determine compaction curves for various simultant materials characteristic of TRU waste. Stress-volume compaction curves for various combinations of these materials were than derived to represent the combustible, metallic, and sludge waste categories. Prediction of compaction response in this manner is considered essential for the WIPP program because of the difficulties inherent in working with real (radioactive) waste. Next, full-sized 55-gallon drums of simulated combustible, metallic, and sludge waste were axially compacted. These results provided data that can be directly applied to room consolidation and data for comparison with the predictions obtained in Part 1 of the investigation. Compaction curves, which represent the combustible, metallic, and sludge waste categories, were determined, and a curve for the averaged waste inventory of the entire repository was derived. 9 refs., 31 figs., 12 tabs

Low-level waste management - suggested solutions for problem wastes

International Nuclear Information System (INIS)

Pechin, W.H.; Armstrong, K.M.; Colombo, P.

1984-01-01

Problem wastes are those wastes which are difficult or require unusual expense to place into a waste form acceptable under the requirements of 10 CFR 61 or the disposal site operators. Brookhaven National Laboratory has been investigating the use of various solidification agents as part of the DOE Low-Level Waste Management Program for several years. Two of the leading problem wastes are ion exchange resins and organic liquids. Ion exchange resins can be solidified in Portland cement up to about 25 wt % resin, but waste forms loaded to this degree exhibit significantly reduced compressive strength and may disintegrate when immersed in water. Ion exchange resins can also be incorporated into organic agents. Mound Laboratory has been investigating the use of a joule-heated glass melter as a means of disposing of ion exchange resins and organic liquids in addition to other combustible wastes

Disposal Of Waste Matter

International Nuclear Information System (INIS)

Kim, Jeong Hyeon; Lee, Seung Mu

1989-02-01

This book deals with disposal of waste matter management of soiled waste matter in city with introduction, definition of waste matter, meaning of management of waste matter, management system of waste matter, current condition in the country, collect and transportation of waste matter disposal liquid waste matter, industrial waste matter like plastic, waste gas sludge, pulp and sulfuric acid, recycling technology of waste matter such as recycling system of Black clawson, Monroe and Rome.

Recycling waste

Energy Technology Data Exchange (ETDEWEB)

Smith, P I.S.

1976-01-01

It is being realized that if environmental quality is to be improved the amount of waste generated by man has to be substantially reduced. There are two ways this can be achieved. First, by conserving materials and energy, and sacrificing economic growth, a solution that is completely unacceptable because it would mean some form of rationing, mass unemployment, and collapse of society as it is known. The second way to reduce the volume of waste is by planned recycling, re-use, and recovery. Already the reclamation industry recovers, processes, and turns back for re-use many products used by industry and thereby reduces the UK's import bill for raw materials. In the book, the author sets out the various ways materials may be recovered from industrial and municipal wastes. The broad technology of waste management is covered and attention is focused on man's new resources lying buried in the mountains of industrial wastes, the emissions from stocks, the effluents and sludges that turn rivers into open sewers, and municipal dumps in seventeen chapters. The final chapter lists terms and concepts used in waste technology, organizations concerned with waste management, and sources of information about recycling waste. (MCW)

Fast reactors

International Nuclear Information System (INIS)

Vasile, A.

2001-01-01

Fast reactors have capacities to spare uranium natural resources by their breeding property and to propose solutions to the management of radioactive wastes by limiting the inventory of heavy nuclei. This article highlights the role that fast reactors could play for reducing the radiotoxicity of wastes. The conversion of 238 U into 239 Pu by neutron capture is more efficient in fast reactors than in light water reactors. In fast reactors multi-recycling of U + Pu leads to fissioning up to 95% of the initial fuel ( 238 U + 235 U). 2 strategies have been studied to burn actinides: - the multi-recycling of heavy nuclei is made inside the fuel element (homogeneous option); - the unique recycling is made in special irradiation targets placed inside the core or at its surroundings (heterogeneous option). Simulations have shown that, for the same amount of energy produced (400 TWhe), the mass of transuranium elements (Pu + Np + Am + Cm) sent to waste disposal is 60,9 Kg in the homogeneous option and 204.4 Kg in the heterogeneous option. Experimental programs are carried out in Phenix and BOR60 reactors in order to study the feasibility of such strategies. (A.C.)

Hanford Waste Vitrification Plant Project Waste Form Qualification Program Plan

International Nuclear Information System (INIS)

Randklev, E.H.

1993-06-01

The US Department of Energy has created a waste acceptance process to help guide the overall program for the disposal of high-level nuclear waste in a federal repository. This Waste Form Qualification Program Plan describes the hierarchy of strategies used by the Hanford Waste Vitrification Plant Project to satisfy the waste form qualification obligations of that waste acceptance process. A description of the functional relationship of the participants contributing to completing this objective is provided. The major activities, products, providers, and associated scheduling for implementing the strategies also are presented

Understanding low-level radioactive waste. National Low-Level Radioactive Waste Management Program

International Nuclear Information System (INIS)

1983-10-01

Chapters are devoted to: background and policymaking for low-level waste management; commercial low-level waste generation; Department of Energy low-level waste generation; low-level waste treatment; packaging and transportation; commercial low-level waste disposal; Department of Energy low-level waste disposal; Department of Energy low-level waste management program; and laws and regulations

Disposal of radioactive wastes

International Nuclear Information System (INIS)

Dlouhy, Z.

1982-01-01

This book provides information on the origin, characteristics and methods of processing of radioactive wastes, as well as the philosophy and practice of their storage and disposal. Chapters are devoted to the following topics: radioactive wastes, characteristics of radioactive wastes, processing liquid and solid radioactive wastes, processing wastes from spent fuel reprocessing, processing gaseous radioactive wastes, fixation of radioactive concentrates, solidification of high-level radioactive wastes, use of radioactive wastes as raw material, radioactive waste disposal, transport of radioactive wastes and economic problems of radioactive wastes disposal. (C.F.)

ITER waste management

International Nuclear Information System (INIS)

Rosanvallon, S.; Na, B.C.; Benchikhoune, M.; Uzan, J. Elbez; Gastaldi, O.; Taylor, N.; Rodriguez, L.

2010-01-01

ITER will produce solid radioactive waste during its operation (arising from the replacement of components and from process and housekeeping waste) and during decommissioning (de-activation phase and dismantling). The waste will be activated by neutrons of energies up to 14 MeV and potentially contaminated by activated corrosion products, activated dust and tritium. This paper describes the waste origin, the waste classification as a function of the French national agency for radioactive waste management (ANDRA), the optimization process put in place to reduce the waste radiotoxicity and volumes, the estimated waste amount based on the current design and maintenance procedure, and the overall strategy from component removal to final disposal anticipated at this stage of the project.

Hanford Site annual dangerous waste report: Volume 1, Part 2, Generator dangerous waste report, dangerous waste

International Nuclear Information System (INIS)

1994-01-01

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

Hanford Site annual dangerous waste report: Volume 1, Part 2, Generator dangerous waste report, dangerous waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

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

Solid waste combustion for alpha waste incineration

International Nuclear Information System (INIS)

Orloff, D.I.

1981-02-01

Radioactive waste incinerator development at the Savannah River Laboratory has been augmented by fundamental combustion studies at the University of South Carolina. The objective was to measure and model pyrolysis and combustion rates of typical Savannah River Plant waste materials as a function of incinerator operating conditions. The analytical models developed in this work have been incorporated into a waste burning transient code. The code predicts maximum air requirement and heat energy release as a function of waste type, package size, combustion chamber size, and temperature. Historically, relationships have been determined by direct experiments that did not allow an engineering basis for predicting combustion rates in untested incinerators. The computed combustion rates and burning times agree with measured values in the Savannah River Laboratory pilot (1 lb/hr) and full-scale (12 lb/hr) alpha incinerators for a wide variety of typical waste materials

Electronic wastes

Science.gov (United States)

Regel-Rosocka, Magdalena

2018-03-01

E-waste amount is growing at about 4% annually, and has become the fastest growing waste stream in the industrialized world. Over 50 million tons of e-waste are produced globally each year, and some of them end up in landfills causing danger of toxic chemicals leakage over time. E-waste is also sent to developing countries where informal processing of waste electrical and electronic equipment (WEEE) causes serious health and pollution problems. A huge interest in recovery of valuable metals from WEEE is clearly visible in a great number of scientific, popular scientific publications or government and industrial reports.

Energy from wastes and the private waste contracting industry

International Nuclear Information System (INIS)

Burnett, J.S.

1993-01-01

The focus of this ongoing work is the utilisation of general non hazardous industrial and commercial waste as an energy or fuel source. Whereas much of the existing experience in energy from waste (EFW) is related to municipal solid wastes (MSW), there is very little direct experience with these other waste streams and the shortage of reliable information in this field is notoriously lacking. It is important to have a good understanding of the private waste contracting industry (pwci) in order to establish the conditions under which energy from waste technologies may play an economically and technically feasible role within that industry's development. The Non Fossil Fuel Obligation (NFFO) has encouraged entrepreneurial interest through premium payments for electricity generated from renewable sources. (author)

Waste -92

International Nuclear Information System (INIS)

Ekwall, K.

1992-11-01

The report gives a review of waste incineration in Sweden today, including environmental and legal aspects. 21 incinerator plants are in use, producing heat to district heating network and, to a minor part, electric power. In 1991 1.31 Mton household waste and 0.35 Mton industrial waste were incinerated producing 4.4 Twh of energy. In a few cities 30-40 percent of the district heat comes from waste incineration. The theoretical and practical potentials for energy production in Sweden are estimated to 7 respective 5 TWh for household waste and 9 respective 5-6 TWh for industrial waste. Landfill gas is extracted at about 35 sites, with a yearly production of 0.3 TWh which corresponds to 3-5 percent of the potentially recoverable quantity. (8 refs., 2 figs., 13 tabs.)

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

Waste Characterization Methods

Energy Technology Data Exchange (ETDEWEB)

Vigil-Holterman, Luciana R. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Naranjo, Felicia Danielle [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-02-02

This report discusses ways to classify waste as outlined by LANL. Waste Generators must make a waste determination and characterize regulated waste by appropriate analytical testing or use of acceptable knowledge (AK). Use of AK for characterization requires several source documents. Waste characterization documentation must be accurate, sufficient, and current (i.e., updated); relevant and traceable to the waste stream’s generation, characterization, and management; and not merely a list of information sources.

Waste Characterization Methods

International Nuclear Information System (INIS)

Vigil-Holterman, Luciana R.; Naranjo, Felicia Danielle

2016-01-01

This report discusses ways to classify waste as outlined by LANL. Waste Generators must make a waste determination and characterize regulated waste by appropriate analytical testing or use of acceptable knowledge (AK). Use of AK for characterization requires several source documents. Waste characterization documentation must be accurate, sufficient, and current (i.e., updated); relevant and traceable to the waste stream's generation, characterization, and management; and not merely a list of information sources.

A NEW WASTE CLASSIFYING MODEL: HOW WASTE CLASSIFICATION CAN BECOME MORE OBJECTIVE?

