The HAW project. Demonstrative disposal of high-level radioactive wastes in the Asse salt mine

International Nuclear Information System (INIS)

Rothfuchs, T.; Duijves, K.

1988-04-01

Since 1968 the GSF has been carrying out research and development programs for the final disposal of high-level radioactive waste (HAW) in salt formations. The heat producing waste has been simulated so far by means of electrical heaters and also cobalt-60-sources. In order to improve the final concept for HAW disposal in salt formations the complete technical system of an underground repository is to be tested in a one-to-one scale test facility. To satisfy the test objectives thirty high radioactive canisters containing the radionuclides Cs-137 and Sr-90 will be emplaced in six boreholes located in two test galleries at the 800 m-level in the Asse salt mine. The duration of testing will be approximately five years. For the handling of the radioactive canisters and their emplacement into the boreholes a system consisting of transportation casks, transportation vehicle, disposal machine, and borehole slider will be developed and tested. The actual scientific investigation program is based on the estimation and observation of the interaction between the radioactive canisters and the rock salt. This program includes measurement of thermally and radiolytically induced water and gas release from the rock salt and the radiolytical decomposition of salt minerals. Also the thermally induced stress and deformation fields in the surrounding rock mass will be investigated carefully. (orig./HP)

NDA generic research programme for higher activity waste management issues - 16390

International Nuclear Information System (INIS)

McKinney, James; Brownridge, Melanie

2009-01-01

NDA has a responsibility to ensure decommissioning activities are sufficiently technically underpinned and appropriate Research and Development (Rand D) is carried out. The NDA funds research and development (R and D) indirectly via the Site Licence Companies (SLCs) or directly. The main component of directly funded R and D is the NDA Direct Research Portfolio (DRP). The DRP is split into four framework areas: - University Interactions; - Waste Processing; - Material Characterisation; - Actinide and Strategic Nuclear Materials. These four framework areas were competed through an Official Journal of European Union (OJEU) process in 2008. Although all four areas involve waste management, Waste Processing and Material Characterisation specifically deal with Higher Activity Waste (HAW) waste management issues. The Waste Processing area was awarded to three groups: (i) National Nuclear Laboratory (NNL), (ii) Consortium led by Hyder Consulting Ltd, and (iii) Consortium led by UKAEA Ltd. The Material Characterisation area was awarded to three groups: (i) NNL, (ii) Serco, and (iii) Consortium led by UKAEA Ltd. The initial work in Waste Processing and Material Characterisation was centered on establishing a forward research programme to address the generic needs of the UK civil nuclear industry and the NDA strategic drivers for waste management and land quality. This has been achieved by the four main framework contractors from the Waste Processing and Materials Characterisation areas working together with the NDA to identify the key research themes and begin the development of the NDA's HAW Management Research Programme. The process also involves active engagement with both industry and regulators via the Nuclear Waste Research Forum (NWRF). The NDA's HAW Management Research Programme includes a number of themes: - Optimisation of Interim Store Operation and Design; - Alternative Waste Encapsulants; - Waste Package Integrity; - Alternative Waste treatment methods

FY-97 operations of the pilot-scale glass melter to vitrify simulated ICPP high activity sodium-bearing waste

International Nuclear Information System (INIS)

Musick, C.A.

1997-11-01

A 3.5 liter refractory-lined joule-heated glass melter was built to test the applicability of electric melting to vitrify simulated high activity waste (HAW). The HAW streams result from dissolution and separation of Idaho Chemical Processing Plant (ICPP) calcines and/or radioactive liquid waste. Pilot scale melter operations will establish selection criteria needed to evaluate the application of joule heating to immobilize ICPP high activity waste streams. The melter was fabricated with K-3 refractory walls and Inconel 690 electrodes. It is designed to be continuously operated at 1,150 C with a maximum glass output rate of 10 lbs/hr. The first set of tests were completed using surrogate HAW-sodium bearing waste (SBW). The melter operated for 57 hours and was shut down due to excessive melt temperatures resulting in low glass viscosity (< 30 Poise). Due to the high melt temperature and low viscosity the molten glass breached the melt chamber. The melter has been dismantled and examined to identify required process improvement areas and successes of the first melter run. The melter has been redesigned and is currently being fabricated for the second run, which is scheduled to begin in December 1997

The HAW-project: Demonstration facility for the disposal of high-level waste in salt

International Nuclear Information System (INIS)

Rothfuchs, T.; Duijves, K.A.

1990-04-01

The HAW-project plants the testwise emplacement of 30 vitrified highly radioactive canisters containing Cs-137 and Sr-90 at the 800 m level of the Asse salt mine for a testing period of approximately five years. The major objective of this project is the pilot testing and demonstration of safe methods for the final disposal of high-level radioactive waste (HAW) in geological salt formations. During the years 1985 to 1989 the underground test field was excavated, the measuring equipment installed, and two preceedings inactive electrical tests taken into operation. Furthermore, the components of a system for transportation and emplacement of highly radioactive canisters was fabricated, installed, and preliminarily tested. After some delays in the licensing procedure the emplacement of the 30 radioactive canisters is now envisaged for early 1991. For handling of the radioactive canisters and their emplacement into the boreholes a system consisting of a transport cask, a transport vehicle, a disposal machine, and of a borehole slider has been developed and will be tested. The actual scientific investigation programme is based on the estimation and observation of the interaction between the radioactive canisters and the rock salt. This programme includes measurement of thermally and radiolytically induced water and gas release from the rock salt and the radiolytical decomposition of salt minerals. Also the thermally induced stress and deformation fields in the surrounding rock mass will be investigated carefully. (orig./HP)

The effects of an instant haw beverage on lipid levels, antioxidant enzyme and immune function in hyperlipidemia patients.

Science.gov (United States)

Chen, Jidi; Xue, Bin; Li, Keji; Shi, Jingda; Krempin, D; Zhu, M; Garland, C

2002-05-01

To determine the effectiveness of an instant haw beverage in regulating lipid disturbance, enhancing antioxidant enzyme activity and immune function. Data was collected from 60 hyperlipidemic subjects. In this crossover design, each subject randomly received either the instant haw beverage (100 ml corresponding to 3 g of haw powder or 30 g of fresh haw fruit plus the carrier-guar gum plus some starch) or placebo (guar gum 1.5 g plus some starch as the carrier of the beverage) twice daily. Each supplementation lasted 31 days with a 28-day washout period between treatments. The instant haw beverage significantly reduced total serum cholesterol (9.6%), triglyceride (12.1%), LDLC (18%) while significantly increased SOD activities (7.5%). The placebo was shown to have positive results in some of the lipid profiles, though the effects of the instant haw beverage demonstrated greater significance. Serum triglyceride levels were significantly decreased and SOD activity significantly increased only as subjects were supplemented with the instant haw beverage while no significant changes were seen with placebo. Supplementation with the instant haw beverage positively affects blood lipid profile, antioxidant status and immune function in individuals with hyperlipidemia.

Environmental Assessment for the Independent Waste Handling Facility, 211-F at the Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-08-01

Currently, liquid Low Activity Waste (LAW) and liquid High Activity Waste (HAW) are generated from various process operational facilities/processes throughout the Savannah River Site (SRS) as depicted on Figure 2-1. Prior to storage in the F-Area tank farm, these wastes are neutralized and concentrated to minimize their volume. The Waste Handling Facility (211-3F) at Building 211-F Complex (see Figure 2-2) is the only existing facility onsite equipped to receive acidic HAW for neutralization and volume reduction processing. Currently, Building 221-F Canyon (see Figure 2-2) houses the neutralization and evaporation facilities for HAW volume reduction and provides support services such as electric power and plant, process, and instrument air, waste transfer capabilities, etc., for 21 1-F operations. The future plan is to deactivate the 221-F building. DOE`s purpose is to be able to process the LAW/HAW that will continue to be generated on site. DOE needs to establish an alternative liquid waste receipt and treatment capability to support site facilities with a continuing mission. The desire is for Building 211-F to provide the receipt and neutralization functions for LAW and HAW independent of 221-F Canyon. The neutralization capability is required to be part of the Nuclear Materials Stabilization Programs (NMSP) facilities since the liquid waste generated by the various site facilities is acidic. Tn order for Waste Management to receive the waste streams, the solutions must be neutralized to meet Waste Management`s acceptance criteria. The Waste Management system is caustic in nature to prevent corrosion and the subsequent potential failure of tanks and associated piping and hardware.

Preparation and characterization of an improved borosilicate glass matrix for the incorporation of high level radioactive waste (HAW). Pt. 1

International Nuclear Information System (INIS)

Guber, W.; Hussain, M.; Kahl, L.; Ondracek, G.; Saidl, J.; Dippel, T.

1979-08-01

On the basis of laboratory and technical experience with the preparation and the characterization of borosilicate glasses as solidification matrix for high level radioactive waste solution (HAW), a borosilicate glass composition with optimum properties has been developed. Keeping in view the technical and final storage requirements, a number of glass compositions with varying proportions of influential components as Al, Mg, Na were prepared and thoroughly investigated for certain parameters as specific gravity, thermal conductivity, impact resistance, thermal expansion, viscosity, characteristic temperature points, specific heat, evaporation losses from the melt, electrical conductivity, leach resistance, tendency toward recrystallization and second phase formation. All the compositions (some with different amounts of Gd 2 O 3 , an expected neutron poision) contained 15 wt. % simulated HAW oxides. Samples for investigation were fabricated very close to the actual process conditions of vitrification. Two glass products GP12 and GP26 (3.7% Gd 2 O 3 ) have been selected out of 25 glasses as the optimised products for further thorough investigations. Leach resistance, viscosity at 1420 K, tendency towards recrystallization and second phase formation were the most important deciding factors. (orig.) [de

Experiments in the HAW project. Data report. ECN contribution July-December 1993

Energy Technology Data Exchange (ETDEWEB)

Vonka, V.; Middleton, D.W.; Ruiter, A. de

1994-09-01

Data are presented from the High Active Waste (HAW) experiment, a large-scale, in situ test being performed underground at the Asse salt mine in Remlingen, FRG. These data include selected field information, the test configuration, instrumentation activities and comprehensive results from a large number of gauges. The results are measured data obtained from gap meters, thermocouples, linear displacement transducers, voltage and electric current meters and pressure gauges. Data certification practices have been described together with the quality assurance of the data reduction and of the data base management system. The experiment began on November 8, 1988 and will continue for five years. Data in this report cover the ECN contribution in the period from July 1st, 1993 to December 31th, 1993. (orig.).

Experiments in the HAW project. Data report. ECN contribution January - June 1993

Energy Technology Data Exchange (ETDEWEB)

Vonka, V.; Middleton, D.W.; Ruiter, A. de

1994-09-01

Data are presented from the High Active Waste (HAW) experiment, a large-scale, in situ test being performed underground at the Asse salt mine in Remlingen, FRG. These data include selected field information, the test configuration, instrumentation activities and comprehensive results from a large number of gauges. The results are measured data obtained from gap meters, thermocouples, linear displacement transducers, voltage and electric current meters and pressure gauges. Data certification practices have been described together with the quality assurance of the data reduction and of the data base management system. The experiment began on November 8, 1988 and will continue for five years. Data in this report cover the ECN contribution in the period from January 1st, 1993 to June 30th, 1993. (orig.).

Experiments in the HAW project. Data report. ECN contribution July-December 1993

International Nuclear Information System (INIS)

Vonka, V.; Middleton, D.W.; Ruiter, A. de.

1994-09-01

Data are presented from the High Active Waste (HAW) experiment, a large-scale, in situ test being performed underground at the Asse salt mine in Remlingen, FRG. These data include selected field information, the test configuration, instrumentation activities and comprehensive results from a large number of gauges. The results are measured data obtained from gap meters, thermocouples, linear displacement transducers, voltage and electric current meters and pressure gauges. Data certification practices have been described together with the quality assurance of the data reduction and of the data base management system. The experiment began on November 8, 1988 and will continue for five years. Data in this report cover the ECN contribution in the period from July 1st, 1993 to December 31th, 1993. (orig.)