Directory of Open Access Journals (Sweden)

Burcea Stefan Gabriel

2015-07-01

Full Text Available The waste management specialist must be able to identify and analyze waste generation sources and to propose proper solutions to prevent the waste generation and encurage the waste minimisation. In certain situations like implementing an integrated waste management sustem and configure the waste collection methods and capacities, practitioners can face the challenge to classify the generated waste. This will tend to be the more demanding as the literature does not provide a coherent system of criteria required for an objective waste classification process. The waste incineration will determine no doubt a different waste classification than waste composting or mechanical and biological treatment. In this case the main question is what are the proper classification criteria witch can be used to realise an objective waste classification? The article provide a short critical literature review of the existing waste classification criteria and suggests the conclusion that the literature can not provide unitary waste classification system which is unanimously accepted and assumed by ideologists and practitioners. There are various classification criteria and more interesting perspectives in the literature regarding the waste classification, but the most common criteria based on which specialists classify waste into several classes, categories and types are the generation source, physical and chemical features, aggregation state, origin or derivation, hazardous degree etc. The traditional classification criteria divided waste into various categories, subcategories and types; such an approach is a conjectural one because is inevitable that according to the context in which the waste classification is required the used criteria to differ significantly; hence the need to uniformizating the waste classification systems. For the first part of the article it has been used indirect observation research method by analyzing the literature and the various

Designing Advanced Ceramic Waste Forms for Electrochemical Processing Salt Waste

International Nuclear Information System (INIS)

Ebert, W. L.; Snyder, C. T.; Frank, Steven; Riley, Brian

2016-01-01

This report describes the scientific basis underlying the approach being followed to design and develop ''advanced'' glass-bonded sodalite ceramic waste form (ACWF) materials that can (1) accommodate higher salt waste loadings than the waste form developed in the 1990s for EBR-II waste salt and (2) provide greater flexibility for immobilizing extreme waste salt compositions. This is accomplished by using a binder glass having a much higher Na_2O content than glass compositions used previously to provide enough Na+ to react with all of the Cl- in the waste salt and generate the maximum amount of sodalite. The phase compositions and degradation behaviors of prototype ACWF products that were made using five new binder glass formulations and with 11-14 mass% representative LiCl/KCl-based salt waste were evaluated and compared with results of similar tests run with CWF products made using the original binder glass with 8 mass% of the same salt to demonstrate the approach and select a composition for further studies. About twice the amount of sodalite was generated in all ACWF materials and the microstructures and degradation behaviors confirmed our understanding of the reactions occurring during waste form production and the efficacy of the approach. However, the porosities of the resulting ACWF materials were higher than is desired. These results indicate the capacity of these ACWF waste forms to accommodate LiCl/KCl-based salt wastes becomes limited by porosity due to the low glass-to-sodalite volume ratio. Three of the new binder glass compositions were acceptable and there is no benefit to further increasing the Na content as initially planned. Instead, further studies are needed to develop and evaluate alternative production methods to decrease the porosity, such as by increasing the amount of binder glass in the formulation or by processing waste forms in a hot isostatic press. Increasing the amount of binder glass to eliminate porosity will decrease the waste

Designing Advanced Ceramic Waste Forms for Electrochemical Processing Salt Waste

Energy Technology Data Exchange (ETDEWEB)

Ebert, W. L. [Argonne National Lab. (ANL), Argonne, IL (United States); Snyder, C. T. [Argonne National Lab. (ANL), Argonne, IL (United States); Frank, Steven [Argonne National Lab. (ANL), Argonne, IL (United States); Riley, Brian [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-03-01

This report describes the scientific basis underlying the approach being followed to design and develop “advanced” glass-bonded sodalite ceramic waste form (ACWF) materials that can (1) accommodate higher salt waste loadings than the waste form developed in the 1990s for EBR-II waste salt and (2) provide greater flexibility for immobilizing extreme waste salt compositions. This is accomplished by using a binder glass having a much higher Na₂O content than glass compositions used previously to provide enough Na+ to react with all of the Cl– in the waste salt and generate the maximum amount of sodalite. The phase compositions and degradation behaviors of prototype ACWF products that were made using five new binder glass formulations and with 11-14 mass% representative LiCl/KCl-based salt waste were evaluated and compared with results of similar tests run with CWF products made using the original binder glass with 8 mass% of the same salt to demonstrate the approach and select a composition for further studies. About twice the amount of sodalite was generated in all ACWF materials and the microstructures and degradation behaviors confirmed our understanding of the reactions occurring during waste form production and the efficacy of the approach. However, the porosities of the resulting ACWF materials were higher than is desired. These results indicate the capacity of these ACWF waste forms to accommodate LiCl/KCl-based salt wastes becomes limited by porosity due to the low glass-to-sodalite volume ratio. Three of the new binder glass compositions were acceptable and there is no benefit to further increasing the Na content as initially planned. Instead, further studies are needed to develop and evaluate alternative production methods to decrease the porosity, such as by increasing the amount of binder glass in the formulation or by processing waste forms in a hot isostatic press. Increasing the amount of binder glass to eliminate porosity will decrease

Analysis of SRP waste streams for waste tank certification

International Nuclear Information System (INIS)

Coleman, C.J.

1989-01-01

The Savannah River Plant (SRP) will apply for certification from the State of South Carolina to operate the SRP High-Level Waste Tanks. The permit application will be submitted as a RCRA Part B, Volume 16, entitled ''RCRA Part B Application For the F and H-Area Radioactive Waste Farm.'' RCRA regulations require that influent and effluent streams of hazardous waste sites be characterized to obtain an operating permit. The Waste Management Technology Department requested ADD to determine 21 components (including pH and weight percent solids) in the current influent streams to SRP High-Level Waste Tanks. The analyses will be used to supplement existing data on the composition of High-Level Waste. Effluent streams, which will feed Saltstone and the DWPF, will be analyzed when they are produced. This report contains the data obtained from analyzing key influent streams to SRP High-Level Waste Tanks. The precision of the data and the analytical methods that were used are also discussed

Radioactive waste management

International Nuclear Information System (INIS)

1984-07-01

The purpose of this document is to set out the Government's current strategy for the long term in the management of radioactive wastes. It takes account of the latest developments, and will be subject to review in the light of future developments and studies. The subject is discussed under the headings: what are radioactive wastes; who is responsible; what monitoring takes place; disposal as the objective; low-level wastes; intermediate-level wastes; discharges from Sellafield; heat generating wastes; how will waste management systems and procedures be assessed; how much more waste is there going to be in future; conclusion. (U.K.)

Radioactive waste processing

International Nuclear Information System (INIS)

Dejonghe, P.

1978-01-01

This article gives an outline of the present situation, from a Belgian standpoint, in the field of the radioactive wastes processing. It estimates the annual quantity of various radioactive waste produced per 1000 MW(e) PWR installed from the ore mining till reprocessing of irradiated fuels. The methods of treatment concentration, fixation, final storable forms for liquid and solid waste of low activity and for high level activity waste. The storage of radioactive waste and the plutonium-bearing waste treatement are also considered. The estimated quantity of wastes produced for 5450 MW(e) in Belgium and their destination are presented. (A.F.)

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

Life-cycle assessment of municipal solid wastes: Development of the WASTED model

International Nuclear Information System (INIS)

Diaz, R.; Warith, M.

2006-01-01

This paper describes the development of the Waste Analysis Software Tool for Environmental Decisions (WASTED) model. This model provides a comprehensive view of the environmental impacts of municipal solid waste management systems. The model consists of a number of separate submodels that describe a typical waste management process: waste collection, material recovery, composting, energy recovery from waste and landfilling. These submodels are combined to represent a complete waste management system. WASTED uses compensatory systems to account for the avoided environmental impacts derived from energy recovery and material recycling. The model is designed to provide solid waste decision-makers and environmental researchers with a tool to evaluate waste management plans and to improve the environmental performance of solid waste management strategies. The model is user-friendly and compares favourably with other earlier models

Waste management system alternatives for treatment of wastes from spent fuel reprocessing

International Nuclear Information System (INIS)

McKee, R.W.; Swanson, J.L.; Daling, P.M.

1986-09-01

This study was performed to help identify a preferred TRU waste treatment alternative for reprocessing wastes with respect to waste form performance in a geologic repository, near-term waste management system risks, and minimum waste management system costs. The results were intended for use in developing TRU waste acceptance requirements that may be needed to meet regulatory requirements for disposal of TRU wastes in a geologic repository. The waste management system components included in this analysis are waste treatment and packaging, transportation, and disposal. The major features of the TRU waste treatment alternatives examined here include: (1) packaging (as-produced) without treatment (PWOT); (2) compaction of hulls and other compactable wastes; (3) incineration of combustibles with cementation of the ash plus compaction of hulls and filters; (4) melting of hulls and failed equipment plus incineration of combustibles with vitrification of the ash along with the HLW; (5a) decontamination of hulls and failed equipment to produce LLW plus incineration and incorporation of ash and other inert wastes into HLW glass; and (5b) variation of this fifth treatment alternative in which the incineration ash is incorporated into a separate TRU waste glass. The six alternative processing system concepts provide progressively increasing levels of TRU waste consolidation and TRU waste form integrity. Vitrification of HLW and intermediate-level liquid wastes (ILLW) was assumed in all cases

Process equipment waste and process waste liquid collection systems

International Nuclear Information System (INIS)

1990-06-01

The US DOE has prepared an environmental assessment for construction related to the Process Equipment Waste (PEW) and Process Waste Liquid (PWL) Collection System Tasks at the Idaho Chemical Processing Plant. This report describes and evaluates the environmental impacts of the proposed action (and alternatives). The purpose of the proposed action would be to ensure that the PEW and PWL collection systems, a series of enclosed process hazardous waste, and radioactive waste lines and associated equipment, would be brought into compliance with applicable State and Federal hazardous waste regulations. This would be accomplished primarily by rerouting the lines to stay within the buildings where the lined floors of the cells and corridors would provide secondary containment. Leak detection would be provided via instrumented collection sumps locate din the cells and corridors. Hazardous waste transfer lines that are routed outside buildings will be constructed using pipe-in-pipe techniques with leak detection instrumentation in the interstitial area. The need for the proposed action was identified when a DOE-sponsored Resource Conservation and Recovery Act (RCRA) compliance assessment of the ICPP facilities found that singly-contained waste lines ran buried in the soil under some of the original facilities. These lines carried wastes with a pH of less than 2.0, which were hazardous waste according to the RCRA standards. 20 refs., 7 figs., 1 tab

Bioremediation of cooking oil waste using lipases from wastes.

Directory of Open Access Journals (Sweden)

Clarissa Hamaio Okino-Delgado

Full Text Available Cooking oil waste leads to well-known environmental impacts and its bioremediation by lipase-based enzymatic activity can minimize the high cytotoxic potential. In addition, they are among the biocatalysts most commercialized worldwide due to the versatility of reactions and substrates. However, although lipases are able to process cooking oil wastes, the products generated from this process do not necessarily become less toxic. Thus, the aim of the current study is to analyze the bioremediation of lipase-catalyzed cooking oil wastes, as well as their effect on the cytotoxicity of both the oil and its waste before and after enzymatic treatment. Thus, assessed the post-frying modification in soybean oil and in its waste, which was caused by hydrolysis reaction catalyzed by commercial and home-made lipases. The presence of lipases in the extracts obtained from orange wastes was identified by zymography. The profile of the fatty acid esters formed after these reactions was detected and quantified through gas chromatography and fatty acids profile compared through multivariate statistical analyses. Finally, the soybean oil and its waste, with and without enzymatic treatment, were assessed for toxicity in cytotoxicity assays conducted in vitro using fibroblast cell culture. The soybean oil wastes treated with core and frit lipases through transesterification reaction were less toxic than the untreated oils, thus confirming that cooking oil wastes can be bioremediated using orange lipases.

Economic analysis of waste management alternatives for reprocessing wastes

International Nuclear Information System (INIS)

McKee, R.W.; Clark, L.L.; Daling, P.M.; Nesbitt, J.F.; Swanson, J.L.

1984-02-01

This study describes the results of a cost analysis of a broad range of alternatives for management of reprocessing wastes that would require geologic repository disposal. The intent was to identify cost-effective alternatives and the costs of potential repository performance requirements. Four integrated treatment facility alternatives for transuranic (TRU) wastes are described and compared. These include no treatment, compaction, incineration, and hulls melting. The advantages of reducing high-level wastes (HLW) volume are also evaluated as are waste transportation alternatives and several performance-related alternatives for emplacing waste in a basalt repository. Results show (1) that system costs for disposal of reprocessing waste are likely to be higher than those for disposal of spent fuel; (2) that volume reduction is cost-effective for both remote-handled (RH) TRU wastes and HLW, and that rail transport for HLW is more cost-effective than truck transport; (3) that coemplacement of RH-TRU wastes with HLW does not have a large cost advantage in a basalt repository; and (4) that, relative to performance requirements, the cost impact for elimination of combustibles is about 5%, long-lived containers for RH-TRU wastes can increase repository costs 10% to 20%, and immediate backfill compared to delayed backfill (bentonite/basalt) around the HLW canisters would increase repository costs up to 10% or overall system costs up to about 5%. 13 references, 4 figures, 12 tables

Properties of radioactive wastes and waste containers

International Nuclear Information System (INIS)

Arora, H.S.; Dayal, R.

1984-01-01

Major tasks in this NRC-sponsored program include: (1) an evaluation of the acceptability of low-level solidified wastes with respect to minimizing radionuclide releases after burial; and (2) an assessment of the influence of pertinent environmental stresses on the performance of high-integrity radwaste container (HIC) materials. The waste form performance task involves studies on small-scale laboratory specimens to predict and extrapolate: (1) leachability for extended time periods; (2) leach behavior of full-size forms; (3) performance of waste forms under realistic leaching conditions; and (4) leachability of solidified reactor wastes. The results show that leach data derived from testing of small-scale specimens can be extrapolated to estimate leachability of a full-scale specimen and that radionuclide release data derived from testing of simulants can be employed to predict the release behavior of reactor wastes. Leaching under partially saturated conditions exhibits lower releases of radionuclides than those observed under the conventional IAEA-type or ANS 16.1 leach tests. The HIC assessment task includes the characterization of mechanical properties of Marlex CL-100, a candidate radwaste high density polyethylene material. Tensile strength and creep rupture tests have been carried out to determine the influence of specific waste constituents as well as gamma irradiation on material performance. Emphasis in ongoing tests is being placed on studying creep rupture while the specimens are in contact with a variety of chemicals including radiolytic by-products of irradiated resin wastes. 12 references 6 figures, 2 tables

Waste acceptance product specifications for vitrified high-level waste forms

International Nuclear Information System (INIS)

Applewhite-Ramsey, A.; Sproull, J.F.

1994-01-01

The Department of Energy (DOE) Office of Environmental Restoration and Waste Management (EM) has developed Waste Acceptance Product Specifications (EM-WAPS). The EM-WAPS will be the basis for defining product acceptance criteria compatible with the requirements of the Civilian Radioactive Waste Management System (CRWMS). The relationship between the EM-WAPS and the CRWMS Systems Requirements document (WA-SRD) will be discussed. The impact of the EM-WAPS on the Savannah River Sit (SRS) Defense Waste Processing Facility's (DWPF) Waste Acceptance Program, Waste Qualification Run planning, and startup schedule will also be reported. 14 refs., 2 tabs

Assessment Strategies for Municipal Selective Waste Collection – Regional Waste Management

Directory of Open Access Journals (Sweden)

Agnieszka Boas Berg

2018-01-01

Full Text Available Waste disposal in landfill sites causes a potentialhazard for the human health, as they release substantial amounts of gas, odours and pollutants to the environment. There have been vast reductions in the volume of waste being landfilledin many European countries and a reduction in the number of illegal landfills The European Parliament’s laws obliged the Member States to amend the national waste law; the main objectives of the implemented directives are to create the conditions for the prevention of excessive waste. Directive 2008/98/EC establishes, as a goal for 2020, that waste reuse and recycling reach 50% of the total waste produced. Poland, having joined the European Union, committed itself to implementing many changes related to waste management. The amendment of the law on the maintenance of cleanliness and order in the municipalities imposed new obligations regarding the waste management (WM on the local government and residents. By adopting a municipal waste management system, the selected municipality made all its residents responsible for their waste. However, the fact of introducing changes does not solve the waste problem. The implementation of EU directives and the development of strategic documents such as the National Waste Management Plan (NWMP have made a clear change in the WM approach. One of the changes was the establishment of selective collection of municipal selective waste (MSW, with the issue of collecting the waste by the residents being a priority. This work describes the legal context of selective collection of MSW as one of the most effective means of reducing the amount of waste being landfilled.

Waste disposal

International Nuclear Information System (INIS)

2005-01-01

Radioactive waste, as a unavoidable remnant from the use of radioactive substances and nuclear technology. It is potentially hazardous to health and must therefore be managed to protect humans and the environment. The main bulk of radioactive waste must be permanently disposed in engineered repositories. Appropriate safety standards for repository design and construction are required along with the development and implementation of appropriate technologies for the design, construction, operation and closure of the waste disposal systems. As backend of the fuel cycle, resolving the issue of waste disposal is often considered as a prerequisite to the (further) development of nuclear energy programmes. Waste disposal is therefore an essential part of the waste management strategy that contributes largely to build confidence and helps decision-making when appropriately managed. The International Atomic Energy Agency provides assistance to Member States to enable safe and secure disposal of RW related to the development of national RWM strategies, including planning and long-term project management, the organisation of international peer-reviews for research and demonstration programmes, the improvement of the long-term safety of existing Near Surface Disposal facilities including capacity extension, the selection of potential candidate sites for different waste types and disposal options, the characterisation of potential host formations for waste facilities and the conduct of preliminary safety assessment, the establishment and transfer of suitable technologies for the management of RW, the development of technological solutions for some specific waste, the building of confidence through training courses, scientific visits and fellowships, the provision of training, expertise, software or hardware, and laboratory equipment, and the assessment of waste management costs and the provision of advice on cost minimisation aspects

Safety research program of NUCEF

International Nuclear Information System (INIS)

Naito, Y.

1996-01-01

To contribute the safety and establishment of advanced technologies in the area of nuclear fuel cycle, Japan Atomic Energy Research Institute (JAERI) has constructed a new research facility NUCEF (Nuclear Fuel Cycle Safety Engineering Research Facility) as the center for the research and development, particularly on the reprocessing technology and transuranium (TRU) waste management. NUCEF consist of three buildings, administration building, experiment building A and B. Building A has two experiment facilities STACY (Static Experiment Critical Facility) and TRACY (Transient Experiment Critical Facility). The experiment building B is referred to as BECKY (Back-end Fuel Cycle Key Elements Research Facility). Researches on the reprocessing and the waste management are carried out with spent fuels, high-level liquid waste, TRU etc. in the α γ cell and glove boxes. NUCEF was constructed with the following aims. Using STACY and TRACY, are aimed, (1) research on advanced technology for criticality safety control, (2) reconfirmation of criticality safety margin of the Rokkasho reprocessing plant. Using BECKY, are aimed, (1) research on advanced technology of reprocessing process, (2) contribution to develop the scenario for TRU waste disposal, (3) development of new technology for TRU partitioning and volume reduction of radioactive waste. To realize the above aims, following 5 research subjects are settled in NUCEF, (1) Criticality safety research, (2) Research on safety and advanced technology of fuel reprocessing, (3) Research on TRU waste management, (4) Fundamental research on TRU chemistry, (5) Key technology development for TRU processing. (author)

Radioactive wastes management

International Nuclear Information System (INIS)

Albert, Ph.

1999-01-01

This article presents the French way to deal with nuclear wastes. 4 categories of radioactive wastes have been defined: 1) very low-level wastes (TFA), 2) low or medium-wastes with short or medium half-life (A), 3) low or medium-level wastes with long half-life (B), and 4) high-level wastes with long half-life (C). ANDRA (national agency for the management of radioactive wastes) manages 2 sites of definitive surface storage (La-Manche and Aube centers) for TFA-wastes. The Aube center allows the storage of A-wastes whose half-life is less than 30 years. This site will receive waste packages for 50 years and will require a regular monitoring for 300 years after its decommissioning. No definitive solutions have been taken for B and C wastes, they are temporarily stored at La Hague processing plant. Concerning these wastes the French parliament will have to take a decision by 2006. At this date and within the framework of the Bataille law (1991), scientific studies concerning the definitive or retrievable storage, the processing techniques (like transmutation) will have been achieved and solutions will be proposed. These studies are numerous, long and complex, they involve fresh knowledge in geology, chemistry, physics,.. and they have implied the setting of underground facilities in order to test and validate solutions in situ. This article presents also the transmutation technique. (A.C.)

40 CFR 268.35 - Waste specific prohibitions-petroleum refining wastes.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Waste specific prohibitions-petroleum refining wastes. 268.35 Section 268.35 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED... generator may use knowledge of the waste. If the waste contains constituents in excess of the applicable...

40 CFR 268.36 - Waste specific prohibitions-inorganic chemical wastes

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 26 2010-07-01 2010-07-01 false Waste specific prohibitions-inorganic chemical wastes 268.36 Section 268.36 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED... generator may use knowledge of the waste. If the waste contains regulated constituents in excess of the...

Waste segregation

International Nuclear Information System (INIS)

Clark, D.E.; Colombo, P.

1982-01-01

A scoping study has been undertaken to determine the state-of-the-art of waste segregation technology as applied to the management of low-level waste (LLW). Present-day waste segregation practices were surveyed through a review of the recent literature and by means of personal interviews with personnel at selected facilities. Among the nuclear establishments surveyed were Department of Energy (DOE) laboratories and plants, nuclear fuel cycle plants, public and private laboratories, institutions, industrial plants, and DOE and commercially operated shallow land burial sites. These survey data were used to analyze the relationship between waste segregation practices and waste treatment/disposal processes, to assess the developmental needs for improved segregation technology, and to evaluate the costs and benefits associated with the implementation of waste segregation controls. This task was planned for completion in FY 1981. It should be noted that LLW management practices are now undergoing rapid change such that the technology and requirements for waste segregation in the near future may differ significantly from those of the present day. 8 figures

Industrial Waste

DEFF Research Database (Denmark)

Christensen, Thomas Højlund

2011-01-01

generation rates and material composition as well as determining factors are discussed in this chapter. Characterizing industrial waste is faced with the problem that often only a part of the waste is handled in the municipal waste system, where information is easily accessible. In addition part...... of the industrial waste may in periods, depending on market opportunities and prices, be traded as secondary rawmaterials. Production-specificwaste from primary production, for example steel slag, is not included in the current presentation. In some countries industries must be approved or licensed and as part...... of the system industry has to inform at the planning stage and afterwards in yearly reports on their waste arising and how the waste is managed. If available such information is very helpful in obtaining information about that specific industry. However, in many countries there is very little information...

Rethinking the waste hierarchy

Energy Technology Data Exchange (ETDEWEB)

Rasmussen, C; Vigsoe, D [eds.

2005-03-01

There is an increasing need to couple environmental and economic considerations within waste management. Consumers and companies alike generate ever more waste. The waste-policy challenges of the future lie in decoupling growth in waste generation from growth in consumption, and in setting priorities for the waste management. This report discusses the criteria for deciding priorities for waste management methods, and questions the current principles of EU waste policies. The basis for the discussion is the so-called waste hierarchy which has dominated the waste policy in the EU since the mid-1970s. The waste hierarchy ranks possible methods of waste management. According to the waste hierarchy, the very best solution is to reduce the amount of waste. After that, reuse is preferred to recycling which, in turn, is preferred to incineration. Disposal at a landfill is the least favourable solution. (BA)

Waste minimization/pollution prevention study of high-priority waste streams

International Nuclear Information System (INIS)

Ogle, R.B.

1994-03-01

Although waste minimization has been practiced by the Metals and Ceramics (M ampersand C) Division in the past, the effort has not been uniform or formalized. To establish the groundwork for continuous improvement, the Division Director initiated a more formalized waste minimization and pollution prevention program. Formalization of the division's pollution prevention efforts in fiscal year (FY) 1993 was initiated by a more concerted effort to determine the status of waste generation from division activities. The goal for this effort was to reduce or minimize the wastes identified as having the greatest impact on human health, the environment, and costs. Two broad categories of division wastes were identified as solid/liquid wastes and those relating to energy use (primarily electricity and steam). This report presents information on the nonradioactive solid and liquid wastes generated by division activities. More specifically, the information presented was generated by teams of M ampersand C staff members empowered by the Division Director to study specific waste streams

Analysis on 3RWB model (Reduce, reuse, recycle, and waste bank) in comprehensive waste management toward community-based zero waste

Science.gov (United States)

Affandy, Nur Azizah; Isnaini, Enik; Laksono, Arif Budi

2017-06-01

Waste management becomes a serious issue in Indonesia. Significantly, waste production in Lamongan Regency is increasing in linear with the growth of population and current people activities, creating a gap between waste production and waste management. It is a critical problem that should be solved immediately. As a reaction to the issue, the Government of Lamongan Regency has enacted a new policy regarding waste management through a program named Lamongan Green and Clean (LGC). From the collected data, it showed that the "wet waste" or "organic waste" was approximately 63% of total domestic waste. With such condition, it can be predicted that the trashes will decompose quite quickly. From the observation, it was discovered that the generated waste was approximately 0.25 kg/person/day. Meanwhile, the number of population in Tumenggungan Village, Lamongan (data obtained from Monograph in Lamongan district, 2012) was 4651 people. Thus, it can be estimated the total waste in Lamongan was approximately 0.25 kg/person/day x 4651 characters = 930 kg/day. Within 3RWB Model, several stages have to be conducted. In the planning stage, the promotion of self-awareness among the communities in selecting and managing waste due to their interest in a potential benefit, is done. It indicated that community's awareness of waste management waste grew significantly. Meanwhile in socialization stage, each village staff, environmental expert, and policymaker should bear significant role in disseminating the awareness among the people. In the implementation phase, waste management with 3RWB model is promoted by applying it among of the community, starting from selection, waste management, until recycled products sale through the waste bank. In evaluation stage, the village managers, environmental expert, and waste managers are expected to regularly supervise and evaluate the whole activity of the waste management.