Experiments in the HAW project. Data report. ECN contribution January - June 1993

International Nuclear Information System (INIS)

Vonka, V.; Middleton, D.W.; Ruiter, A. de.

1994-09-01

Data are presented from the High Active Waste (HAW) experiment, a large-scale, in situ test being performed underground at the Asse salt mine in Remlingen, FRG. These data include selected field information, the test configuration, instrumentation activities and comprehensive results from a large number of gauges. The results are measured data obtained from gap meters, thermocouples, linear displacement transducers, voltage and electric current meters and pressure gauges. Data certification practices have been described together with the quality assurance of the data reduction and of the data base management system. The experiment began on November 8, 1988 and will continue for five years. Data in this report cover the ECN contribution in the period from January 1st, 1993 to June 30th, 1993. (orig.)

A nuclear waste deposit in space - the ultimate solution for low-cost and safe disposal

International Nuclear Information System (INIS)

Ruppe, H.O.; Hayn, D.; Braitinger, M.; Schmucker, R.H.

1980-01-01

The disposal of nuclear high-active waste (HAW) is representative for the problem of burdening the environment with highly active or toxic waste products at present and in the future. Safe disposal methods on Earth are technically very difficult to achieve and the costs of establishment and maintenance of such plants are extremely high. Furthermore the emotionally based rejection by a wide sector of the population gives sufficient reason to look for new solutions. Here, space technology can offer a real alternative - a waste deposit in space. With the Space Transportation System, which shall soon be operative, and the resulting high flight frequencies it will be possible to transport all future HAW into space at economical casts. (orig.) [de

Haw River PFCs Data Set

Data.gov (United States)

U.S. Environmental Protection Agency — PFAS concentrations in river and drinking water in and around the Haw River in North Carolina. This dataset is associated with the following publication: Sun, M., E....

Phenolic content and antioxidant activity of Pereskia grandifolia Haw. (Cactaceae) extracts

Science.gov (United States)

Sim, K. S.; Nurestri, A. M. Sri; Norhanom, A. W.

2010-01-01

The leaves of Pereskia grandifolia Haw. (Cactaceae), commonly known as “Jarum Tujuh Bilah” in Malaysia, have been traditionally used as natural remedy in folk medicine by the locals. In the present study, the antioxidant potential of P. grandifolia crude methanol and its fractionated extracts (hexane, ethyl acetate and water) have been investigated, employing three different established testing systems, such as scavenging activity on 1,1-diphenyl-2-picrylhydrazyl (DPPH) radicals, reducing power assay and β-carotene method. The total phenolic content of the P. grandifolia extracts was also assessed by the Folin-Ciocalteau’s method. The ethyl acetate extract showed significantly the highest total phenolic content, DPPH scavenging ability and antioxidant activity in β-carotene bleaching assay while the hexane extract possessed significantly strongest reducing power. The data obtained in these testing systems clearly establish the antioxidant potency of P. grandifolia. As such, this is the first report on the antioxidant activities of P. grandifolia. PMID:20931088

Manipulation technology optimization for the interim storage of HAW transport and storage containers; Optimierung der Handhabungstechnik zur Zwischenlagerung von HAW-Transport- und Lagerbehaeltern

Energy Technology Data Exchange (ETDEWEB)

Emmrich, Uwe; Krueger, Michael; Schulze, Hartmut [GNS Gesellschaft fuer Nuklear-Service mbH, Essen (Germany)

2011-07-01

The handling of high-level radioactive waste transport and storage containers from reprocessing plants is determined by the cask configuration and the radiation protection measures with respect to the safe enclosure of the radioactive inventory and shielding of gamma and neutron radiation. The new of CASTOR {sup registered} HAW28M was designed for higher radioactive inventories, the heat generation is has rarely been changed with respect to the former design. The essential structural modifications are shock absorbers that have to be demounted before storage in the interim storage facility Gorleben. Due to public acceptance forcings the ALARA principle is not the only basis for manipulation technology optimizations, the minimization of dose rate for the operational personnel is of increasing importance. The authors describe the optimizations and the resulting dose reductions.

The HAW Project. Test disposal of highly radioactive radiation sources in the Asse salt mine

International Nuclear Information System (INIS)

Rothfuchs, T.; Mueller-Lyda, I.; Raynal, M.; Major, J.C.

1993-01-01

In order to prove the safe disposal of high-level radioactive waste (HAW) in salt a five years test disposal of thirty highly radioactive canisters is planned in the Asse salt mine in the Federal Republic of Germany. The thirty canisters containing the radionuclides Caesium 137 and Strontium 90 in quantities sufficient to cover the bandwith of heat generation and gamma radiation of real HAW will be emplaced in six boreholes located in two galleries at the 800-m-level. Two electrical heater tests were already started in November 1988 and are continuously surveyed in respect of the thermomechanical and geochemical response of the rock mass. Also the handling system necessary for the emplacement of the radioactive canisters was developed and successfully tested. A laboratory investigation programme on radiation effects in salt is being performed in advance to the radioactive canister emplacement. This programme includes the investigation of thermally and radiolytically induced water and gas release from the rock salt and the radiolytical decomposition of salt minerals. For gamma dose and dose rate measurements in the test field measuring systems consisting of ionization chambers as well as solid state dosemeters were developed and tested. 70 refs

27 CFR 9.214 - Haw River Valley.

Science.gov (United States)

2010-04-01

... significance. (b) Approved maps. The two United States Geological Survey 1:100,000-scale metric topographic...) Greensboro, North Carolina, 1984; and (2) Chapel Hill, North Carolina, 1984. (c) Boundary. The Haw River... line southeast 2 miles to the intersection of North Carolina State Highway 49 and an unnamed, light...

Actual Situation and Further Development of Interim Storage of Spent Nuclear Fuel (SNF) and Highly Active Waste (HAW) from the View of the Competent Authority in the Field of section 6

International Nuclear Information System (INIS)

Gastl, Christoph; Drobniewski, Christian

2014-01-01

According to the German atomic law the storage of nuclear material has to be licensed following section 6 by the competent authority in this field, which is the Federal Office for Radiation Protection. Interim storage in its actual form started in 2002 in the interim storage facility next to the NPP Lingen. Since this time each NPP erected its own storage facilities and three central storage facilities have been built. The spent nuclear fuel (SNF) and the vitrified high level waste (HAW) will be stored there until final disposal. The time span from now on to the point of opening of a final disposal facility shall be presented from a regulators point of view, divided into different phase which could spread from years to decades. Special attention shall be drawn on the different aspects influencing the licensing process and its duration at the moment and in future including the capabilities of the competent authority. (authors)

Experiments in the HAW project

International Nuclear Information System (INIS)

Vonka, V.; Middleton, D.W.; Ruiter, A. de.

1993-12-01

This data report is the eighth of a series intended to document the data obtained from the HAW in situ experiment (at Asse) and to make these data available to potential users. During this experiment a considerable number of thermocouples was damaged so that their signals are lost. In some cases it resulted in plots with no signal but empty frames. In the previous report we tried to change our procedure and remove these frames from the report. This action was not completely successful because, as it turned out, also some of the not empty plots were removed wrongly as well. (orig.)

Technical Status Report: Preliminary Glass Formulation Report for INEEL HAW

International Nuclear Information System (INIS)

Peeler, D.; Reamer, I.; Vienna, J.; Crum, J.A.

1998-03-01

This study was performed by a team comprising experts in glass chemistry, glass technology, and statistics at both SRTC and PNNL. This joint effort combined the strengths of each discipline and site to quickly develop a glass formulation for specific INEEL HAW

Monitoring and inspection techniques for long term storage of higher activity waste packages

International Nuclear Information System (INIS)

Bolton, Gary

2013-01-01

In 2009, following recent changes in United Kingdom (UK) Government Policy, the Nuclear Decommissioning Authority (NDA) identified a knowledge gap in the area of long term interim storage of waste packages. A cross-industry Integrated Project Team (IPT) for Interim Storage was created with responsibility for delivering Industry Guidance on the storage of packaged Higher Activity Waste (HAW) for the current UK civil decommissioning and clean-up programmes. This included a remit to direct research and development projects via the NDA's Direct Research Portfolio (DRP) to fill the knowledge gap. The IPT for Interim Storage published Industry Guidance in 2012 which established a method to define generic package performance criteria and made recommendations on monitoring and inspection. The package performance method consists of the following steps; identification of the package safety function, identification of evolutionary processes that may affect safety function performance, determination of measurable indicators of these evolutionary processes and calibration of the indicators into package performance zones. This article provides an overview of three projects funded by the NDA's DRP that the UK National Nuclear Laboratory (NNL) have completed to address monitoring and inspection needs of waste packages in interim storage. (orig.)

Spanish participation in the Haw Project: Laboratory investigations on Gamma irradiation effects in rock salt

International Nuclear Information System (INIS)

Cuevas, C. de las; Miralles, L.; Teixidor, P.; Garcia Veigas, J.; Dies, X.; Ortega, X.; Pueyo, J.J.

1993-01-01

In order to prove the safe disposal of high-level radioactive waste (HAW) in salt rock, a five years test disposal of thirty highly radioactive radiation sources is planned in the Asse salt mine, in the Federal Republic of Germany. The thirty radiation sources consist of steel canisters containing the vitrified radionuclides Caesium 137 and Strontium 90 in quantities sufficient to cover the bandwidth of heat generation and gamma radiation of real HAW. The radiation sources will be emplaced in six boreholes located in two galleries at the 800 m level. Two electrical heater tests were already started in November 1988 and are continuosly surveyed in respect of the rock mass. Also the handling system necessary for the emplacement of the radioactive canisters was developed and succesfully tested. A laboratory investigation programme on radiation effects in salt is being performed in advance to the radioactive canister emplacement. This programme includes the investigation of thermally and radiolytically induced water and gas release from the rock salt and the radiolytical decomposition of salt minerals. Part of this programme has been carried out since 1988 at the University of Barcelona, basically what refers to colloidal sodium determinations by light absorption measurements and microstructural studies on irradiated salt samples. For gamma dose and dose rate measurements in the test field, measuring systems consisting of ionisation chambers as well as solid state dosemeters were developed and tested. Thermomechanical computer code validation is performed by calculational predictions and parallel investigation of the stress and displacement fields in the underground test field

Response of Opuntia stricta Haw micropropagated plants in acclimatization and field

Directory of Open Access Journals (Sweden)

Marina Medeiros de Araújo Silva

2017-07-01

Full Text Available Forage palm (Opuntia stricta Haw. is a great important crop for the semi-arid region of Brasil. It has been propagated through in vitro culture, by areole activation. This work aimed to determine the response of Opuntia stricta Haw. variety ‘Oreja de Elefante Mexicana’ micropropagated plants during its acclimatization and field planting. Plants were acclimatized in tubes and plastic bags with a mixture of soil and manure, and it were kept in greenhouse for 130 days. Later, the plants kept in tubes were divided into nine treatments, according to their size (between 6 to 14 cm, and transfer to the field. The use of tubes provided a higher survival, height, fresh and dry mass of the cladodes. There was no significant differences between the recipients used for root development. At the end of acclimatization it was observed that plants did not have a uniform development, presenting size variation. After the first 15 days in the field, the majority of the plants with primary shoots were larger than 10 cm. At 60 days the survival was 100%, and all plants presented shoots, even the smallest. However, is recommended that plants larger than 10 cm will be used, due to the better establishment to field conditions. The results demonstrate the feasibility in the use of micropropagated plants for the establishment of forage palm fields. Keywords: cladodes, forage palm, in vitro culture, semi-arid region

Testing and evaluation of the properties of various potential materials for immobilizing high activity waste

International Nuclear Information System (INIS)

Malow, G.; Beran, V.; Lutze, W.