IGNEOUS INTRUSION IMPACTS ON WASTE PACKAGES AND WASTE FORMS

International Nuclear Information System (INIS)

Bernot, P.

2004-01-01

The purpose of this model report is to assess the potential impacts of igneous intrusion on waste packages and waste forms in the emplacement drifts at the Yucca Mountain Repository. The models are based on conceptual models and includes an assessment of deleterious dynamic, thermal, hydrologic, and chemical impacts. The models described in this report constitute the waste package and waste form impacts submodel of the Total System Performance Assessment for the License Application (TSPA-LA) model assessing the impacts of a hypothetical igneous intrusion event on the repository total system performance. This submodel is carried out in accordance with Technical Work Plan for Waste Form Degradation Modeling, Testing, and Analyses in Support of LA (BSC 2004 [DIRS:167796]) and Total System Performance Assessment-License Application Methods and Approaches (BSC 2003 [DIRS: 166296]). The technical work plan was prepared in accordance with AP-2.27Q, Planning for Science Activities. Any deviations from the technical work plan are documented in the following sections as they occur. The TSPA-LA approach to implementing the models for waste package and waste form response during igneous intrusion is based on identification of damage zones. Zone 1 includes all emplacement drifts intruded by the basalt dike, and Zone 2 includes all other emplacement drifts in the repository that are not in Zone 1. This model report will document the following model assessments: (1) Mechanical and thermal impacts of basalt magma intrusion on the invert, waste packages and waste forms of the intersected emplacement drifts of Zone 1. (2) Temperature and pressure trends of basaltic magma intrusion intersecting Zone 1 and their potential effects on waste packages and waste forms in Zone 2 emplacement drifts. (3) Deleterious volatile gases, exsolving from the intruded basalt magma and their potential effects on waste packages of Zone 2 emplacement drifts. (4) Post-intrusive physical

Importance of waste composition for Life Cycle Assessment of waste management solutions

DEFF Research Database (Denmark)

Bisinella, Valentina; Götze, Ramona; Conradsen, Knut

2017-01-01

The composition of waste materials has fundamental influence on environmental emissions associated with waste treatment, recycling and disposal, and may play an important role also for the Life Cycle Assessment (LCA) of waste management solutions. However, very few assessments include effects...... of the waste composition and waste LCAs often rely on poorly justified data from secondary sources. This study systematically quantifiesy the influence and uncertainty on LCA results associated with selection of waste composition data. Three archetypal waste management scenarios were modelled with the waste...... LCA model EASETECH based on detailed waste composition data from the literature. The influence from waste composition data on the LCA results was quantified with a step-wise Global Sensitivity Analysis (GSA) approach involving contribution, sensitivity, uncertainty and discernibility analyses...

Hanford Tank Waste - Near Source Treatment of Low Activity Waste

International Nuclear Information System (INIS)

Ramsey, William Gene

2013-01-01

Abstract only. Treatment and disposition of Hanford Site waste as currently planned consists of 100+ waste retrievals, waste delivery through up to 8+ miles of dedicated, in-ground piping, centralized mixing and blending operations- all leading to pre-treatment combination and separation processes followed by vitrification at the Hanford Tank Waste Treatment and Immobilization Plant (WTP). The sequential nature of Tank Farm and WTP operations requires nominally 15-20 years of continuous operations before all waste can be retrieved from many Single Shell Tanks (SSTs). Also, the infrastructure necessary to mobilize and deliver the waste requires significant investment beyond that required for the WTP. Treating waste as closely as possible to individual tanks or groups- as allowed by the waste characteristics- is being investigated to determine the potential to 1) defer, reduce, and/or eliminate infrastructure requirements, and 2) significantly mitigate project risk by reducing the potential and impact of single point failures. The inventory of Hanford waste slated for processing and disposition as LAW is currently managed as high-level waste (HLW), i.e., the separation of fission products and other radionuclides has not commenced. A significant inventory of this waste (over 20M gallons) is in the form of precipitated saltcake maintained in single shell tanks, many of which are identified as potential leaking tanks. Retrieval and transport (as a liquid) must be staged within the waste feed delivery capability established by site infrastructure and WTP. Near Source treatment, if employed, would provide for the separation and stabilization processing necessary for waste located in remote farms (wherein most of the leaking tanks reside) significantly earlier than currently projected. Near Source treatment is intended to address the currently accepted site risk and also provides means to mitigate future issues likely to be faced over the coming decades. This paper

WASTE-ACC: A computer model for analysis of waste management accidents

International Nuclear Information System (INIS)

Nabelssi, B.K.; Folga, S.; Kohout, E.J.; Mueller, C.J.; Roglans-Ribas, J.

1996-12-01

In support of the U.S. Department of Energy's (DOE's) Waste Management Programmatic Environmental Impact Statement, Argonne National Laboratory has developed WASTE-ACC, a computational framework and integrated PC-based database system, to assess atmospheric releases from facility accidents. WASTE-ACC facilitates the many calculations for the accident analyses necessitated by the numerous combinations of waste types, waste management process technologies, facility locations, and site consolidation strategies in the waste management alternatives across the DOE complex. WASTE-ACC is a comprehensive tool that can effectively test future DOE waste management alternatives and assumptions. The computational framework can access several relational databases to calculate atmospheric releases. The databases contain throughput volumes, waste profiles, treatment process parameters, and accident data such as frequencies of initiators, conditional probabilities of subsequent events, and source term release parameters of the various waste forms under accident stresses. This report describes the computational framework and supporting databases used to conduct accident analyses and to develop source terms to assess potential health impacts that may affect on-site workers and off-site members of the public under various DOE waste management alternatives

Radioactive waste management

International Nuclear Information System (INIS)

Kawakami, Yutaka

2008-01-01

Radioactive waste generated from utilization of radioisotopes and each step of the nuclear fuel cycle and decommissioning of nuclear facilities are presented. On the safe management of radioactive waste management, international safety standards are established such as ''The Principles of Radioactive Waste Management (IAEA)'' and T he Joint Convention on the Safety of Radioactive Waste Management . Basic steps of radioactive waste management consist of treatment, conditioning and disposal. Disposal is the final step of radioactive waste management and its safety is confirmed by safety assessment in the licensing process. Safety assessment means evaluation of radiation dose rate caused by radioactive materials contained in disposed radioactive waste. The results of the safety assessment are compared with dose limits. The key issues of radioactive waste disposal are establishment of long term national strategies and regulations for safe management of radioactive waste, siting of repository, continuity of management activities and financial bases for long term, and security of human resources. (Author)

Integrated solid waste management: a palliative to existing waste ...

African Journals Online (AJOL)

As a concept, Integrated Solid Waste Management (ISWM) is a sustainable ... on the perspective of consumers on waste generation, collection and disposal. ... to effective solid waste management in the case study area; non-sorting and ...

Mixed waste and waste minimization: The effect of regulations and waste minimization on the laboratory

International Nuclear Information System (INIS)

Dagan, E.B.; Selby, K.B.

1993-08-01

The Hanford Site is located in the State of Washington and is subject to state and federal environmental regulations that hamper waste minimization efforts. This paper addresses the negative effect of these regulations on waste minimization and mixed waste issues related to the Hanford Site. Also, issues are addressed concerning the regulations becoming more lenient. In addition to field operations, the Hanford Site is home to the Pacific Northwest Laboratory which has many ongoing waste minimization activities of particular interest to laboratories

Waste Information Management System with 2012-13 Waste Streams - 13095

International Nuclear Information System (INIS)

Upadhyay, H.; Quintero, W.; Lagos, L.; Shoffner, P.; Roelant, D.

2013-01-01

The Waste Information Management System (WIMS) 2012-13 was updated to support the Department of Energy (DOE) accelerated cleanup program. The schedule compression required close coordination and a comprehensive review and prioritization of the barriers that impeded treatment and disposition of the waste streams at each site. Many issues related to waste treatment and disposal were potential critical path issues under the accelerated schedule. In order to facilitate accelerated cleanup initiatives, waste managers at DOE field sites and at DOE Headquarters in Washington, D.C., needed timely waste forecast and transportation information regarding the volumes and types of radioactive waste that would be generated by DOE sites over the next 40 years. Each local DOE site historically collected, organized, and displayed waste forecast information in separate and unique systems. In order for interested parties to understand and view the complete DOE complex-wide picture, the radioactive waste and shipment information of each DOE site needed to be entered into a common application. The WIMS application was therefore created to serve as a common application to improve stakeholder comprehension and improve DOE radioactive waste treatment and disposal planning and scheduling. WIMS allows identification of total forecasted waste volumes, material classes, disposition sites, choke points, technological or regulatory barriers to treatment and disposal, along with forecasted waste transportation information by rail, truck and inter-modal shipments. The Applied Research Center (ARC) at Florida International University (FIU) in Miami, Florida, developed and deployed the web-based forecast and transportation system and is responsible for updating the radioactive waste forecast and transportation data on a regular basis to ensure the long-term viability and value of this system. (authors)

Waste Information Management System with 2012-13 Waste Streams - 13095

Energy Technology Data Exchange (ETDEWEB)

Upadhyay, H.; Quintero, W.; Lagos, L.; Shoffner, P.; Roelant, D. [Applied Research Center, Florida International University, 10555 West Flagler Street, Suite 2100, Miami, FL 33174 (United States)

2013-07-01

The Waste Information Management System (WIMS) 2012-13 was updated to support the Department of Energy (DOE) accelerated cleanup program. The schedule compression required close coordination and a comprehensive review and prioritization of the barriers that impeded treatment and disposition of the waste streams at each site. Many issues related to waste treatment and disposal were potential critical path issues under the accelerated schedule. In order to facilitate accelerated cleanup initiatives, waste managers at DOE field sites and at DOE Headquarters in Washington, D.C., needed timely waste forecast and transportation information regarding the volumes and types of radioactive waste that would be generated by DOE sites over the next 40 years. Each local DOE site historically collected, organized, and displayed waste forecast information in separate and unique systems. In order for interested parties to understand and view the complete DOE complex-wide picture, the radioactive waste and shipment information of each DOE site needed to be entered into a common application. The WIMS application was therefore created to serve as a common application to improve stakeholder comprehension and improve DOE radioactive waste treatment and disposal planning and scheduling. WIMS allows identification of total forecasted waste volumes, material classes, disposition sites, choke points, technological or regulatory barriers to treatment and disposal, along with forecasted waste transportation information by rail, truck and inter-modal shipments. The Applied Research Center (ARC) at Florida International University (FIU) in Miami, Florida, developed and deployed the web-based forecast and transportation system and is responsible for updating the radioactive waste forecast and transportation data on a regular basis to ensure the long-term viability and value of this system. (authors)

Surrogate formulations for thermal treatment of low-level mixed waste, Part II: Selected mixed waste treatment project waste streams

Energy Technology Data Exchange (ETDEWEB)

Bostick, W.D.; Hoffmann, D.P.; Chiang, J.M.; Hermes, W.H.; Gibson, L.V. Jr.; Richmond, A.A. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States); Mayberry, J. [Science Applications International Corp., Idaho Falls, ID (United States); Frazier, G. [Univ. of Tennessee, Knoxville, TN (United States)

1994-01-01

This report summarizes the formulation of surrogate waste packages, representing the major bulk constituent compositions for 12 waste stream classifications selected by the US DOE Mixed Waste Treatment Program. These waste groupings include: neutral aqueous wastes; aqueous halogenated organic liquids; ash; high organic content sludges; adsorbed aqueous and organic liquids; cement sludges, ashes, and solids; chloride; sulfate, and nitrate salts; organic matrix solids; heterogeneous debris; bulk combustibles; lab packs; and lead shapes. Insofar as possible, formulation of surrogate waste packages are referenced to authentic wastes in inventory within the DOE; however, the surrogate waste packages are intended to represent generic treatability group compositions. The intent is to specify a nonradiological synthetic mixture, with a minimal number of readily available components, that can be used to represent the significant challenges anticipated for treatment of the specified waste class. Performance testing and evaluation with use of a consistent series of surrogate wastes will provide a means for the initial assessment (and intercomparability) of candidate treatment technology applicability and performance. Originally the surrogate wastes were intended for use with emerging thermal treatment systems, but use may be extended to select nonthermal systems as well.

Surrogate formulations for thermal treatment of low-level mixed waste, Part II: Selected mixed waste treatment project waste streams

International Nuclear Information System (INIS)

Bostick, W.D.; Hoffmann, D.P.; Chiang, J.M.; Hermes, W.H.; Gibson, L.V. Jr.; Richmond, A.A.; Mayberry, J.; Frazier, G.