1980-01-01

Second joint annual report of the work performed on the testing and evaluation of materials for immobilizing high activity waste under Community contracts. At Marcoule, active block samples containing HAW from the Marcoule reprocessing plant were cast to the specification of five of the six original reference samples and leach tested at ambient temperature. Phosphate glass -bead samples produced by the Gelsenberg/DWK PAMELA process- were included in the test programme at HMI-Berlin and UKAEA Harwell. Leaching tests of inactive samples with leachants of various pH-values, with ionized water and with natural water compositions representative of certain repository conditions (salt, clay and granite) were added to the Harwell programme. The studies of radiation and thermal effects and the investigation of devitrification phenomena, started in 1977, continued, as samples reached annealing times of 2400 h and doses 4 x 10 17 dpg. The results achieved have so far confirmed most of the favourable preliminary assessments of glass based solidification products. At this stage the programme aims primarily at the understanding of physical and chemical phenomena rather that at verification under realistic waste storage and disposal conditions

The HAW project. Test storage of high-level radiation sources in the Asse salt mine. Documentation and assessment of the storage system

International Nuclear Information System (INIS)

Mueller, K.; Rothfuchs, T.

1994-01-01

The HAW project aimed primarily at studying the interaction between high-level radioactive waste moulds and rock salt as the respository medium. Another priority was the prototype development and testing of a technical system for the emplacement of high-level radioactive moulds in deep storage boreholes. To simulate real high-level radioactive wastes, special high-level radiation sources (Cs-137, Sr-90) were produced in the United States of America under a German-American cooperation contract, for carrying out the tests at the Asse salt mine. The components of the storage system are described, their position and task within the entire handling procedure explained. Questions of radiation protection and accident protection, of functioning and operating reliability, of quality assurance and examination of documents, materials, of manufacture and functioning, and of documentation are dealt with in detail. With a view to the planning of storage techniques for a mine respository, the experience of development and operation is recorded, and recommendation of further developments are given. Problems which arose during work on the HAW project were partly due to test-specific reasons and will not or not in this form occur in a mine respository. It was planned to start the test emplacement in 1987, and it could have been executed in 1993 after appropriate preparation and approval of the storage system by the mining authority and the Hanover TUEV in 1991. In December 1992, however, the Federal Government decided to give up to the project due to the uncertain licensing situation, and to immediately stop all preparatory work. (orig./HP) [de

Caracterización morfoanatómica comparativa entre Aloe vera (L. Burm. F., Aloe arborescens Mill., Aloe saponaria Haw. y Aloe ciliaris Haw. (Aloeaceae

Directory of Open Access Journals (Sweden)

Stella Maris Carpano

Full Text Available Aloe vera (L. Burm. F. (= Aloe barbadensis Miller conhecida como "a planta da imortalidade" no antigo Egito é utilizada em fitoterapia como humectante, antibacteriana, antifúngica, antiviral e antioxidante. Com a finalidade de contribuir para identificação da droga vegetal, foram realizados estudos morfoanatômicos da folha. A utilização de plantas com características terapêuticas reconhecidas determina que, por analogia, popularmente sejam utilizadas com a mesma finalidade outras espécies do mesmo gênero. Isto é o que ocorre com três espécies de Aloe spp., que se cultivam ou crescem acidentalmente na Argentina: A. arborescens Mill., A. saponaria Haw. e A. ciliaris Haw. (Aloaceae. Estabeleceram-se os caracteres morfoanatômicos de diagnóstico por microscopia óptica e microscopia eletrônica de varredura (apresentam-se desenhos e fotomicrografias dos mesmos. Obtiveram-se valores numéricos dos elementos histológicos de diagnóstico: magnitudes lineares e proporcionais. Realizaram-se reações histoquímicas de identificação dos princípios ativos para sua localização "in situ".

Off-Gas Analysis During the Vitrification of Hanford Radioactive Waste Samples

International Nuclear Information System (INIS)

Ha, B.C.; Ferrara, D.M.; Crawford, C.L.; Choi, A.S.; Bibler, N.E.

1998-01-01

This paper describes the off-gas analysis of samples collected during the radioactive vitrification experiments. Production and characterization of the Hanford waste-containing LAW and HAW glasses are presented in related reports from this conference

Petrogenesis and geochemical characterisation of ultramafic cumulate rocks from Hawes Head, Fiordland, New Zealand

International Nuclear Information System (INIS)

Daczko, N.R.; Emami, S.; Allibone, A.H.; Turnbull, I.M.

2012-01-01

Early Cretaceous parts of the western Median Batholith (Western Fiordland Orthogneiss) represent the exposed root of a magmatic arc of dioritic to monzodioritic composition (SiO 2 = 51-55 wt%; Na 2 O/K 2 O = 3.7-8.8 in this study). We characterise for the first time the field relationships, petrography, mineralogy and geochemistry of ultramafic and mafic cumulates at Hawes Head, the largest exposure of ultramafic rocks in western Fiordland. We distinguish three related rock types at Hawes Head: hornblende peridotite (MgO = 21-35 wt%); hornblendite (MgO = 15-16 wt%); and pyroxenite (MgO = 21 wt%). Petrogenetic relationships between the ultramafic rocks and the surrounding Misty Pluton of the Western Fiordland Orthogneiss are demonstrated by: (i) mutually cross-cutting relationships; (ii) similar mafic phases (e.g. pyroxene and amphibole) with elevated Mg-numbers (e.g. olivine Mg/(Mg+Fe) = 0.77-0.82); (iii) fractionation trends in mineral geochemistry; and (iv) shared depleted heavy rare earth element patterns. In addition, the application of solid/liquid partition coefficients indicates that olivine in the ultramafic rocks at Hawes Head crystallised from a magma with Mg/(Mg+Fe) = 0.54-0.57. The olivine grains therefore represent a plausible early crystallising phase of the adjacent Western Fiordland Orthogneiss (Mg/(Mg+Fe) = 0.51-0.55). (author). 42 refs., 5 figs., 1 tab.

The long path to a disposal for high radioactive waste. Pt. 3. A new approach for a better understanding of processes and the system in a whole; Auf dem langen Weg zu einem Endlager fuer hochradioaktive, Waerme entwickelnde Abfaelle. T. 3. Ein neuer konzeptionell-konfigurativer Ansatz und ein neues Simulationswerkzeug zur Erarbeitung eines verbesserten Prozess- und Systemverstaendnisses fuer HAW-Entsorgungsanlagen - ohne und mit direktem laengerfristigem Monitoring

Energy Technology Data Exchange (ETDEWEB)

Lux, Karl-Heinz; Wolters, Ralf; Zhao, Juan [Technische Univ. Clausthal, Clausthal-Zellerfeld (Germany). Inst. fuer Aufbereitung, Deponiertechnik und Geomechanik

2017-05-15

A new conceptual@configurative approach and a new simulation tool for the development of an improved process and system understanding for HAW disposal systems - without and with direct long-term monitoring are presented and discussed. With regard to the final repository development, a retrieveability of the heat-generating high-radio-active waste during the storage phase and a general recoverability during the first 500 years after closure of the repository in the post-closure phase are required. Both for the monitoring of the repository during the storage phase as well as thereafter, a direct monitoring of the storage horizon could be implemented as an alternative to an indirect monitoring.

HAW simulation experiments with cobalt-60 radiation sources in the Asse salt mine

International Nuclear Information System (INIS)

Rothfuchs, T.; Wieczorek, K.; Feddersen, H.K.

1986-01-01

The report describes the experimental work and the measured data of the joint German-American project for the HAW simulation experiment with cobalt-60 radiation sources in the Asse salt mine, covering the period up to the end of the third quarter 1986. The experiment is intended to yield information on the synergistic effects of heat and ionizing radiation on the salt rock under representative waste repository conditions. The investigations aim at the migration, release, and radiolytic decomposition of the water and gas components in the rock salt, and at the thermally induced strain and deformation processes. In addition, corrosion tests are planned to be made on various container test materials, and analyses of salt rock core samples for assessing the effect of heat and radiation on the rock. The report in hand presents all data obtained during the experiment. The results of the subsequent evaluation and verification studies will be presented in another report, the programme being given in an annex to the report in hand. (orig./RB) [de

The long path to a disposal for high radioactive waste. Pt. 2. A new approach for a better understanding of processes and the system in a whole; Auf dem langen Weg zu einem Endlager fuer hoch radioaktive Waerme entwickelnde Weg Abfaelle. T. 2. Ein neuer konzeptionell-konfigurativer Ansatz und ein neues Simulationswerkzeug zur Erarbeitung eines verbesserten Prozess- und Systemverstaendnisses fuer HAW-Entsorgungsanlagen - ohne und mit direktem laengerfristigem Monitoring

Energy Technology Data Exchange (ETDEWEB)

Lux, Karl-Heinz; Wolters, Ralf; Zhao, Juan [Technische Univ. Clausthal, Clausthal-Zellerfeld (Germany). Inst. fuer Aufbereitung, Deponietechnik und Geomechanik

2017-04-15

A new conceptual-configurative approach and a new simulation tool for the development of an improved process and system understanding for HAW disposal systems - without and with direct long term monitoring are presented and discussed. With regard to the final repository development, a retrieveability of the heat generating high radio active waste during the storage phase and a general recoverability during the first 500 years after closure of the repository in the post closure phase are required. Both for the monitoring of the repository during the storage phase as well as thereafter, a direct monitoring of the storage horizon could be implemented as an alternative to an indirect monitoring.

Irradiation effects on the rock-salt HAW-Asse Project

International Nuclear Information System (INIS)

Palut, J.M.

1991-01-01

Since 1988 ANDRA is involved in the HAW project, a test disposal of high level radioactive canisters in a salt dome, at Asse in FRG. ANDRA is responsible of in situ measurements, laboratory analyses and predictive calculations. Thus are delayed in situ dose measurements. Two methods have been developed, one is based on thermoluminescent dosemeters and measure an integrated dose, the other uses ionization chambers and gives a dose rate. Specific equipments had to be developed: manufacturing and testing. Geomechanics is also concerned by in situ measurement, especially rocksalt deformation, induced by the heat production of the canisters. Three groups of tiltmeters have been installed, providing informations on both natural creeping of rocksalt and effect of electrical heating in two boreholes. Laboratory studies consist in analyzing gases released by Asse salt samples irradiated under various conditions. Most of the 150 sample irradiations are completed. The last topic to the project intends to predict gamma ray flux and spectrum in the HAW test field using computer models. The work carried out and discussed includes digitalization of test data (sources, borehole lining, rocksalt), Bremsstrahlung sensitivity analysis, and calculation of both energy deposited and dose rate around the sources. This calculation was performed for 50 points, requiring 400 runs of Mercure-5 models. Interpolation functions are also provided in order to give values between these 50 points. The next step aim to determine gamma spectrum in salt and also energy deposited at various locations in the dummy canister where samples are intended to be emplaced. TRIPOLI-2 Model will be used for these purposes [fr

Pilot tests on radioactive waste disposal in underground facilities

International Nuclear Information System (INIS)

Haijtink, B.

1992-01-01

The report describes the pilot test carried out in the underground facilities in the Asse salt mine (Germany) and in the Boom clay beneath the nuclear site at Mol (Belgium). These tests include test disposal of simulated vitrified high-level waste (HAW project) and of intermediate level waste and spent HTR fuel elements in the Asse salt mine, as well as an active handling experiment with neutron sources, this last test with a view to direct disposal of spent fuel. Moreover, an in situ test on the performance of a long-term sealing system for galleries in rock salt is described. Regarding the tests in the Boom clay, a combined heating and radiation test, geomechanical and thermo-hydro mechanical tests are dealt with. Moreover, the design of a demonstration test for disposal of high-level waste in clay is presented. Finally the situation concerning site selection and characterization in France and the United Kingdom are described

The Haw in-situ test at Asse - its conception and goals

International Nuclear Information System (INIS)

Gies, H.; Hinsch, H.; Monig, J.

1989-01-01

The HAW-disposal test is a demonstration and a R and D test utilizing nearly full-size waste canisters with vitrified Cs-137 and Sr-90 as heat and radiation sources in a repository-like setting. It is, however, not intended as an in-situ experiment for testing the glass product of the vitrified waste. The entire test field comprises two separate rooms, A and B, each having four boreholes. The maximum salt temperatures are planned to be 250 0 C (electric heating) and 250/200/200 0 C (γ radiative heating), with essentially the same maximum dose rates for two pairs of boreholes (∼5·10 5 rad/h). The loaded test canisters are now available and do not completely meet the intended specification. Heat loadings as well as dose rates are, for several reasons, lower than planned by about 30%. The designs of the emplacement boreholes in each of the two test rooms are basically the same. For retrievability reasons, all boreholes will have a liner. The only significant difference will be, that the room A-boreholes will have a backfilling of inert alumina pebbles between liner and the salt, whereas these in room B will have a free annulus that allows the salt to converge freely onto the liner surfaces, thus simulating the salt converging onto canisters in an actual repository. Gas sampling from the boreholes will mainly be done in the annular regions. A special dosimetry program, as well as an extensive radiolytic effects program, both in situ and laboratory, are under preparation. A special radiation effects study will be performed with Dummy canisters located at the top of the canister stacks. The entire test is a joint European project with the financial contribution of the CEC and the close cooperation with ECN, ANDRA and ENRESA

Investigations concerning the source term for the emission of fission products and transuranic elements from the highly radioactive waste in the temperature region between 200 and 11000C

International Nuclear Information System (INIS)

Baumgartner, F.; Krebs, K.; Merte, B.

1984-04-01

Starting point of these investigations was the research report 290 of the former Institute for Reactor Safety, Cologne. The largely incorrect assumptions made in the chemical statement led to high radioactive doses not only for the closer, but also for the further surroundings of a reprocessing plant in case that the cooling system of the fuel element storage or the storage tank for the highly radioactive waste (HAW) should become inoperative for an extended period of time. However, as a result of this temperature region which we used in our experiments, the investigations concerning the source term of the HAW between 1100 and 1200 0 C became interesting again, because a glass melt of about 1100 0 C is used during the PAMELA-process for the vitrification of the HAW. The aqueous HAW-solution is thereby poured onto a hot glass melt. The solution thereby dries up, the HAW-salt is calcined and finally sinks into the glass melt. From today's point of view an investigation concerning the source term of the fission products and transuranic elements from the HAW at 1100 0 C therefore provides information regarding the fission product- and transuranic element volatilization within the melting furnace during the vitrification process. The results may now therefore also be considered a contribution for the layout of the off-gas purification system during the PAMELA-process

Requirements for a long-term safety certification for chemotoxic substances stored in a final storage facility for high radioactive and heat-generating radioactive waste in rock salt formations

International Nuclear Information System (INIS)

Tholen, M.; Hippler, J.; Herzog, C.

2007-01-01

Within the scope of a project funded by the German Federal Ministry of Economics and Technology (Bundesministerium fuer Wirtschaft und Technologie, BMWi), a safety certification concept for a future permanent final storage for high radioactive and heat-generating radioactive waste (HAW disposal facility) in rock salt formations is being prepared. For a reference concept, compliance with safety requirements in regard to operational safety as well as radiological and non-radiological protection objectives related to long-term safety, including ground water protection, will be evaluated. This paper deals with the requirements for a long-term safety certification for the purpose of protecting ground water from chemotoxic substances. In particular, longterm safety certifications for the permanent disposal of radioactive waste in a HAW disposal facility in rock salt formations and for the dumping of hazardous waste in underground storage facilities in rock salt formations are first discussed, followed by an evaluation as to whether these methods can be applied to the long-term safety certification for chemotoxic substances. The authors find it advisable to apply the long-term safety certification for underground storage facilities to the long-term safety certification for chemotoxic substances stored in a HAW disposal facility in rock salt formations. In conclusion, a corresponding certification concept is introduced. (orig.)

Results of research and development works 1981 of the Institute for Nuclear Waste Management Techniques

International Nuclear Information System (INIS)

1982-02-01

The emphasis of the work is on the development and characterization of waste products suitable for final storage, such as actinides and fission products from MAW/LAW, as well as on the development of methods for the treatment and solidification of radioactive wastes, e.g. wet chemical oxidation, vitrification and cementation. Investigations on the HAW-storage in salt are carried out in cooperation with the GSF. (HP) [de

Factors influencing bank geomorphology and erosion of the Haw River, a high order river in North Carolina, since European settlement.

Science.gov (United States)

Macfall, Janet; Robinette, Paul; Welch, David

2014-01-01

The Haw River, a high order river in the southeastern United States, is characterized by severe bank erosion and geomorphic change from historical conditions of clear waters and connected floodplains. In 2014 it was named one of the 10 most threatened rivers in the United States by American Rivers. Like many developed areas, the region has a history of disturbance including extensive upland soil loss from agriculture, dams, and upstream urbanization. The primary objective of this study was to identify the mechanisms controlling channel form and erosion of the Haw River. Field measurements including bank height, bankfull height, bank angle, root depth and density, riparian land cover and slope, surface protection, river width, and bank retreat were collected at 87 sites along 43.5 km of river. A Bank Erosion Hazard Index (BEHI) was calculated for each study site. Mean bank height was 11.8 m, mean width was 84.3 m, and bank retreat for 2005/2007-2011/2013 was 2.3 m. The greatest bank heights, BEHI values, and bank retreat were adjacent to riparian areas with low slope (<2). This is in contrast to previous studies which identify high slope as a risk factor for erosion. Most of the soils in low slope riparian areas were alluvial, suggesting sediment deposition from upland row crop agriculture and/or flooding. Bank retreat was not correlated to bank heights or BEHI values. Historical dams (1.2-3 m height) were not a significant factor. Erosion of the Haw River in the study section of the river (25% of the river length) contributed 205,320 m3 of sediment and 3759 kg of P annually. Concentration of suspended solids in the river increased with discharge. In conclusion, the Haw River is an unstable system, with river bank erosion and geomodification potential influenced by riparian slope and varied flows.

Physics of the mechanical toy Gee-Haw Whammy Diddle.

Science.gov (United States)

Marek, Martin; Badin, Matej; Plesch, Martin

2018-02-27

Gee-Haw Whammy Diddle is a seemingly simple mechanical toy consisting of a wooden stick and a second stick that is made up of a series of notches with a propeller at its end. When the wooden stick is pulled over the notches, the propeller starts to rotate. Despite its simplicity, physical principles governing the motion of the stick and the propeller are rather complicated and interesting. Here we provide a thorough analysis of the system and parameters influencing the motion. We show that contrary to the results published on this topic so far, neither elliptic motion of the stick nor frequency synchronization is needed for starting a stable motion of the propeller.

Commentary - Physiological variation and phenotypic plasticity: a response to 'Platicity in arthropod cryotypes' by Hawes and Bale

DEFF Research Database (Denmark)

Chown, S.L.; Sørensen, Jesper Givskov; Sinclair, B.J.

2008-01-01

In a recent publication, Hawes and Bale provide an extended discussion of phenotypic plasticity in the context of low temperature responses of animals. They argue that phenotypic plasticity may be partitioned phylogenetically at several levels and go on to explore these levels, and cold hardiness...

Amylase production by endophytic fungi Cylindrocephalum sp. isolated from medicinal plant Alpinia calcarata (Haw. Roscoe

Directory of Open Access Journals (Sweden)

V. H. Sunitha.

2012-09-01

Full Text Available Amylases are among the most important enzymes used in modern biotechnology particularly in the process involving starch hydrolysis. Fungal amylase has large applications in food and pharmaceutical industries. Considering these facts, endophytic fungi isolated from the plant Alpinia calcarata (Haw. Roscoe were screened for amylolytic activity on glucose yeast extract peptone agar (GYP medium. Among thirty isolates of endophytic fungi, isolate number seven identified as Cylindrocephalum sp. (Ac-7 showed highest amylolytic activity and was taken for further study. Influence of various physical and chemical factors such as pH, temperature, carbon and nitrogen sources on amylase production in liquid media were studied. The maximal amylase production was found to be at 30ºC and at pH 7.0 of the growth medium. Among the various carbon and nitrogen sources tested, maltose at 1.5% and Sodium nitrate at 0.3% respectively gave optimum amylase production.

The HAW-Project. Test disposal of highly radioactive radiation sources in the Asse salt mine. Final report

International Nuclear Information System (INIS)

Rothfuchs, T.; Cuevas, C. de las; Donker, H.; Feddersen, H.K.; Garcia-Celma, A.; Gies, H.; Goreychi, M.; Graefe, V.; Heijdra, J.; Hente, B.; Jockwer, N.; LeMeur, R.; Moenig, J.; Mueller, K.; Prij, J.; Regulla, D.; Smailos, E.; Staupendahl, G.; Till, E.; Zankl, M.

1995-01-01

In order to improve the final concept for the disposal of high-level radioactive waste (HAW) in boreholes drilled into salt formation plans were developed a couple of years ago for a full scale testing of the complete technical system of an underground repository. To satisfy the test objectives, thirty highly radioactive radiation sources were planned to be emplaced in six boreholes located in two test galleries at the 800-m-level in the Asse salt mine. A duration of testing of approximately five years was envisaged. Because of licensing uncertainties the German Federal Government decided on December 3rd, 1992 to stop all activities for the preparation of the test disposal immediately. In the course of the preparation of the test disposal, however, a system, necessary for handling of the radiation sources was developed and installed in the Asse salt mine and two non-radioactive reference tests with electrical heaters were started in November 1988. These tests served for the investigation of thermal effects in comparison to the planned radioactive tests. An accompanying scientific investigation programme performed in situ and in the laboratory comprises the estimation and observation of the thermal, radiation-induced, and mechanical interaction between the rock salt and the electrical heaters and the radiation sources, respectively. The laboratory investigations are carried out at Braunschweig (FRG), Petten (NL), Saclay (F) and Barcelona (E). As a consequence of the premature termination of the project the working programme was revised. The new programme agreed to by the project partners included a controlled shutdown of the heater tests in 1993 and a continuation of the laboratory activities until the end of 1994. (orig.)

Dynamic of biochemical soil properties in rainfed agave angustifolia haw. fields in semiard zone

International Nuclear Information System (INIS)

Cruz, A. B.; Cervantes, T. L.; Pacheco, R. P.; Martinez, M. D. L. R.; Perez, A. B.