1994-01-01

This report summarizes the formulation of surrogate waste packages, representing the major bulk constituent compositions for 12 waste stream classifications selected by the US DOE Mixed Waste Treatment Program. These waste groupings include: neutral aqueous wastes; aqueous halogenated organic liquids; ash; high organic content sludges; adsorbed aqueous and organic liquids; cement sludges, ashes, and solids; chloride; sulfate, and nitrate salts; organic matrix solids; heterogeneous debris; bulk combustibles; lab packs; and lead shapes. Insofar as possible, formulation of surrogate waste packages are referenced to authentic wastes in inventory within the DOE; however, the surrogate waste packages are intended to represent generic treatability group compositions. The intent is to specify a nonradiological synthetic mixture, with a minimal number of readily available components, that can be used to represent the significant challenges anticipated for treatment of the specified waste class. Performance testing and evaluation with use of a consistent series of surrogate wastes will provide a means for the initial assessment (and intercomparability) of candidate treatment technology applicability and performance. Originally the surrogate wastes were intended for use with emerging thermal treatment systems, but use may be extended to select nonthermal systems as well

The data-base of properties of actinides for metal fuels

International Nuclear Information System (INIS)

Inoue, Tadashi; Kurata, Masateru

1989-01-01

It is developed the technology that transuranium elements (TRUs) to be recovered from high active wastes transmute into relatively short lived nuclides by burning them within metallic fuel alloys. In this paper, we collect published data of properties of TRUs and U-Pu(-Zr) alloys and make up the data base for the design study of alloys with TRUs. In addition, the data base possesses a function of statistic analysis in order to facilitate the comparison of data and can afford to estimate properties. This data base collects (1) properties affecting fuel temperature and microstructure, (2) mechanical properties and (3) fundamental properties such as hardness and density, and furthermore, (1) fission gas release, (2) swelling and (3) fuel-cladding interaction and eutectic property as irradiation behavior. (author)

Artificial radionuclides in an intertidal sediment from northwest England

International Nuclear Information System (INIS)

Morris, K.; Keith-Roach, M.J.; Butterworth, J.C.; Livens, L.K.; Day, J.P.; Hursthouse, A.S.; Fifield, L.K.; Bardgett, R.D.

1998-01-01

An intertidal sediment core has been analysed for the principal transuranium elements present in the BNFL Sellafield radioactive waste discharges (Np, Pu, Am) and the high yield fission products 99 Tc and 137 Cs. Interstitial water samples were collected using porous cup samplers and early results from these analyses show that there is a pronounced seasonality in the pattern of dissolved Pu, which apparently relates to changes in dissolved Fe and Mn. More recent work has concentrated on the characterization of changes in the sediment microbial community and on the development of analytical methods for the analysis of dissolved Np, apparently the most readily mobilized of the transuranic elements, which is present at concentrations of the order of 10 8 atoms/litre

Nuclear power without a risk is possible

International Nuclear Information System (INIS)

Thom, K.

1977-01-01

This popular-science article introductorily deals with the great danger arising from the continous plutonium production of common nuclear reactors and indicates a new gas nuclear reactor technology which is at present being followed by NASA. In this new type of breeder reactor a) gaseous thorium compounds or UF 6 are to be used as fuels externally introduced, b) the transuranium elements obtained from the nuclear fission, especially plutonium, are to be continuously recycled into the reactor and finally completely used up. The advantage of this reactor is considered to be, amongst other, that fissionable material usuable for the making of atom bombs, is no longer present in the atomic waste and the slight critical mass rules out reactor catastrophies. (GG) [de

Transportation considerations related to waste forms and canisters for Defense TRU wastes

International Nuclear Information System (INIS)

Schneider, K.J.; Andrews, W.B.; Schreiber, A.M.; Rosenthal, L.J.; Odle, C.J.

1981-09-01

This report identifies and discusses the considerations imposed by transportation on waste forms and canisters for contact-handled, solid transuranic wastes from the US Department of Energy (DOE) activities. The report reviews (1) the existing raw waste forms and potential immobilized waste forms, (2) the existing and potential future DOE waste canisters and shipping containers, (3) regulations and regulatory trends for transporting commercial transuranic wastes on the ISA, (4) truck and rail carrier requirements and preferences for transporting the wastes, and (5) current and proposed Type B external packagings for transporting wastes

Waste statistics 2004

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-04-07

The 2004 reporting to the ISAG comprises 394 plants owned by 256 enterprises. In 2003, reports covered 403 plants owned by 273 enterprises. Waste generation in 2004 is compared to targets for 2008 in the government's Waste Strategy 2005-2008. The following summarises waste generation in 2004: 1) In 2004, total reported waste arisings amounted to 13,359,000 tonnes, which is 745,000 tonnes, or 6 per cent, more than in 2003. 2) If amounts of residues from coal-fired power plants are excluded from statistics, waste arisings in 2004 were 12,179,000 tonnes, which is a 9 per cent increase from 2003. 3) If amounts of residues from coal-fired power plants and waste from the building and construction sector are excluded from statistics, total waste generation in 2004 amounted to 7,684,000 tonnes, which is 328,000 tonnes, or 4 per cent, more than in 2002. In other words, there has been an increase in total waste arisings, if residues and waste from building and construction are excluded. Waste from the building and construction sector is more sensitive to economic change than most other waste. 4) The total rate of recycling was 65 per cent. The 2008 target for recycling is 65 per cent. The rate of recycling in 2003 was also 65 per cent. 5) The total amount of waste led to incineration amounted to 26 per cent, plus an additional 1 per cent left in temporary storage to be incinerated at a later time. The 2008 target for incineration is 26 per cent. These are the same percentage figures as applied to incineration and storage in 2003. 6) The total amount of waste led to landfills amounted to 8 per cent, which is one percentage point better than the overall landfill target of a maximum of 9 per cent landfilling in 2008. Also in 2003, 8 per cent of the waste was landfilled. 7) The targets for treatment of waste from individual sectors are still not being met: too little waste from households and the service sector is being recycled, and too much waste from industry is being

The Hazardous Waste/Mixed Waste Disposal Facility

International Nuclear Information System (INIS)

Bailey, L.L.

1991-01-01

The Hazardous Waste/Mixed Waste Disposal Facility (HW/MWDF) will provide permanent Resource Conservation and Recovery Act (RCRA) permitted storage, treatment, and disposal for hazardous and mixed waste generated at the Department of Energy's (DOE) Savannah River Site (SRS) that cannot be disposed of in existing or planned SRS facilities. Final design is complete for Phase I of the project, the Disposal Vaults. The Vaults will provide RCRA permitted, above-grade disposal capacity for treated hazardous and mixed waste generated at the SRS. The RCRA Part B Permit application was submitted upon approval of the Permit application, the first Disposal Vault is scheduled to be operational in mid 1994. The technical baseline has been established for Phase II, the Treatment Building, and preliminary design work has been performed. The Treatment Building will provide RCRA permitted treatment processes to handle a variety of hazardous and mixed waste generated at SRS in preparation for disposal. The processes will treat wastes for disposal in accordance with the Environmental Protection Agency's (EPA's) Land Disposal Restrictions (LDR). A RCRA Part B Permit application has not yet been submitted to SCDHEC for this phase of the project. The Treatment Building is currently scheduled to be operational in late 1996

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.)

SECONDARY WASTE MANAGEMENT STRATEGY FOR EARLY LOW ACTIVITY WASTE TREATMENT

Energy Technology Data Exchange (ETDEWEB)

TW, CRAWFORD

2008-07-17

This study evaluates parameters relevant to River Protection Project secondary waste streams generated during Early Low Activity Waste operations and recommends a strategy for secondary waste management that considers groundwater impact, cost, and programmatic risk. The recommended strategy for managing River Protection Project secondary waste is focused on improvements in the Effiuent Treatment Facility. Baseline plans to build a Solidification Treatment Unit adjacent to Effluent Treatment Facility should be enhanced to improve solid waste performance and mitigate corrosion of tanks and piping supporting the Effiuent Treatment Facility evaporator. This approach provides a life-cycle benefit to solid waste performance and reduction of groundwater contaminants.

Waste processing practices at waste management department from INR

International Nuclear Information System (INIS)

Bujoreanu, D.; Bujoreanu, L.

2010-01-01

The Institute for Nuclear Research Pitesti (INR), subsidiary of the Romanian Authority for Nuclear Activities has its own Radioactive Waste Treatment Plant (STDR). The object of activity of STDR within the INR Pitesti is to treat and condition radioactive waste resulted from the nuclear facility. Also, it will must prepare and manage the decommissioning projects of its own facilities and to upgrade the facilities for the management of the radioactive waste resulting from other decommissioning activities. In according with the National Nuclear Program and the Governmental order no. 11/2003, the Institute for Nuclear Research is the main support for implementation of the methods and technologies for conditioning and disposal of radioactive waste generated by the decommissioning of nuclear facilities. The classes and criteria of classification for radioactive waste generated in operation and decommissioning in Romania are established in compliance with the classification recommended by IAEA and generally valid in EU countries. The general classification takes into consideration the disposal requirements to isolate the radioactive waste from environment. In Romania, waste minimization is considered by Order No. 56/2004 of CNCAN President for approval of Fundamental regulations on the safe management of radioactive waste. According to this regulation, the generation of radioactive waste is to be kept to the minimum practicable level in terms of both its activity and volume through appropriate design measures, facility operation and decommissioning practices. In order to meet this requirement, the operator must ensure: - selection and control of materials; - recycling and reuse of materials, including clearance of materials; - implementing adequate operating procedures, including those referring to the physical, chemical and radiological characterization of the waste and sorting of different type of materials. (orig.)

Development of analytical methods for the separation of plutonium, americium, curium and neptunium from environmental samples

Energy Technology Data Exchange (ETDEWEB)

Salminen, S.

2009-07-01

In this work, separation methods have been developed for the analysis of anthropogenic transuranium elements plutonium, americium, curium and neptunium from environmental samples contaminated by global nuclear weapons testing and the Chernobyl accident. The analytical methods utilized in this study are based on extraction chromatography. Highly varying atmospheric plutonium isotope concentrations and activity ratios were found at both Kurchatov (Kazakhstan), near the former Semipalatinsk test site, and Sodankylae (Finland). The origin of plutonium is almost impossible to identify at Kurchatov, since hundreds of nuclear tests were performed at the Semipalatinsk test site. In Sodankylae, plutonium in the surface air originated from nuclear weapons testing, conducted mostly by USSR and USA before the sampling year 1963. The variation in americium, curium and neptunium concentrations was great as well in peat samples collected in southern and central Finland in 1986 immediately after the Chernobyl accident. The main source of transuranium contamination in peats was from global nuclear test fallout, although there are wide regional differences in the fraction of Chernobyl-originated activity (of the total activity) for americium, curium and neptunium. The separation methods developed in this study yielded good chemical recovery for the elements investigated and adequately pure fractions for radiometric activity determination. The extraction chromatographic methods were faster compared to older methods based on ion exchange chromatography. In addition, extraction chromatography is a more environmentally friendly separation method than ion exchange, because less acidic waste solutions are produced during the analytical procedures. (orig.)

WASTES: Waste System Transportation and Economic Simulation--Version 2:

International Nuclear Information System (INIS)

Sovers, R.A.; Shay, M.R.; Ouderkirk, S.J.; McNair, G.W.; Eagle, B.G.

1988-02-01

The Waste System Transportation and Economic Simulation (WASTES) Technical Reference Manual was written to describe and document the algorithms used within the WASTES model as implemented in Version 2.23. The manual will serve as a reference for users of the WASTES system. The intended audience for this manual are knowledgeable users of WASTES who have an interest in the underlying principles and algorithms used within the WASTES model. Each algorithm is described in nonprogrammers terminology, and the source and uncertainties of the constants in use by these algorithms are described. The manual also describes the general philosophy and rules used to: 1) determine the allocation and priority of spent fuel generation sources to facility destinations, 2) calculate transportation costs, and 3) estimate the cost of at-reactor ex-pool storage. A detailed description of the implementation of many of the algorithms is also included in the WASTES Programmers Reference Manual (Shay and Buxbaum 1986a). This manual is separated into sections based on the general usage of the algorithms being discussed. 8 refs., 14 figs., 2 tabs

Radioactive wastes

International Nuclear Information System (INIS)

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

1994-01-01

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

Waste disposal

International Nuclear Information System (INIS)

Neerdael, B.; Marivoet, J.; Put, M.; Verstricht, J.; Van Iseghem, P.; Buyens, M.