2015-01-01

This study determined (a) the activity of the selected enzymes of C (invertase and cellulase), N (urease), P (acid phosphatase, AcP and alkaline phosphatase, AlkP) cycling, as well as soil microbial biomass carbon (SMBC) in the rhizosphere of Agave angustifolia Haw. (maguey espadin) cultivated in valley, hill and mountain soils in Tlacolula, Oaxaca (Mexico), and (b) changes in selected biochemical soil properties associated with seasonality and plant age. Three maguey espadin plantations with two replicates per topography were selected. Rhizosphere soil sampling was carried out for one year. AcP and urease activities were highest in mountain sites. AlkP and cellulase activities were highest in hill and mountain sites. Invertase activity and SMBC were not different among sites. Phosphatase activity showed no temporal changes. Cellulase and invertase activities were highest in December; maximum urease activity was in October and February. SMBC was highest in August. AcP activity was highest in 0-2 years old plants. AlkP activity and SMBC were highest in 2.1-4 years old plants. Urease, cellulase and invertase activity was not affected by plant age. Significant effects for the site*seasonality*plant age interaction suggest that biochemical soil properties were influenced by site. Mountain soils displayed the highest enzyme activity, which can accelerate soil organic matter turnover and contribute to the longterm sustainability of maguey espadin cropping under rainfed conditions. (author)

Long-term stable, long-term safe storage of residues and radioactive waste. Contribution to discussion to the storage (final storage); Langzeitstabile, langzeitsichere Verwahrung von Rueckstaenden und radioaktiven Abfaellen. Beitrag zur Diskussion um Lagerung (Endlagerung)

Energy Technology Data Exchange (ETDEWEB)

Lersow, Michael [DGGT e.V., Breitenbrunn/Erzgeb. (Germany). Ak 5.5 Tailings; Gellermann, Rainer [Nuclear Control and Consulting GmbH, Braunschweig (Germany)

2015-09-15

In this paper it is presented, where radioactive waste and residues occur, how these materials can be classified, which rules and regulations have to be complied with regarding the disposal and which geotechnical environmental constructions (final repositories) are suitable to guarantee a safe long-term disposal of these materials. Primary protection objective is ''to permanently prevent the transfer of toxic, radioactive contaminations into the biosphere by air, water or rock path or to keep the amount of contamination within a commonly accepted range''. Radionuclide inventories and the given time period considered for long-term safety are compared with. It is shown, that the site-specific disposal solutions cannot be justified by the radioactive inventory deposited there. The given period of 10{sup 6} years is critically evaluated. Based on this it is suggested to subdivide this period into two time periods with different prognosis reliabilities. Results of a specially designed long-term monitoring as part of the site-specific waste disposal solution should be considered for the long-term safety proof. A modular concept for the final storage of High Active Waste (HAW) is derived based on the critical evaluation of the long-term safety, including transmutation, provisional storage and monitoring module. A foundation model is proposed to guarantee the financial resources required for the disposal of HAW.

Propagação por sementes de Schlumbergera truncata (Haw. Moran (flor-de-maio em diferentes substratos = Propagation by seeds of Schlumbergera truncata (Haw. Moran (florde- maio in different substrates

Directory of Open Access Journals (Sweden)

José Renato Soares Nunes

2007-07-01

Full Text Available Schlumbergera truncata (Haw. Moran (Cactaceae, conhecida como flor-demaio, é uma espécie herbácea epífita, nativa no Brasil, muito apreciada como planta ornamental pela beleza de suas flores. Esta espécie multiplica-se por sementes, mas comercialmente é propagada por estacas e enxertia. Este trabalho teve como objetivo avaliar a germinação de quatro variedades de cores desta espécie (rosa, vermelha, branca e amarela em cinco substratos (vermiculita de granulometria média, xaxim desfibrado, areia, substrato comercial Rendmax® Floreiras e mistura de 50% do substrato comercial Rendmax®Floreiras + 50% xaxim desfibrado. Os resultados mostraram que a espécie pode ser reproduzida com facilidade por sementes. O substrato comercial Rendmax® Floreiras proporcionou os melhores resultados.Schlumbergera truncata (Haw. Moran (Cactaceae, known as “flor-de-maio”, is a Brazilian endogenous herbaceous epiphytic species, muchappreciated as ornamental for the beauty of its flowers. This species is multiplied by seeds, but commercially it is propagated by cuttings and grafting. The aim of this research was to evaluate the germination of four varieties of colors of this species (pink, red, white and yellow in five substrates (vermiculite, de-fibered tree ferns, sand, commercial substrate Rendmax® Floreiras and a mixture of 50% of the commercial substrate Rendmax® Floreiras + 50% tree ferns. The results showed that this species can be easily reproduced by seeds. The commercial substrate Rendmax® Floreiras provided the best germination result.

Long-term risk assessment of radioactive waste disposal in geological formations

International Nuclear Information System (INIS)

Girardi, F.; Bertozzi, G.; D'Alessandro, M.

1978-01-01

Methods for long-term safety analysis of waste from nuclear power production in the European Community are under study at the Joint Research Centre (JRC) at Ispra, Italy. Aim of the work is to develop a suitable methodology for long-term risk assessment. The methodology under study is based on the assessment of the quantitative value of a system of barriers which may be interposed between waste and man. The barriers considered are: a) quality of the segregation afforded by the geological formation, b) chemical and physical stability of conditioned waste, c) interaction with geological environments (subsoil retention), d) distribution in the biosphere. The methodology is presently being applied to idealized test cases based on the following assumptions: waste are generated during 30 years of operations in a nuclear park (reprocessing + refabrication plant) capable of treating 1000 ton/yr of LWR fuel. High activity waste is conditioned as borosilicate glass (HAW) while low- and medium-level wastes are bituminized (BIP). All waste is disposed off into a salt formation. Transport to the biosphere, following the containment failure occurs by groundwater, with no delay due to retention on adsorbing media. Distribution into the biosphere occurs according to the terrestrial model indicated. Under these assumptions, information was drawn concerning environmental contamination, its levels, contributing elements and pathways to man

Zoochoric and hydrochoric maritime dispersal of the Opuntia monacantha (Willd. Haw. (Cactaceae

Directory of Open Access Journals (Sweden)

Angelo Martins Fraga

2012-03-01

Full Text Available Evolutionary adaptations in the morphology and physiology of cactus species have been associated to their mechanisms of dispersal and colonization. The dispersal mechanisms and modes of Opuntia monacantha (Willd. Haw. (Cactaceae were characterized in two beaches in Florianopolis, SC, Brazil. A marsupial from the genus Didelphis (Mammalia: Didelphidae was the only frugivorous and, thus, disperser of fruits, presenting specific eating places. The maritime hydrochory was due to the overwash on restinga vegetation, it is characterized by the dispersal of cladodes and fruits at various times of the year. It is here firstly described the sea action as a potential disperser for a cactus species.

Phase transformations in lithium bearing sodiumborosilicate base glass melts for the solidification of HAW

International Nuclear Information System (INIS)

Goettlicher, J.

1994-10-01

Metastable phase separation has been observed in the Li-bearing basic glass SM58. This observation gave rise to examine the exsolution behaviour in model glasses by chemical substitution. It is impossible to produce metastable phase separation in the Li-free HAW-glasses VG98/12 and VG98/12.2. However, one can't exclude textural changes of Li-bearing glasses, because in a HAW-container the central temperature remains at about 300 C for more than 50 years. For the first time it has been tried to find a relationship between glass textures and structural parameters by combining textural investigations (electron microscopy) with structural determinations (NMR, WAXS). Modell glasses belong to the system (Li, Na) 2 O.B 2 O 3 , (Al 2 O 3 ).n(TO 2 ), with T=Si, Ge and n=2, 4, 6. Furthermore glasses from the KfK and from Mol (PAMELA) were investigated. A newly built apparatus was used to prepare glasses by replica technique (PtIrC oblique shadowing) for TEM investigations. This method turned out to be well suited to study glass textures with features down to 5 nm. Sometimes direct examinations of ion-thinned glasses showed that their textures were affected by radiation damage, caused by accelerated electrons. LVSE-(Low Voltage Scanning Electron)- and AF-(Atomic Force)- microscopy seems to be a promising method for studying glass surfaces and their textures directly. (orig./MM) [de

Partitioning of actinides from high active waste solution of Purex origin counter-current extraction studies using TBP and CMPO

International Nuclear Information System (INIS)

Chitnis, R.R.; Dhami, P.S.; Gopalkrishnan, V.; Wattal, P.K.; Ramanujam, A.; Murali, M.S.; Mathur, J.N.; Bauri, A.K.; Chattopadhyay, S.

2000-10-01

A solvent extraction scheme has been formulated for the partitioning of actinides from Purex high level waste (HLW). The scheme is based on the results of earlier studies carried out with simulated waste solutions. In the present studies, the scheme was tested with high active waste (HAW) solution generated during the reprocessing of spent fuel from research reactors using laboratory scale mixer-settlers. The proposed process involved two-step extraction using tri-n-butyl phosphate (TBP) and octyl (phenyl)-N,N-diisobutylcarbamolylmethylphosphine oxide (CMPO). In the first step, uranium, neptunium and plutonium were removed from the waste using TBP as extractant. The minor actinides left in the raffinate were extracted using a mixture of CMPO and TBP in the second step. The results showed complete extraction of actinides from the waste solution. Plutonium and neptunium extracted in TBP, were stripped together using a mixture of hydrogen peroxide and ascorbic acid in 2 M nitric acid medium, leaving uranium in the organic phase. Uranium can later be stripped using dilute nitric acid. Actinides extracted in CMPO-TBP phase were stripped using a mixture of formic acid, hydrazine, hydrate and citric acid. The stripping was quantitative in both the stripping runs. An additional extraction step for the preferential recovery of uranium, neptunium and plutonium from the waste solution using TBP is a modification over the conventional Truex process. Selective stripping of neptunium and plutonium from large quantities of uranium. The extraction of uranium using TBP eliminates the possibility of third phase and undesired loading of CMPO-TBP in the following step. Use of citrate-containing strippant allows the recovery of actinides from loaded CMPO-TBP mixture without causing any reflux of the actinides during stripping. The process has been developed with due consideration to minimising the generation of secondary wastes. The proposed strippants are effective even in presence of

TRUEX partitioning from radioactive ICPP sodium bearing waste

International Nuclear Information System (INIS)

Herbst, R.S.; Brewer, K.N.; Tranter, T.J.; Todd, T.A.

1995-03-01

The Idaho Chemical Processing Plant (ICPP) located at the Idaho National Engineering Laboratory in Southeast Idaho is currently evaluating several treatment technologies applicable to waste streams generated over several decades of-nuclear fuel reprocessing. Liquid sodium bearing waste (SBW), generated primarily during decontamination activities, is one of the waste streams of interest. The TRansUranic EXtraction (TRUEX) process developed at Argonne National Laboratory is currently being evaluated to separate the actinides from SBW. On a mass basis, the amount of the radioactive species in SBW are low relative to inert matrix components. Thus, the advantage of separations is a dramatic decrease in resulting volumes of high activity waste (HAW) which must be dispositioned. Numerous studies conducted at the ICPP indicate the applicability of the TRUEX process has been demonstrated; however, these studies relied on a simulated SBW surrogate for the real waste. Consequently, a series of batch contacts were performed on samples of radioactive ICPP SBW taken from tank WM-185 to verify that actual waste would behave similarly to the simulated waste. The test results with SBW from tank WM-185 indicate the TRUEX solvent effectively extracts the actinides from the samples of actual waste. Gross alpha radioactivity, attributed predominantly to Pu and Am, was reduced from 3.14E+04 dps/mL to 1.46 dps/mL in three successive batch contacts with fresh TRUEX solvent. This reduction corresponds to a decontamination factor of DF = 20,000 or 99.995% removal of the gross a activity in the feed. The TRUEX solvent also extracted the matrix components Zr, Fe, and Hg to an appreciable extent (D Zr > 10, D Fe ∼ 2, D Hg ∼6). Iron co-extracted with the actinides can be successfully scrubbed from the organic with 0.2 M HNO 3 . Mercury can be selectively partitioned from the actinides with either sodium carbonate or nitric acid (≥ 5 M HNO 3 ) solutions

Activation/waste management

International Nuclear Information System (INIS)

Maninger, C.