1998-01-01

The primary mission of the Waste Disposal programme at the Belgian Nuclear Research Centre SCK/CEN is to propose, develop, and assess solutions for the safe disposal of radioactive waste. In Belgium, deep geological burial in clay is the primary option for the disposal of High-Level Waste and spent nuclear fuel. The main achievements during 1997 in the following domains are described: performance assessment, characterization of the geosphere, characterization of the waste, migration processes, underground infrastructure

Analysis of waste treatment requirements for DOE mixed wastes: Technical basis

International Nuclear Information System (INIS)

1995-02-01

The risks and costs of managing DOE wastes are a direct function of the total quantities of 3wastes that are handled at each step of the management process. As part of the analysis of the management of DOE low-level mixed wastes (LLMW), a reference scheme has been developed for the treatment of these wastes to meet EPA criteria. The treatment analysis in a limited form was also applied to one option for treatment of transuranic wastes. The treatment requirements in all cases analyzed are based on a reference flowsheet which provides high level treatment trains for all LLMW. This report explains the background and basis for that treatment scheme. Reference waste stream chemical compositions and physical properties including densities were established for each stream in the data base. These compositions are used to define the expected behavior for wastes as they pass through the treatment train. Each EPA RCRA waste code was reviewed, the properties, chemical composition, or characteristics which are of importance to waste behavior in treatment were designated. Properties that dictate treatment requirements were then used to develop the treatment trains and identify the unit operations that would be included in these trains. A table was prepared showing a correlation of the waste physical matrix and the waste treatment requirements as a guide to the treatment analysis. The analysis of waste treatment loads is done by assigning wastes to treatment steps which would achieve RCRA compliant treatment. These correlation's allow one to examine the treatment requirements in a condensed manner and to see that all wastes and contaminant sets are fully considered

End-of-waste criteria for waste plastic for conversion. Technical proposals.

OpenAIRE

VILLANUEVA KRZYZANIAK Alejandro; EDER Peter

2014-01-01

This report is the JRC-IPTS contribution to the development of the end-of-waste criteria for waste plastic in accordance with Article 6 of Directive 2008/98/EC of the European Parliament and of the Council on waste (the Waste Framework Directive). This report includes a possible set of end-of-waste criteria and shows how the proposals were developed based on a comprehensive techno-economic analysis of the waste plastic production chain and an analysis of the economic, environmental and le...

Introduction to Waste Management

DEFF Research Database (Denmark)

Christensen, Thomas Højlund

2011-01-01

Solid waste management is as old as human civilization, although only considered an engineering discipline for about one century. The change from the previous focus on public cleansing of the cities to modern waste management was primarily driven by industrialization, which introduced new materials...... and chemicals, dramatically changing the types and composition of waste, and by urbanization making waste management in urban areas a complicated and costly logistic operation. This book focuses on waste that commonly appears in the municipal waste management system. This chapter gives an introduction to modern...... waste management, including issues as waste definition, problems associated with waste, waste management criteria and approaches to waste management. Later chapters introduce aspects of engineering (Chapter 1.2), economics (Chapter 1.3) and regulation (Chapter 1.4)....

Mixed waste: Proceedings

International Nuclear Information System (INIS)

Moghissi, A.A.; Blauvelt, R.K.; Benda, G.A.; Rothermich, N.E.

1993-01-01

This volume contains the peer-reviewed and edited versions of papers submitted for presentation a the Second International Mixed Waste Symposium. Following the tradition of the First International Mixed Waste Symposium, these proceedings were prepared in advance of the meeting for distribution to participants. The symposium was organized by the Mixed Waste Committee of the American Society of Mechanical Engineers. The topics discussed at the symposium include: stabilization technologies, alternative treatment technologies, regulatory issues, vitrification technologies, characterization of wastes, thermal technologies, laboratory and analytical issues, waste storage and disposal, organic treatment technologies, waste minimization, packaging and transportation, treatment of mercury contaminated wastes and bioprocessing, and environmental restoration. Individual abstracts are catalogued separately for the data base

Mixed waste: Proceedings

Energy Technology Data Exchange (ETDEWEB)

Moghissi, A.A.; Blauvelt, R.K.; Benda, G.A.; Rothermich, N.E. [eds.] [Temple Univ., Philadelphia, PA (United States). Dept. of Environmental Safety and Health

1993-12-31

This volume contains the peer-reviewed and edited versions of papers submitted for presentation a the Second International Mixed Waste Symposium. Following the tradition of the First International Mixed Waste Symposium, these proceedings were prepared in advance of the meeting for distribution to participants. The symposium was organized by the Mixed Waste Committee of the American Society of Mechanical Engineers. The topics discussed at the symposium include: stabilization technologies, alternative treatment technologies, regulatory issues, vitrification technologies, characterization of wastes, thermal technologies, laboratory and analytical issues, waste storage and disposal, organic treatment technologies, waste minimization, packaging and transportation, treatment of mercury contaminated wastes and bioprocessing, and environmental restoration. Individual abstracts are catalogued separately for the data base.

Energy from waste: a wholly acceptable waste-management solution

International Nuclear Information System (INIS)

Porteous, A.

1997-01-01

This paper briefly reviews the 'waste management hierarchy' and why it should be treated as a checklist and not a piece of unquestioning dogma. The role of energy from waste (EfW) is examined in depth to show that it is a rigorous and environmentally sound waste-management option which complements other components of the waste-management hierarchy and assists resource conservation. (Copyright (c) 1997 Elsevier Science B.V., Amsterdam. All rights reserved.)

ALTENER. Strategic framework municipal solid waste. Waste for energy network

International Nuclear Information System (INIS)

Kwant, K.W.; Van Halen, C.; Pfeiffer, A.E.

1997-01-01

General objective of European, national and regional waste for energy (WfE) policies is to support sustainable development. In each of the Altener WfE countries (Austria, Denmark, Finland, Italy, Netherlands, Portugal, Spain, Sweden and UK) general waste management strategies have been implemented. Common aspects are waste management hierarchies and general objectives such as: (1) to reduce the amount of wastes; (2) to make the best use of the wastes that are produced; and (3) to choose waste management practices, which (4) minimise the risks of immediate and future environmental pollution and harm to human health. All WfE countries have defined an order of preference for waste handling, starting with prevention as most preferred option, through re-use and recycling, thermal treatment with energy-recovery to landfill as a least desired option. In all Altener WfE countries, waste management structures are in a phase of transformation. At least three general transition processes can be recognized to take place, which are of great importance for the waste for energy future of the Altener countries: (1) increased energy recovery from MSW; (2) increased separation of MSW for recycling and recovery; and (3) reorganization of landfills. Two groups of instruments to stimulate the use of waste to energy are distinguished: (1) instruments, aiming to create improved WfE solutions; and (2) instruments, aiming to create a WfE market. In this framework document an overview is given of today's WfE situation in 9 European countries, as well as up-to-date national waste and energy policies, including the available instruments and future goals

Food waste and food processing waste for biohydrogen production: a review.

Science.gov (United States)

Yasin, Nazlina Haiza Mohd; Mumtaz, Tabassum; Hassan, Mohd Ali; Abd Rahman, Nor'Aini

2013-11-30

Food waste and food processing wastes which are abundant in nature and rich in carbon content can be attractive renewable substrates for sustainable biohydrogen production due to wide economic prospects in industries. Many studies utilizing common food wastes such as dining hall or restaurant waste and wastes generated from food processing industries have shown good percentages of hydrogen in gas composition, production yield and rate. The carbon composition in food waste also plays a crucial role in determining high biohydrogen yield. Physicochemical factors such as pre-treatment to seed culture, pH, temperature (mesophilic/thermophilic) and etc. are also important to ensure the dominance of hydrogen-producing bacteria in dark fermentation. This review demonstrates the potential of food waste and food processing waste for biohydrogen production and provides a brief overview of several physicochemical factors that affect biohydrogen production in dark fermentation. The economic viability of biohydrogen production from food waste is also discussed. Copyright © 2013 Elsevier Ltd. All rights reserved.

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)

Radioactive Waste.

Science.gov (United States)

Blaylock, B. G.

1978-01-01

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

An approach for sampling solid heterogeneous waste at the Hanford Site waste receiving and processing and solid waste projects

International Nuclear Information System (INIS)

Sexton, R.A.

1993-03-01

This paper addresses the problem of obtaining meaningful data from samples of solid heterogeneous waste while maintaining sample rates as low as practical. The Waste Receiving and Processing Facility, Module 1, at the Hanford Site in south-central Washington State will process mostly heterogeneous solid wastes. The presence of hazardous materials is documented for some packages and unknown for others. Waste characterization is needed to segregate the waste, meet waste acceptance and shipping requirements, and meet facility permitting requirements. Sampling and analysis are expensive, and no amount of sampling will produce absolute certainty of waste contents. A sampling strategy is proposed that provides acceptable confidence with achievable sampling rates

Solid waste study

International Nuclear Information System (INIS)

Ortiz, Paul G.

1995-01-01

The purpose of this document is to study the solid waste issues brought about by a Type C Investigation; ''Disposal of Inappropriate Material in the Los Alamos County Landfill'' (May 28, 1993). The study was completed in August 1995 by Coleman Research Corporation, under subcontract number 405810005-Y for Los Alamos National Laboratory (LANL). The study confirmed the issues identified in the Type C investigation, and also ascertained further issues or problems. During the course of this study two incidents involving hazardous waste resulted in the inappropriate disposal of the waste. An accidental spill, on June 8, 1995, at one of Laboratory buildings was not handled correctly, and ended up in the LAC Landfill. Hazardous waste was disposed of in a solid waste container and sent to the Los Alamos County Landfill. An attempt to locate the hazardous waste at the LAC Landfill was not successful. The second incident involving hazardous waste was discovered by the FSS-8, during a random dumpster surveillance. An interim dumpster program managed by FSS-8 discovered hazardous waste and copper chips in the solid waste, on August 9, 1995. The hazardous waste and copper chips would have been transported to the LAC Landfill if the audit team had not brought the problem to the awareness of the facility waste management personnel

SOLID WASTE STUDY

Energy Technology Data Exchange (ETDEWEB)

PAUL G. ORTIZ - COLEMAN RESEARCH CORP/COMPA INDUSTRIES

1995-08-01

The purpose of this document is to study the solid waste issues brought about by a Type C Investigation; ``Disposal of Inappropriate Material in the Los Alamos County Landfill'' (May 28, 1993). The study was completed in August 1995 by Coleman Research Corporation, under subcontract number 405810005-Y for Los Alamos National Laboratory (LANL). The study confirmed the issues identified in the Type C investigation, and also ascertained further issues or problems. During the course of this study two incidents involving hazardous waste resulted in the inappropriate disposal of the waste. An accidental spill, on June 8, 1995, at one of Laboratory buildings was not handled correctly, and ended up in the LAC Landfill. Hazardous waste was disposed of in a solid waste container and sent to the Los Alamos County Landfill. An attempt to locate the hazardous waste at the LAC Landfill was not successful. The second incident involving hazardous waste was discovered by the FSS-8, during a random dumpster surveillance. An interim dumpster program managed by FSS-8 discovered hazardous waste and copper chips in the solid waste, on August 9, 1995. The hazardous waste and copper chips would have been transported to the LAC Landfill if the audit team had not brought the problem to the awareness of the facility waste management personnel.

Understanding the role of waste prevention in local waste management: A literature review.

Science.gov (United States)

Zacho, Kristina O; Mosgaard, Mette A

2016-10-01

Local waste management has so far been characterised by end-of-pipe solutions, landfilling, incineration, and recycling. End-of-pipe solutions build on a different mind-set than life cycle-based approaches, and for this reason, local waste managers are reluctant to consider strategies for waste prevention. To accelerate the transition of waste and resource management towards a more integrated management, waste prevention needs to play a larger role in the local waste management. In this review article, we collect knowledge from the scientific community on waste prevention of relevance to local waste management. We analyse the trends in the waste prevention literature by organising the literature into four categories. The results indicate an increasing interest in waste prevention, but not much literature specifically concerns the integration of prevention into the local waste management. However, evidence from the literature can inform local waste management on the prevention potential; the environmental and social effects of prevention; how individuals in households can be motivated to reduce waste; and how the effects of prevention measures can be monitored. Nevertheless, knowledge is still lacking on local waste prevention, especially regarding the methods for monitoring and how local waste management systems can be designed to encourage waste reduction in the households. We end the article with recommendations for future research. The literature review can be useful for both practitioners in the waste sector and for academics seeking an overview of previous research on waste prevention. © The Author(s) 2016.