1984-10-01

The selection of materials and the design of the blankets for fusion reactors have significant effects upon the radioactivity generated by neutron activation in the materials. This section considers some aspects of materials selection with respect to waste management. The activation of the materials is key to remote handling requirements for waste, to processing and disposal methods for waste, and to accident severity in waste management operations. In order to realize the desirable evnironmental potentials of fusion power systems, there are at least three major goals for waste management. These are: (a) near-surface burial; (b) disposal on-site of the fusion reactor; (c) acceptable radiation doses at least cost during and after waste management operations

The long path to a disposal for high radioactive waste. Pt. 1. A new approach for a better understanding of processes and the system in a whole; Auf dem langen Weg zu einem Endlager fuer hochradioaktive Waerme entwickelnde Abfaelle. T. 1. Ein neuer konzeptionell-konfigurativer Ansatz und ein neues Simulationswerkzeug zur Erarbeitung eines verbesserten Prozess- und Systemverstaendnisses fuer HAW-Entsorgungsanlagen - ohne und mit direktem laengerfristigem Monitoring

Energy Technology Data Exchange (ETDEWEB)

Lux, Karl-Heinz; Wolters, Ralf; Zhao, Juan [Technische Univ. Clausthal, Clausthal-Zellerfeld (Germany). Inst. fuer Aufbereitung, Deponiertechnik und Geomechanik

2017-03-15

A new conceptual-configurative approach and a new simulation tool for the development of an improved process and system understanding for HAW disposal systems - without and with direct long-term monitoring are presented and discussed. With regard to the final repository development, a retrievability of the heat-generating high-radioactive waste during the storage phase and a general recoverability during the first 500 years after closure of the repository in the post-closure phase are required. Both for the monitoring of the repository during the storage phase as well as thereafter, a direct monitoring of the storage horizon could be implemented as an alternative to an indirect monitoring.

CASTOR(r) and CONSTOR(r) type transport and storage casks for spent fuel and high active waste

International Nuclear Information System (INIS)

Kuehne, B.; Sowa, W.

2002-01-01

The German company GNB has developed, tested, licensed, fabricated, loaded, transported and stored a large number of casks for spent fuel and high-level waste. CASTOR(r) casks are used at 18 sites on three continents. Spent fuel assemblies of the types PWR, BWR, VVER, RBMK, MTR and THTR as well as vitrified high active waste (HAW) containers are stored in these kinds of casks. More than 600 CASTOR(r) casks have been loaded for long-term storage. The two decades of storage have shown that the basic requirements, which are safe confinement, criticality safety, sufficient shielding and appropriate heat transfer have been fulfilled in each case. There is no indication that problems will arise in the future. Of course, the experience of 20 years has resulted in improvements of the cask design. One basic improvement is GNB's development since the mid 1990s of a sandwich cask design using heavy concrete and steel as basic materials, for economical and technical reasons. This CONSTOR(r) cask concept also fulfils all design criteria for transport and storage given by the IAEA recommendations and national authorities. By May 2002 40 CONSTOR(r) casks had been delivered and 15 had been successfully loaded and stored. In this paper the different types of casks are presented. Experiences gained during the large number of cask loadings and more than 4000 cask-years of storage will be summarised. The presentation of recent and future development shows the optimisation potential of the CASTOR(r) and CONSTOR(r) cask families for safe and economical management of spent fuel. (author)

Accumulated energy determination in salts rocks irradiated by means of thermoluminescence techniques: application to the high level radioactive wastes repositories analysis

International Nuclear Information System (INIS)

Dies, J.; Ortega. J.; Tarrasa. F.; Cuevas, C.

1995-01-01

The report summarizes the study carried out to develop the radiation effects on salt rocks in order to repository the high level radioactive wastes. The study is structured into 3 main aspects: 1.- Analysis of irradiation experiences in Haw project of Pet ten reactor. 2.- Irradiation of salt sample of CESAR industrial irradiator. 3.- Correlation study between the accumulated energy, termoluminescence answer and the defect concentration

Institute of Nuclear Waste Management Technology (INE). 1994 progress report on research and development

International Nuclear Information System (INIS)

1995-01-01

In 1994 INE worked on the following research projects: radionuclide behaviour during corrosion of high-level radioactive COGEMA glass; studies of glassy basalt of the Werra-Fulda salt deposit as a natural analogue of the corrosion of HAW glass; corrosion studies of high burnup LWR fuels in brine; chemical behaviour of Tc in aqueous, chloride systems; corrosion studies of waste container materials; solution chemistry of U; thermodynamics of Np(V) in concentrated brines; radiation-chemical effects in the vicinity of repositories; laser spectroscopic speciation and thermodynamics of Cm(III); development of laser spectroscopic methods; radiochemical and chemical analyses of nuclear samples; solid-state and surface analyses; coupling of transport and speciation models; influence of colloid formation on the migration behaviour of long-lived radionuclides; studies of the consolidation behaviour of filling material; thermomechanical effects of inhomogeneities in the salt dome; basic studies and process engineering developments in the field of solidification of high-level radioactive fission product solutions; corrosion behaviour of WAK-HAW containing glass products in brines. (orig./HP) [de

Radioactive waste management in Germany

International Nuclear Information System (INIS)

Brammer, K.J.

2011-01-01

The responsibility for the disposal of radioactive waste is regulated in the Federal Republic of Germany in the Atomic Energy Act. Basically, it is the responsibility of the waste producers to carry out all necessary processing steps up to the delivery to a repository. The Federal Republic reserves the right to select, explore and operate the repository (§ 9a, para. 3 AtG). The costs of all necessary expenditures of this task are borne by the waste producers in accordance with § 21 AtG regulation. The waste quantity forecasts have shown that by the year 2080 a total volume of about 300,000 m3 of low- and intermediate-level (non-heat-generating) waste will be generated in research, industry, medicine and in the production of electricity in nuclear power plants. This waste is to be transported to the ‘Konrad repository’ which is under construction. The Federal Office for Radiation Protection (BfS), which is responsible for the construction and operation, intends to commission the repository at 2019. As a repository for heat-generating wastes, i. Approximately 10.000 tSM spent fuel (BE) 7,500 molds (HAW and MAW, corresponding to about 6000 tSM) returned Waste from reprocessing, the Gorleben salt dome has been explored since 1979. The works were resumed on 01.10.2010 after a 10-year break. Federal Environment Minister Röttgen has made it clear that the Federal Government has proposed a transparent procedure and a dialogue and participation procedure for open-ended exploration. (roessner)

Treatment of solid non-active wastes

International Nuclear Information System (INIS)

Chmielewska, E.

2008-01-01

In this part of the text-book treatment of solid non-active wastes is described. This part consist of following chapters: (1) Law on wastes; (2) Present situation in waste management; (3) Strategic tendencies of waste management; (4) Incineration (disposal of solid wastes); (5) Disposal; (6) Composting; (7) Treatment of sludge from sewage clarification plant; (8) Biodegradation; (9) Recycling of wastes (assessing of secondary raw materials). Legal aspects of treatment of solid non-active wastes is presented

Involvement of arginine-vasopressin in the diuretic and hypotensive effects of Pereskia grandifolia Haw. (Cactaceae).

Science.gov (United States)

Kazama, Caroline Calixto; Uchida, Denise Thiemi; Canzi, Karina Natally; de Souza, Priscila; Crestani, Sandra; Gasparotto, Arquimedes; Laverde, Antonio

2012-10-31

Pereskia grandifolia Haw. (Cactaceae), popularly known as "ora-pro-nobis" is well recognized in Brazilian traditional medicine as a diuretic agent, although no scientific data have been published to support this effect. The aim of this work is to evaluate the diuretic and hypotensive activities of the infusion (INFPG) and the ethanol extract (HEPG) of Pereskia grandifolia and possible mechanism of action. The infusions (2.5-10%) and the HEPG (3-100 mg/kg) were orally administered in a single dose or daily (for seven days) to rats. The urine excretion rate, pH, density, conductivity and content of Na(+), K(+), Cl(-) and HCO(3)(-) were measured in the urine of saline-loaded animals. In collected serum samples the concentration of electrolytes, urea, creatinine, aldosterone, vasopressin and angiotensin converting enzyme (ACE) activity were evaluated. The involvement of V(2) vasopressin receptor in the diuretic activity and the hypotensive effect of HEPG were also determined. Water excretion rate was significantly increased by HEPG, while the urinary K(+) and Cl(-) excretion was significantly reduced in acute and prolonged treatment. The oral administration of the HEPG (30mg/kg) significantly reduced serum levels of vasopressin and the mean arterial pressure (MAP) in normotensive rats. All other evaluated parameters have not been affected by any treatment. The results showed that HEPG could present compound(s) responsible for aquaretic activities with no signs of toxicity, and this effect could involve a reduction in the arginine-vasopressin release. Copyright © 2012 Elsevier Ireland Ltd. All rights reserved.

Low-Activity Radioactive Wastes

Science.gov (United States)

In 2003 EPA published an Advance Notice of Proposed Rulemaking (ANPR) to collect public comment on alternatives for disposal of waste containing low concentrations of radioactive material ('low-activity' waste).

Finite element analyses of a heater-interruption in the HAW test field

International Nuclear Information System (INIS)

Horn, B.A. van den.

1991-09-01

In this report the results of two finite element analyses of the HAW field are presented. The determination of the influence of a heater-interruption on the tube load as well as the differences in the evaluation of the tube load for both types of boreholes (type A and type B) are the main objectives of this report. Axisymmetric models are made for both type of boreholes in order to simulate this heater-interruption. It appeared that a heater-interruption of 4 hours leads to a temperature drop of 17.2deg C at the borehole wall and to a maximum reduction of the tube load of 1.76 MPa. About 20 days after reparation of the heaters of the heaters the evolution of the maximum temperature and the maximum tube load will be rehabilitated; the difference with the corresponding evolutions due to an uninterrupted heat-production are negligible. (author). 9 refs.; 25 figs.; 5 tabs

Nonlinear models applied to seed germination of Rhipsalis cereuscula Haw (Cactaceae

Directory of Open Access Journals (Sweden)

Terezinha Aparecida Guedes

2014-09-01

Full Text Available The objective of this analysis was to fit germination data of Rhipsalis cereuscula Haw seeds to the Weibull model with three parameters using Frequentist and Bayesian methods. Five parameterizations were compared using the Bayesian analysis to fit a prior distribution. The parameter estimates from the Frequentist method were similar to the Bayesian responses considering the following non-informative a priori distribution for the parameter vectors: gamma (10³, 10³ in the model M1, normal (0, 106 in the model M2, uniform (0, Lsup in the model M3, exp (μ in the model M4 and Lnormal (μ, 106 in the model M5. However, to achieve the convergence in the models M4 and M5, we applied the μ from the estimates of the Frequentist approach. The best models fitted by the Bayesian method were the M1 and M3. The adequacy of these models was based on the advantages over the Frequentist method such as the reduced computational efforts and the possibility of comparison.

Physiological differences and changes in global DNA methylation levels in Agave angustifolia Haw. albino variant somaclones during the micropropagation process.

Science.gov (United States)

Duarte-Aké, Fátima; Castillo-Castro, Eduardo; Pool, Felipe Barredo; Espadas, Francisco; Santamaría, Jorge M; Robert, Manuel L; De-la-Peña, Clelia

2016-12-01

Global DNA methylation changes caused by in vitro conditions are associated with the subculturing and phenotypic variation in Agave angustifolia Haw. While the relationship between the development of albinism and in vitro culture is well documented, the role of epigenetic processes in this development leaves some important questions unanswered. During the micropropagation of Agave angustifolia Haw., we found three different phenotypes, green (G), variegated (V) and albino (A). To understand the physiological and epigenetic differences among the somaclones, we analyzed several morphophysiological parameters and changes in the DNA methylation patterns in the three phenotypes during their in vitro development. We found that under in vitro conditions, the V plantlets maintained their CAM photosynthetic capacity, while the A variant showed no pigments and lost its CAM photosynthetic ability. Epigenetic analysis revealed that global DNA methylation increased in the G phenotype during the first two subcultures. However, after that time, DNA methylation levels declined. This hypomethylation correlated with the appearance of V shoots in the G plantlets. A similar correlation occurred in the V phenotype, where an increase of 2 % in the global DNA methylation levels was correlated with the generation of A shoots in the V plantlets. This suggests that an "epigenetic stress memory" during in vitro conditions causes a chromatin shift that favors the generation of variegated and albino shoots.

Morfoanatomia vegetativa de Opuntia brasiliensis (Willd Haw / Vegetative morphology and anatomy of Opuntia brasiliensis (Willd Haw

Directory of Open Access Journals (Sweden)

Camila Firmino de Azevedo

2013-01-01

Full Text Available Opuntia brasiliensis (Willd Haw. é uma Cactaceae nativa do Brasil utilizada como ornamental, que apresenta caracteres morfológicos semelhantes a outras espécies do gênero, o que dificulta sua identificação. Dessa forma, foi realizado uma descrição morfoanatômica de O. brasiliensis com o objetivo de ampliar o conhecimento sobre a organização estrutural do gênero e fornecer subsídios para a identificação da espécie, bem como observar caracteres importantes na adaptação a ambientes xerófilos. Foram feitas secções transversais e paradérmicas da raiz, caule principal e cladódios com espécimes coletados na zona rural da cidade de Serra Branca (PB, localizada na região do cariri ocidental. O. brasiliensis apresenta raiz ramificada e caule clorofilado formando um eixo principal de onde partem inúmeros cladódios delgados. Observamse pelos e epiderme unisseriada irregular na raiz, que possui córtex formado por parênquima, seguido de endoderme multisseriada e periciclo. No cilindro central da raiz, ocorrem tecidos vasculares formando cinco pólos seguidos de medula. O caule e o cladódio apresentam epiderme com paredes sinuosas, em que encontram-se estômatos paralelocíticos que apresentam câmara subestomática; e na camada subsequente, hipoderme com grande quantidade de drusas de oxalato de cálcio. O córtex é formado por parênquimas clorofiliano e aquífero, onde observam-se feixes vasculares, com raios de floema voltados para o lado externo, seguido de xilema helicoidal. Porém, nos cladódios, o parênquima clorofiliano é bem mais denso e os feixes vasculares são dispostos irregularmente, enquanto no caule estão distribuídos no sentido radial. O. brasiliensis apresenta várias características importantes na sua identificação, bem como adaptações estruturais a ambientes xerófilos

The very-low activity waste storage facility. A new waste management system

International Nuclear Information System (INIS)

2006-01-01

Very-low activity wastes have a radioactivity level close to the natural one. This category of waste is taken into consideration by the French legislation and their storage is one of their point of achievement. This document gives a complete overview of the principles of storage implemented at the storage center for very-low activity wastes (CSTFA) sited in the Aube departement in the vicinity of the storage center for low- and intermediate activity wastes: storage concept, wastes confinement, center organization, environmental monitoring. (J.S.)

Development of an assessment methodology for the disposal of high-level radioactive waste into deep ocean sediments

International Nuclear Information System (INIS)

Murray, C.N.; Stanners, D.A.

1982-01-01

This paper presents the results of a theoretical study concerning the option of disposal of vitrified high activity waste (HAW) into deep ocean sediments. The development of a preliminary methodology is presented which concerns the assessment of the possible effects of a release of radioactivity on the ecosystem and eventually on man. As the long-term hazard is considered basically to be due to transuranic elements (and daughter products) the period studied for the assessment is from 10 3 to 10 6 years. A simple ecosystem model is developed so that the transfer of activity between different compartments of the systems, e.g. the sediment column, sediment-water interface, deep sea water column, can be estimated. A critical pathway analysis is made for an imaginary critical group in order to complete the assessment. A sensitivity analysis is undertaken using the computed minimum-maximum credible values for the different parameters used in the calculations in order to obtain a minimum-maximum dose range for a critical group. (Auth.)

Shielding calculations with SCALE/MAVRIC and comparison with measurements for the TN85 cask with vitrified high level radioactive waste

Science.gov (United States)

Thiele, Holger; Börst, Frank-Michael

2017-09-01

A series of dose rate/spectra measurements in the German interim storage facility Gorleben was carried out at a TN85 cask in April 2009. This type of cask is used for the transport and interim storage of vitrified high level radioactive waste (HAW) from reprocessing. The aim of this work is to assess the shielding component MAVRIC of the SCALE code system with these measurements for the use in the German Bundesamt für Kerntechnische Entsorgungssicherheit (BfE).

Solid Waste Activity Packet for Teachers.

Science.gov (United States)

Illinois Univ., Urbana. Cooperative Extension Service.

This solid waste activity packet introduces students to the solid waste problem in Illinois. Topics explore consumer practices in the market place, packaging, individual and community garbage generation, and disposal practices. The activities provide an integrated approach to incorporating solid waste management issues into subject areas. The…

Geological and geotechnical limitations of radioactive waste retrievability in geologic disposals

Energy Technology Data Exchange (ETDEWEB)

Stahlmann, Joachim; Leon-Vargas, Rocio; Mintzlaff, Volker; Treidler, Ann-Kathrin [TU Braunschweig (Germany). Inst. for Soil Mechanics and Foundation Engineering

2015-07-01

The capability of retrieving radioactive waste emplaced in deep geological formations is nowadays in discussion in many countries. Based on the storage of high-level radioactive waste (HAW) in deep geological repositories there is a number of possible scenarios for their retrieval. Measurements for an improved retrieving capability may impact on the geotechnical and geological barriers, e.g. keeping open the access drifts for a long period of time can result in a bigger evacuation damage zone (EDZ) in the host rock which implies potential flow paths for ground water. Nevertheless, to limit the possible scenarios associated to the retrieval implementation, it is necessary to take in consideration which criteria will be used for an efficient monitoring program, while clearly determining the performance reliability of the geotechnical barriers. In addition, the integrity of the host rock as geological barrier has to be verified. Therefore, it is important to evaluate different design solutions and the most appropriate measurement methods to improve the retrievability process of wastes from a geological repository. A short presentation of the host rocks is given is this paper.

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.

Enzyme Activities in Waste Water and Activated Sludge

DEFF Research Database (Denmark)

Nybroe, Ole; Jørgensen, Per Elberg; Henze, Mogens

1992-01-01

The purpose of the present study was to evaluate the potential of selected enzyme activity assays to determine microbial abundance and heterotrophic activity in waste water and activated sludge. In waste water, esterase and dehydrogenase activities were found to correlate with microbial abundance...... measured as colony forming units of heterotrophic bacteria. A panel of four enzyme activity assays, α-glucosidase, alanine-aminopeptidase, esterase and dehydrogenase were used to characterize activated sludge and anaerobic hydrolysis sludge from a pilot scale plant. The enzymatic activity profiles were...... distinctly different, suggesting that microbial populations were different, or had different physiological properties, in the two types of sludge. Enzyme activity profiles in activated sludge from four full-scale plants seemed to be highly influenced by the composition of the inlet. Addition of hydrolysed...

Regulation of higher-activity NARM wastes by EPA

International Nuclear Information System (INIS)

Bandrowski, M.S.

1988-01-01

The US Environmental Protection Agency (EPA) is currently developing standards for the disposal of low-level radioactive waste (LLW). As part of this Standard, EPA is including regulations for the disposal of naturally occurring and accelerator-produced radioactive material (NARM) wastes not covered under the Atomic Energy Act (AEA). The regulations will cover only higher-activity NARM wastes, defined as NARM waste with specific activity exceeding two nanocuries per gram. The proposed regulations will specify that NARM wastes exceeding the above limits, except for specific exempted items, must be disposed of in regulated radioactive waste disposal facilities. The proposed EPA regulations for NARM wastes will be discussed, as well as the costs and benefits of the regulation, how it will be implemented by EPA, and the rationale for covering only higher-activity NARM wastes exceeding two nanocuries per gram

Geotechnical and geological aspects for repository concepts with retrievability of radioactive waste; Geotechnische und geologische Aspekte fuer Tiefenlagerkonzepte mit der Option der Rueckholung der radioaktiven Reststoffe

Energy Technology Data Exchange (ETDEWEB)

Stahlmann, Joachim; Leon Vargas, Rocio; Mintzlaff, Volker [Technische Univ. Braunschweig (Germany). Inst. fuer Grundbau und Bodenmechanik

2016-03-15

The retrievability of heat-producing high-level radioactive waste (HAW) is on debate internationally as well as in Germany. This article deals with the geological and geotechnical consequences of the design of a repository with retrievability in different host rocks. The properties of rock salt, clay, shale and crystalline rock - potential host rocks for a repository with retrievability in Germany - will be presented. Based on these properties generic models of repositories with measurements for retrievability and monitoring will be also presented. With these models it can be derived that due the different stress-deformation-behavior there is a conflict of aims between the best possible closure of the waste and the option of retrieval.

Recent activity on disposal of uranium waste

International Nuclear Information System (INIS)

Fujiwara, Noboru

1999-01-01

The concept on the disposal of uranium waste has not been discussed in the Atomic Energy Commission of Japan, but the research and development of it are carried out in the company and agency which are related to uranium waste. In this paper, the present condition and problems on disposal of uranium waste were shown in aspect of the nuclear fuel manufacturing companies' activity. As main contents, the past circumstances on the disposal of uranium waste, the past activity of nuclear fuel manufacturing companies, outline and properties of uranium waste were shown, and ideas of nuclear fuel manufacturing companies on the disposal of uranium waste were reported with disposal idea in the long-term program for development and utilization of nuclear energy. (author)

Compaction and packaging of dry active municipal wastes

International Nuclear Information System (INIS)

Chen Zongming; Xi Xinmin

1994-01-01

The authors present the feature of a compaction system for active municipal wastes and the radiological monitoring results of workplace and environment. A variety of dry active municipal wastes could be compacted by this system. Volume reduction factor attained to 5 to 7 for soft wastes and 8 to 13 for hard wastes. No evident radiological impact was found on workplace and environment

Solidification of highly active wastes

International Nuclear Information System (INIS)

Morris, J.B.

1986-07-01

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

Segregation of low-level dry active waste

International Nuclear Information System (INIS)

Kornblith, L. Jr.; Naughton, M.D.; Welsh, L.

1984-01-01

A program has been carried out to characterize the Dry Active Waste (DAW) stream from a typical PWR power plant in order to determine the usefulness of large-volume DAW monitors for segregating such waste in order to dispose of it in appropriate facilities. A waste monitor using plastic scintillation counters was used for measuring the waste. The monitor had a volume of about 300 liters and an overall efficiency of about 12% for a typical fission product mixture. It provides automatic compensation for background radioactivity and can measure a bag of waste in less than a minute, including background measurements. Six hundred consecutively generated bags of DAW were measured. These had a total activity of about one millicurie and an average specific activity of about 540 nanocuries per kilogram. About half of the bags contained less than 1000 nanocuries and had specific activities of less than 100 nanocuries per kilogram. Based on simplified preliminary calculations, it appears that an evaluation of the risks of disposal of bags such as these in a landfill other than a low-level waste disposal facility could be carried out that would demonstrate that such disposal of half or more of these bags would not result in any substantial hazard, either short or long term

Propagação por sementes de Schlumbergera truncata (Haw. Moran (flor-de-maio em diferentes substratos - DOI: 10.4025/actascibiolsci.v29i3.480 Propagation by seeds of Schlumbergera truncata (Haw. Moran (florde- maio in different substrates - DOI: 10.4025/actascibiolsci.v29i3.480

Directory of Open Access Journals (Sweden)

Daniela Biondi

2007-12-01

Full Text Available Schlumbergera truncata (Haw. Moran (Cactaceae, conhecida como flor-demaio, é uma espécie herbácea epífita, nativa no Brasil, muito apreciada como planta ornamental pela beleza de suas flores. Esta espécie multiplica-se por sementes, mas comercialmente é propagada por estacas e enxertia. Este trabalho teve como objetivo avaliar a germinação de quatro variedades de cores desta espécie (rosa, vermelha, branca e amarela em cinco substratos (vermiculita de granulometria média, xaxim desfibrado, areia, substrato comercial Rendmax® Floreiras e mistura de 50% do substrato comercial Rendmax® Floreiras + 50% xaxim desfibrado. Os resultados mostraram que a espécie pode ser reproduzida com facilidade por sementes. O substrato comercial Rendmax® Floreiras proporcionou os melhores resultados.Schlumbergera truncata (Haw. Moran (Cactaceae, known as “flor-de-maio”, is a Brazilian endogenous herbaceous epiphytic species, much appreciated as ornamental for the beauty of its flowers. This species is multiplied by seeds, but commercially it is propagated by cuttings and grafting. The aim of this research was to evaluate the germination of four varieties of colors of this species (pink, red, white and yellow in five substrates (vermiculite, de-fibered tree ferns, sand, commercial substrate Rendmax® Floreiras and a mixture of 50% of the commercial substrate Rendmax® Floreiras + 50% tree ferns. The results showed that this species can be easily reproduced by seeds. The commercial substrate Rendmax® Floreiras provided the best germination result.