Hazardous Waste

Science.gov (United States)

... chemicals can still harm human health and the environment. When you throw these substances away, they become hazardous waste. Some hazardous wastes come from products in our homes. Our garbage can include such hazardous wastes as old batteries, bug spray cans and paint thinner. U.S. residents ...

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

International Nuclear Information System (INIS)

1990-11-01

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

Regional waste treatment with monolith disposal for low-level radioactive waste

International Nuclear Information System (INIS)

Forsberg, C.W.

1983-01-01

An alternative system is proposed for the disposal of low-level radioactive waste. This system, called REgional Treatment with MOnolith Disposal (RETMOD), is based on integrating three commercial technologies: automated package warehousing, whole-barrel rotary kiln incineration, and cement-based grouts for radioactive waste disposal. In the simplified flowsheet, all the sludges, liquids, resins, and combustible wastes are transported to regional facilities where they are incinerated. The ash is then mixed with special cement-based grouts, and the resulting mixture is poured into trenches to form large waste-cement monoliths. Wastes that do not require treatment, such as damaged and discarded equipment, are prepositioned in the trenches with the waste-cement mixture poured on top. The RETMOD system may provide higher safety margins by conversion of wastes into a solidified low-leach form, creation of low-surface area waste-cement monoliths, and centralization of waste processing into a few specialized facilities. Institutional problems would be simplified by placing total responsibility for safe disposal on the disposal site operator. Lower costs may be realized through reduced handling costs, the economics of scale, simplified operations, and less restrictive waste packaging requirements

Disposal of hazardous wastes

International Nuclear Information System (INIS)

Barnhart, B.J.

1978-01-01

The Fifth Life Sciences Symposium entitled Hazardous Solid Wastes and Their Disposal on October 12 through 14, 1977 was summarized. The topic was the passage of the National Resources Conservation and Recovery Act of 1976 will force some type of action on all hazardous solid wastes. Some major points covered were: the formulation of a definition of a hazardous solid waste, assessment of long-term risk, list of specific materials or general criteria to specify the wastes of concern, Bioethics, sources of hazardous waste, industrial and agricultural wastes, coal wastes, radioactive wastes, and disposal of wastes

Waste Analysis Plan for the Waste Receiving and Processing (WRAP) Facility

International Nuclear Information System (INIS)

TRINER, G.C.

1999-01-01

The purpose of this waste analysis plan (WAP) is to document the waste acceptance process, sampling methodologies, analytical techniques, and overall processes that are undertaken for dangerous, mixed, and radioactive waste accepted for confirmation, nondestructive examination (NDE) and nondestructive assay (NDA), repackaging, certification, and/or storage at the Waste Receiving and Processing Facility (WRAP). Mixed and/or radioactive waste is treated at WRAP. WRAP is located in the 200 West Area of the Hanford Facility, Richland, Washington. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

Waste retrieval plan for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1993-03-01

The US DOE has prepared this plan to meet the requirements of Public Law 102579, the Waste Isolation Pilot Plant (WIPP) LWA, The purpose. is to demonstrate readiness to retrieve from the WIPP underground transuranic radioactive waste that will be used for testing should retrieval be needed. The WIPP, a potential geologic repository for transuranic wastes generated in national-defense activities, has been constructed in southeastern New Mexico. Because the transuranic wastes will remain radioactive for a very long time, the WIPP must reasonably ensure safe performance over thousands of years. The DOE therefore decided to develop the facility in phases, to preclude premature decisions and to conduct the performance assessments needed to demonstrate long-term safety. Surface facilities for receiving waste have been built, and considerable underground excavation, 2150 feet below the surface, has been completed. The next step is a test phase, including underground experiments called ''bin tests'' and ''alcove test(s)'' with contact-handled transuranic waste. The objective of these waste tests is to collect relevant data about the gas-generation potential and volatile organic compound (VOC) source term of the waste for developing a basis for demonstrating long term safety by compliance with the applicable disposal regulations (40 CFR 191, 264 and 268). The test phase will end when a decision is made to begin disposal in the WIPP or to terminate the project if regulatory compliance cannot be determined and demonstrated. Authorization to receive transuranic waste at the WIPP for the test phase is given by the WIPP LWA provided certain requirements are met

Liquid Secondary Waste Grout Formulation and Waste Form Qualification

Energy Technology Data Exchange (ETDEWEB)

Um, Wooyong [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Williams, B. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Snyder, Michelle M. V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wang, Guohui [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2016-05-23

This report describes the results from liquid secondary waste (LSW) grout formulation and waste form qualification tests performed at Pacific Northwest National Laboratory (PNNL) for Washington River Protection Solutions (WRPS) to evaluate new formulations for preparing a grout waste form with high-sulfate secondary waste simulants and the release of key constituents from these grout monoliths. Specific objectives of the LSW grout formulation and waste form qualification tests described in this report focused on five activities: 1.preparing new formulations for the LSW grout waste form with high-sulfate LSW simulants and solid characterization of the cured LSW grout waste form; 2.conducting the U.S. Environmental Protection Agency (EPA) Method 1313 leach test (EPA 2012) on the grout prepared with the new formulations, which solidify sulfate-rich Hanford Tank Waste Treatment and Immobilization Plant (WTP) off-gas condensate secondary waste simulant, using deionized water (DIW); 3.conducting the EPA Method 1315 leach tests (EPA 2013) on the grout monoliths made with the new dry blend formulations and three LSW simulants (242-A evaporator condensate, Environmental Restoration Disposal Facility (ERDF) leachate, and WTP off-gas condensate) using two leachants, DIW and simulated Hanford Integrated Disposal Facility (IDF) Site vadose zone pore water (VZPW); 4.estimating the ⁹⁹Tc desorption K_d (distribution coefficient) values for ⁹⁹Tc transport in oxidizing conditions to support the IDF performance assessment (PA); 5.estimating the solubility of ⁹⁹Tc(IV)-bearing solid phases for ⁹⁹Tc transport in reducing conditions to support the IDF PA.

Low and intermediate level waste in SFR-1. Reference waste inventory

International Nuclear Information System (INIS)

Riggare, P.; Johansson, Claes

2001-06-01

The objective with this report is to describe all the waste and the waste package that is expected to be deposited in SFR-1 at the time of closure. This report is a part of the SAFE project (Safety Assessment of Final Repository for Radioactive Operational Waste), i.e. the renewed safety assessment of SFR-1. The accounted waste inventory has been used as input to the release calculation that has been performed in the SAFE project. The waste inventory is based on an estimated operational lifetime of the Swedish nuclear power plants of 40 years and that closure of the SFR repository will happen in 2030. In the report, data about geometries, weights, materials, chemicals and radionuclide are given. No chemo toxic material has been identified in the waste. The inventory is based on so called waste types and the waste types reference waste package. The reference waste package combined with a prognosis of the number of waste packages to the year 2030 gives the final waste inventory for SFR-1. All reference waste packages are thoroughly described in the appendices of this report. The reference waste packages are as far as possible based on actual experiences and measurements. The radionuclide inventory is also based on actual measurements. The inventory is based on measurements of 60 Co and 137 Cs in waste packages and on measurements 239 Pu and 240 Pu in reactor water. Other nuclides in the inventory are calculated with correlation factors. In the SAFE project's prerequisites it was said that one realistic and one conservative (pessimistic) inventory should be produced. The conservative one should then be used for the release calculations. In this report one realistic and one conservative radionuclide inventory is presented. The conservative one adds up to 10 16 Bq. Regarding materials there is only one inventory given since it is not certain what is a conservative assumption

Radioactive waste management

International Nuclear Information System (INIS)

Blomek, D.

1980-01-01

The prospects of nuclear power development in the USA up to 2000 and the problems of the fuel cycle high-level radioactive waste processing and storage are considered. The problems of liquid and solidified radioactive waste transportation and their disposal in salt deposits and other geologic formations are discussed. It is pointed out that the main part of the high-level radioactive wastes are produced at spent fuel reprocessing plants in the form of complex aqueous mixtures. These mixtures contain the decay products of about 35 isotopes which are the nuclear fuel fission products, about 18 actinides and their daughter products as well as corrosion products of fuel cans and structural materials and chemical reagents added in the process of fuel reprocessing. The high-level radioactive waste management includes the liquid waste cooling which is necessary for the short and middle living isotope decay, separation of some most dangerous components from the waste mixture, waste solidification, their storage and disposal. The conclusion is drawn that the seccessful solution of the high-level radioactive waste management problem will permit to solve the problem of the fuel cycle radioactive waste management as a whole. The salt deposits, shales and clays are the most suitable for radioactive waste disposal [ru

Updated Liquid Secondary Waste Grout Formulation and Preliminary Waste Form Qualification

Energy Technology Data Exchange (ETDEWEB)

Saslow, Sarah A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Um, Wooyong [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Russell, Renee L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wang, Guohui [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Asmussen, Robert M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sahajpal, Rahul [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2017-07-01

This report describes the results from liquid secondary waste grout (LSWG) formulation and cementitious waste form qualification tests performed by Pacific Northwest National Laboratory (PNNL) for Washington River Protection Solutions, LLC (WRPS). New formulations for preparing a cementitious waste form from a high-sulfate liquid secondary waste stream simulant, developed for Effluent Management Facility (EMF) process condensates merged with low activity waste (LAW) caustic scrubber, and the release of key constituents (e.g. ⁹⁹Tc and ¹²⁹I) from these monoliths were evaluated. This work supports a technology development program to address the technology needs for Hanford Site Effluent Treatment Facility (ETF) liquid secondary waste (LSW) solidification and supports future Direct Feed Low-Activity Waste (DFLAW) operations. High-priority activities included simulant development, LSWG formulation, and waste form qualification. The work contained within this report relates to waste form development and testing and does not directly support the 2017 integrated disposal facility (IDF) performance assessment (PA). However, this work contains valuable information for use in PA maintenance past FY17, and for future waste form development efforts. The provided data should be used by (i) cementitious waste form scientists to further understanding of cementitious dissolution behavior, (ii) IDF PA modelers who use quantified constituent leachability, effective diffusivity, and partitioning coefficients to advance PA modeling efforts, and (iii) the U.S. Department of Energy (DOE) contractors and decision makers as they assess the IDF PA program. The results obtained help fill existing data gaps, support final selection of a LSWG waste form, and improve the technical defensibility of long-term waste form performance estimates.

Low-level radioactive waste in the northeast: revised waste volume projections

International Nuclear Information System (INIS)

1984-06-01

The volume of low-level radioactive waste generated in the eleven Northeast states has undergone significant change since the inital 1982 analysis and projection. These revised projections incorporate improved data reporting and evidence of sharp declines in certain categories of waste. Volumes in the 1982-1983 period reflect waste shipped for disposal as reported by disposal site operators. Projected waste volumes represent waste intended for disposal. The recent dramatic changes in source reduction and waste management practices underscore the need for annual review of waste volume projections. The volume of waste shipped for off-site disposal has declined approximately 12% in two years, from an average 1,092,500 ft 3 annually in 1979 to 1981 to an average annual 956,500 ft 3 in 1982 to 1983; reactor waste disposal volumes declined by about 39,000 ft 3 or 7% during this period. Non-reactor waste volumes shipped for disposal declined by over 70,000 ft 3 or 15% during this period. The data suggest that generators increased their use of such management practices as source reduction, compaction, or, for carbon-14 and tritium, temporary storage followed by disposal as non-radioactive waste under the NRC de minimus standard effective March 1981. Using the Technical Subcommittee projection methodology, the volume of low-level waste produced annually in the eleven states, individually and collectively, is expected to increase through the year 2000, but at a significantly lower rate of increase than initially projected. By the year 2000, the Northeast is projected to generate 1,137,600 ft 3 of waste annually, an increase of about 20% over 1982 to 1983 average volume

Waste acceptance criteria for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1996-04-01

The Waste Isolation Pilot Plant (WIPP) Waste Acceptance Criteria (WAC), DOE/WIPP-069, was initially developed by a U.S. Department of Energy (DOE) Steering Committee to provide performance requirements to ensure public health and safety as well as the safe handling of transuranic (TRU) waste at the WIPP. This revision updates the criteria and requirements of previous revisions and deletes those which were applicable only to the test phase. The criteria and requirements in this document must be met by participating DOE TRU Waste Generator/Storage Sites (Sites) prior to shipping contact-handled (CH) and remote-handled (RH) TRU waste forms to the WIPP. The WIPP Project will comply with applicable federal and state regulations and requirements, including those in Titles 10, 40, and 49 of the Code of Federal Regulations (CFR). The WAC, DOE/WIPP-069, serves as the primary directive for assuring the safe handling, transportation, and disposal of TRU wastes in the WIPP and for the certification of these wastes. The WAC identifies strict requirements that must be met by participating Sites before these TRU wastes may be shipped for disposal in the WIPP facility. These criteria and requirements will be reviewed and revised as appropriate, based on new technical or regulatory requirements. The WAC is a controlled document. Revised/changed pages will be supplied to all holders of controlled copies

76 FR 4823 - Hazardous Waste Management System; Identifying and Listing Hazardous Waste Exclusion

Science.gov (United States)

2011-01-27

... Waste Management System; Identifying and Listing Hazardous Waste Exclusion AGENCY: Environmental... hazardous wastes. The Agency has decided to grant the petition based on an evaluation of waste-specific... excludes the petitioned waste from the requirements of hazardous waste regulations under the Resource...

Methods for maintaining a record of waste packages during waste processing and storage

International Nuclear Information System (INIS)

2005-01-01

During processing, radioactive waste is converted into waste packages, and then sent for storage and ultimately for disposal. A principal condition for acceptance of a waste package is its full compliance with waste acceptance criteria for disposal or storage. These criteria define the radiological, mechanical, physical, chemical and biological properties of radioactive waste that can, in principle, be changed during waste processing. To declare compliance of a waste package with waste acceptance criteria, a system for generating and maintaining records should be established to record and track all relevant information, from raw waste characteristics, through changes related to waste processing, to final checking and verification of waste package parameters. In parallel, records on processing technology and the operational parameters of technological facilities should adhere to established and approved quality assurance systems. A records system for waste management should be in place, defining the data to be collected and stored at each step of waste processing and using a reliable selection process carried over into the individual steps of the waste processing flow stream. The waste management records system must at the same time ensure selection and maintenance of all the main information, not only providing evidence of compliance of waste package parameters with waste acceptance criteria but also serving as an information source in the case of any future operations involving the stored or disposed waste. Records generated during waste processing are a constituent part of the more complex system of waste management record keeping, covering the entire life cycle of radioactive waste from generation to disposal and even the post-closure period of a disposal facility. The IAEA is systematically working on the preparation of a set of publications to assist its Member States in the development and implementation of such a system. This report covers all the principal

Determinants of consumer food waste behaviour: Two routes to food waste.

Science.gov (United States)

Stancu, Violeta; Haugaard, Pernille; Lähteenmäki, Liisa

2016-01-01

Approximately one quarter of the food supplied for human consumption is wasted across the food supply chain. In the high income countries, the food waste generated at the household level represents about half of the total food waste, making this level one of the biggest contributors to food waste. Yet, there is still little evidence regarding the determinants of consumers' food waste behaviour. The present study examines the effect of psycho-social factors, food-related routines, household perceived capabilities and socio-demographic characteristics on self-reported food waste. Survey data gathered among 1062 Danish respondents measured consumers' intentions not to waste food, planning, shopping and reuse of leftovers routines, perceived capability to deal with household food-related activities, injunctive and moral norms, attitudes towards food waste, and perceived behavioural control. Results show that perceived behavioural control and routines related to shopping and reuse of leftovers are the main drivers of food waste, while planning routines contribute indirectly. In turn, the routines are related to consumers' perceived capabilities to deal with household related activities. With regard to intentional processes, injunctive norms and attitudes towards food waste have an impact while moral norms and perceived behavioural control make no significant contribution. Implications of the study for initiatives aimed at changing consumers' food waste behaviour are discussed. Copyright © 2015 Elsevier Ltd. All rights reserved.

Potential for waste reduction

International Nuclear Information System (INIS)

Warren, J.L.

1990-01-01

The author focuses on wastes considered hazardous under the Resource Conservation and Recovery Act. This chapter discusses wastes that are of interest as well as the factors affecting the quantity of waste considered available for waste reduction. Estimates are provided of the quantities of wastes generated. Estimates of the potential for waste reduction are meaningful only to the extent that one can understand the amount of waste actually being generated. Estimates of waste reduction potential are summarized from a variety of government and nongovernment sources

Radioactive mixed waste disposal

International Nuclear Information System (INIS)

Jasen, W.G.; Erpenbeck, E.G.

1993-02-01

Various types of waste have been generated during the 50-year history of the Hanford Site. Regulatory changes in the last 20 years have provided the emphasis for better management of these wastes. Interpretations of the Atomic Energy Act of 1954 (AEA), the Resource Conservation and Recovery Act of 1976 (RCRA), and the Hazardous and Solid Waste Amendments (HSWA) have led to the definition of radioactive mixed wastes (RMW). The radioactive and hazardous properties of these wastes have resulted in the initiation of special projects for the management of these wastes. Other solid wastes at the Hanford Site include low-level wastes, transuranic (TRU), and nonradioactive hazardous wastes. This paper describes a system for the treatment, storage, and disposal (TSD) of solid radioactive waste

Secondary Waste Form Down-Selection Data Package—Fluidized Bed Steam Reforming Waste Form

Energy Technology Data Exchange (ETDEWEB)

Qafoku, Nikolla; Westsik, Joseph H.; Strachan, Denis M.; Valenta, Michelle M.; Pires, Richard P.

2011-09-12

The Hanford Site in southeast Washington State has 56 million gallons of radioactive and chemically hazardous wastes stored in 177 underground tanks (ORP 2010). The U.S. Department of Energy (DOE), Office of River Protection (ORP), through its contractors, is constructing the Hanford Tank Waste Treatment and Immobilization Plant (WTP) to convert the radioactive and hazardous wastes into stable glass waste forms for disposal. Within the WTP, the pretreatment facility will receive the retrieved waste from the tank farms and separate it into two treated process streams. These waste streams will be vitrified, and the resulting waste canisters will be sent to offsite (high-level waste [HLW]) and onsite (immobilized low-activity waste [ILAW]) repositories. As part of the pretreatment and ILAW processing, liquid secondary wastes will be generated that will be transferred to the Effluent Treatment Facility (ETF) on the Hanford Site for further treatment. These liquid secondary wastes will be converted to stable solid waste forms that will be disposed of in the Integrated Disposal Facility (IDF). To support the selection of a waste form for the liquid secondary wastes from WTP, Washington River Protection Solutions (WRPS) has initiated secondary waste form testing work at Pacific Northwest National Laboratory (PNNL). In anticipation of a down-selection process for a waste form for the Solidification Treatment Unit to be added to the ETF, PNNL is developing data packages to support that down-selection. The objective of the data packages is to identify, evaluate, and summarize the existing information on the four waste forms being considered for stabilizing and solidifying the liquid secondary wastes. At the Hanford Site, the FBSR process is being evaluated as a supplemental technology for treating and immobilizing Hanford LAW radioactive tank waste and for treating secondary wastes from the WTP pretreatment and LAW vitrification processes.

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.

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

Waste policies gone soft: An analysis of European and Swedish waste prevention plans.

Science.gov (United States)

Johansson, Nils; Corvellec, Hervé

2018-04-30

This paper presents an analysis of European and Swedish national and municipal waste prevention plans to determine their capability of preventing the generation of waste. An analysis of the stated objectives in these waste prevention plans and the measures they propose to realize them exposes six problematic features: (1) These plans ignore what drives waste generation, such as consumption, and (2) rely as much on conventional waste management goals as they do on goals with the aim of preventing the generation of waste at the source. The Swedish national and local plans (3) focus on small waste streams, such as food waste, rather than large ones, such as industrial and commercial waste. Suggested waste prevention measures at all levels are (4) soft rather than constraining, for example, these plans focus on information campaigns rather than taxes and bans, and (5) not clearly connected to incentives and consequences for the actors involved. The responsibility for waste prevention has been (6) entrusted to non-governmental actors in the market such as companies that are then free to define which proposals suit them best rather than their being guided by planners. For improved waste prevention regulation, two strategies are proposed. First, focus primarily not on household-related waste, but on consumption and production of products with high environmental impact and toxicity as waste. Second, remove waste prevention from the waste hierarchy to make clear that, by definition, waste prevention is not about the management of waste. Copyright © 2018 Elsevier Ltd. All rights reserved.

Conceptual designs for waste quality checking facilities for low level and intermediate level radioactive wastes and hazardous waste

International Nuclear Information System (INIS)

Driver, S.; Griffiths, M.; Leonard, C.D.; Smith, D.L.G.

1992-01-01

This report summarises work carried out on the design of facilities for the quality checking of Intermediate and Low Level Radioactive Waste and Hazardous Waste. The procedures used for the quality checking of these categories of waste are summarised. Three building options are considered: a separate LLW facility, a combined facility for LLW and HW and a Waste Quality Checking Facility for the three categories of waste. Budget Cost Estimates for the three facilities are given based on 1991 prices. (author)

Radioactive wastes. Management

International Nuclear Information System (INIS)

Guillaumont, R.

2001-01-01

Many documents (journal articles, book chapters, non-conventional documents..) deal with radioactive wastes but very often this topic is covered in a partial way and sometimes the data presented are contradictory. The aim of this article is to precise the definition of radioactive wastes and the proper terms to describe this topic. It describes the main guidelines of the management of radioactive wastes, in particular in France, and presents the problems raised by this activity: 1 - goal and stakes of the management; 2 - definition of a radioactive waste; 3 - radionuclides encountered; 4 - radio-toxicity and radiation risks; 5 - French actors of waste production and management; 6 - French classification and management principles; 7 - wastes origin and characteristics; 8 - status of radioactive wastes in France per categories; 9 - management practices; 10 - packages conditioning and fabrication; 11 - storage of wastes; 12 - the French law from December 30, 1991 and the opportunities of new ways of management; 13 - international situation. (J.S.)

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

International Nuclear Information System (INIS)

Christensen, B. D.

1999-01-01

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

Charging for waste motivates generators to optimize waste control at the source

International Nuclear Information System (INIS)

Berry, J.B.; Homan, F.J.

1988-01-01

The Department of Energy (DOE) has recognized the need for waste management that incorporates improved waste-handling techniques and more stringent regulatory requirements to prevent future liabilities such as Superfund sites. DOE-Oak Ridge Operations (DOE-ORO) has recognized that an effective waste management program focuses on control at the source and that the burden for responsible waste management can be placed on generators by charging for waste management costs. The principle of including the waste management costs in the total cost of the product, even when the product is research and development, is being implemented at Oak Ridge National Laboratory (ORNL). Charging waste management costs to generators creates an incentive to optimize processes so that less waste is produced, and it provides a basis for determining the cost effectiveness of capital improvements so that the mature phase of waste management can be attained. Improving waste management practices requires a long-range commitment and consistent administration. Making this commitment and providing adequate funding for proper waste disposal are most cost-effective measures than the alternative of paying for remedial actions after improper disposal. This paper summarizes a plan to charge waste generators, the administrative structure of the plan, a comparison between the rate structure and changes in waste disposal operations, and issues that have surfaced as the plan is implemented

40 CFR 148.10 - Waste specific prohibitions-solvent wastes.

Science.gov (United States)

2010-07-01

... injection unless the solvent waste is a solvent-water mixture or solvent-containing sludge containing less... 40 Protection of Environment 22 2010-07-01 2010-07-01 false Waste specific prohibitions-solvent wastes. 148.10 Section 148.10 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER...

Organizing waste reduction in the Dutch waste sector

International Nuclear Information System (INIS)

De Jong, P.T.

2000-01-01

Many organizations in the Netherlands are concerned with the collection, treatment and disposal of waste (either by tipping or incineration). They make up what is called the refuse market, and they all have their own business interests. What they have in common is that their internal objectives are not necessarily concerned with limiting the size or altering the composition of refuse streams. On the contrary, the organizations have an interest in the destination of waste streams. Besides the market-oriented organization, the waste sector also comprises various tiers of government, policy support groups and pressure and lobby organizations. All these organizations have their own different sets of interests. In other words, the refuse sector in the Netherlands is complex. The research project on 'Organizing Waste Reduction in the Dutch Waste Sector' focuses on the structure of the sector: the organizations, the relations between them, and organizational factors such as tariff systems, ownership relations and the market situation. An important question, which the research seeks to answer, is whether a modification in the structure of the sector can lead to the encouragement of reduction in the quantity of waste

Mixed waste management options

International Nuclear Information System (INIS)

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