Activities in department of energy hazardous and mixed waste defense waste management

International Nuclear Information System (INIS)

Eyman, L.D.

1988-01-01

In January 1986, the U.S. Department of Energy (DOE) Office of Assistant Secretary for Defense Programs (DP) created the Hazardous Waste and Remedial Actions Division within the Office of Defense Waste and Transportation Management. The Oak Ridge Operations Office (ORO) was assigned the responsibility for supporting DOE Headquarters (HQ) in planning nationally integrated activities for Resource Conservation and Recovery Act/Comprehensive Environmental Response, Compensation, and Liability Act/Superfund Amendments and Reauthorization Act (RCRA/CERCLA/SARA) compliance. In turn, ORO created the Hazardous Waste Remedial Actions Program Support Contractor Office (HAZWRAPSCO) to assist with the expanded lead assignment. The HAZWRAPSCO activities are currently supported by three distinct DOE-HQ funding elements: the Environmental Restoration Program, the Hazardous Waste Compliance Technology Program, and the Hazardous Waste Research and Development R and D Program. The Environmental Restoration Program is discussed in the paper, entitled The DOE Defense Program for Environmental Restoration

Hanford immobilized low-activity tank waste performance assessment

International Nuclear Information System (INIS)

Mann, F.M.

1998-01-01

The Hanford Immobilized Low-Activity Tank Waste Performance Assessment examines the long-term environmental and human health effects associated with the planned disposal of the vitrified low-level fraction of waste presently contained in Hanford Site tanks. The tank waste is the by-product of separating special nuclear materials from irradiated nuclear fuels over the past 50 years. This waste has been stored in underground single and double-shell tanks. The tank waste is to be retrieved, separated into low and high-activity fractions, and then immobilized by private vendors. The US Department of Energy (DOE) will receive the vitrified waste from private vendors and plans to dispose of the low-activity fraction in the Hanford Site 200 East Area. The high-level fraction will be stored at Hanford until a national repository is approved. This report provides the site-specific long-term environmental information needed by the DOE to issue a Disposal Authorization Statement that would allow the modification of the four existing concrete disposal vaults to provide better access for emplacement of the immobilized low-activity waste (ILAW) containers; filling of the modified vaults with the approximately 5,000 ILAW containers and filler material with the intent to dispose of the containers; construction of the first set of next-generation disposal facilities. The performance assessment activity will continue beyond this assessment. The activity will collect additional data on the geotechnical features of the disposal sites, the disposal facility design and construction, and the long-term performance of the waste. Better estimates of long-term performance will be produced and reviewed on a regular basis. Performance assessments supporting closure of filled facilities will be issued seeking approval of those actions necessary to conclude active disposal facility operations. This report also analyzes the long-term performance of the currently planned disposal system as a basis

Hanford immobilized low-activity tank waste performance assessment

Energy Technology Data Exchange (ETDEWEB)

Mann, F.M.

1998-03-26

The Hanford Immobilized Low-Activity Tank Waste Performance Assessment examines the long-term environmental and human health effects associated with the planned disposal of the vitrified low-level fraction of waste presently contained in Hanford Site tanks. The tank waste is the by-product of separating special nuclear materials from irradiated nuclear fuels over the past 50 years. This waste has been stored in underground single and double-shell tanks. The tank waste is to be retrieved, separated into low and high-activity fractions, and then immobilized by private vendors. The US Department of Energy (DOE) will receive the vitrified waste from private vendors and plans to dispose of the low-activity fraction in the Hanford Site 200 East Area. The high-level fraction will be stored at Hanford until a national repository is approved. This report provides the site-specific long-term environmental information needed by the DOE to issue a Disposal Authorization Statement that would allow the modification of the four existing concrete disposal vaults to provide better access for emplacement of the immobilized low-activity waste (ILAW) containers; filling of the modified vaults with the approximately 5,000 ILAW containers and filler material with the intent to dispose of the containers; construction of the first set of next-generation disposal facilities. The performance assessment activity will continue beyond this assessment. The activity will collect additional data on the geotechnical features of the disposal sites, the disposal facility design and construction, and the long-term performance of the waste. Better estimates of long-term performance will be produced and reviewed on a regular basis. Performance assessments supporting closure of filled facilities will be issued seeking approval of those actions necessary to conclude active disposal facility operations. This report also analyzes the long-term performance of the currently planned disposal system as a basis

Wastes Characterisation from Foundry Activities on European Level

International Nuclear Information System (INIS)

Andres, I.; Ruiz, C.; Ibanez, R.; Viguri, J.; Irabien, A.

1999-01-01

This work presents The results of the eco toxicological characterisation of 22 defined wastes from steel foundry activities. The wastes have been selected from three processes, steel mill (smelting). sand casting and cleaning and finishing of steel products,with the common characteristics of represent an important industrial activity in the area and generated the wastes considered in this study. The eco toxicological characterisation obtained applying the Spanish regulations on hazardous waste is compared to the hazardous attributions considered by the European Union in order to characterise a waste as hazardous (non hazardous). The results allow to conclude that a acceptable concordance between both methodologies is reached and remark the need to split the broad generic types of wastes given by the Spanish regulation (Eco toxic / non eco toxic) into clearly identifiable specific types of waste

Permitting plan for the immobilized low-activity waste project

International Nuclear Information System (INIS)

Deffenbaugh, M.L.

1997-01-01

This document addresses the environmental permitting requirements for the transportation and interim storage of the Immobilized Low-Activity Waste (ILAW) produced during Phase 1 of the Hanford Site privatization effort. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage and disposal of Tank Waste Remediation Systems (TWRS) immobilized low-activity tank waste (ILAW) and (2) interim storage of TWRS immobilized HLW (IHLW) and other canistered high-level waste forms. Low-activity waste (LAW), low-level waste (LLW), and high-level waste (HLW) are defined by the TWRS, Hanford Site, Richland, Washington, Final Environmental Impact Statement (EIS) DOE/EIS-0189, August 1996 (TWRS, Final EIS). By definition, HLW requires permanent isolation in a deep geologic repository. Also by definition, LAW is ''the waste that remains after separating from high-level waste as much of the radioactivity as is practicable that when solidified may be disposed of as LLW in a near-surface facility according to the NRC regulations.'' It is planned to store/dispose of (ILAW) inside four empty vaults of the five that were originally constructed for the Group Program. Additional disposal facilities will be constructed to accommodate immobilized LLW packages produced after the Grout Vaults are filled. The specifications for performance of the low-activity vitrified waste form have been established with strong consideration of risk to the public. The specifications for glass waste form performance are being closely coordinated with analysis of risk. RL has pursued discussions with the NRC for a determination of the classification of the Hanford Site's low-activity tank waste fraction. There is no known RL action to change law with respect to onsite disposal of waste

Method to determine the activity concentration and total activity of radioactive waste

International Nuclear Information System (INIS)

Angeles C, A.

2001-02-01

A characteristic system of radioactive waste is described to determine the concentration of radionuclides activity and the total activity of bundles of radioactive waste. The system this integrated by three subsystems: - Elevator of drums. - Electromechanics. - Gamma spectroscopy. In the system it is analyzed waste of issuing gamma specifically, and this designed for materials of relative low density and it analyzes materials of cylindrical recipients

Technical baseline description of high-level waste and low-activity waste feed mobilization and delivery

International Nuclear Information System (INIS)

Papp, I.G.

1997-01-01

This document is a compilation of information related to the high-level waste (HLW) and low-activity waste (LAW) feed staging, mobilization, and transfer/delivery issues. Information relevant to current Tank Waste Remediation System (TWRS) inventories and activities designed to feed the Phase I Privatization effort at the Hanford Site is included. Discussions on the higher level Phase II activities are offered for a perspective on the interfaces

Novel Activated Carbons from Agricultural Wastes and their Characterization

Directory of Open Access Journals (Sweden)

S. Karthikeyan

2008-01-01

Full Text Available Solid waste disposal has become a major problem in India, Either it has to be disposed safely or used for the recovery of valuable materials as agricultural wastes like turmeric waste, ferronia shell waste, jatropha curcus seed shell waste, delonix shell waste and ipomea carnia stem. Therefore these wastes have been explored for the preparation of activated carbon employing various techniques. Activated carbons prepared from agricultural solid wastes by chemical activation processes shows excellent improvement in the surface characteristics. Their characterization studies such as bulk density, moisture content, ash content, fixed carbon content, matter soluble in water, matter soluble in acid, pH, decolourising power, phenol number, ion exchange capacity, ion content and surface area have been carried out to assess the suitability of these carbons as absorbents in the water and wastewater. For anionic dyes (reactive, direct, acid a close relationship between the surface area and surface chemical groups of the modified activated carbon and percentage of dye removal by adsorption can be observed. Cationic dyes large amount of surface chemical groups present in the sample (mainly carboxylic, anhydrides, lactones and phenols etc. are good anchoring sites for adsorption. The present study reveals the recovery of valuable adsorbents from readily and cheaply available agriculture wastes.

Status of defense radioactive waste disposal activities

International Nuclear Information System (INIS)

Wade, T.W.

1988-01-01

The Office of Defense Programs, U.S. Department of Energy, is responsible for the production of nuclear weapons and materials for national defense. As a byproduct to their activities, nuclear production facilities have generated, and will continue to generate, certain radioactive, hazardous, or mixed wastes that must be managed and disposed of in a safe and cost-effective manner. Compliance with all applicable Federal and State regulations is required. This paper describes the principal elements that comprise Defense Programs' approach to waste management and disposal. The status of high-level, transuranic, and low-level radioactive waste disposal is set forth. Defense Programs' activities in connection with the environmental restoration of inactive facilities and with the safe transport of waste materials are summarized. Finally, the principal challenges to realizing the goals set for the defense waste program are discussed in terms of regulatory, public acceptance, technical, and budget issues

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

Science.gov (United States)

HAZWRAP, The Hazardous Waste Remedial Actions Program.

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

Chemical Composition Analysis of INEEL Phase 3 Glasses: Task Technical and QA Plan

International Nuclear Information System (INIS)

Peeler, D.

2000-01-01

For about four decades radioactive wastes have been collected and calcined from nuclear fuels reprocessing at the Idaho Chemical Processing Plant (ICPP). Over this time span, secondary radioactive waste from decontamination, laboratory activities and fuels storage activities have also been collected and stored as liquid. These liquid high-activity wastes (HAW) are collectively called Sodium Bearing Wastes (SBW). Currently about 5.7 million liters of these wastes are temporarily stored in stainless steel tanks at the Idaho National Engineering and Environmental Laboratory (INEEL). Vitrification is being considered as a treatment option for SBW. The resulting glass can be sent to either the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, as remote handled transuranic waste (RH-TRU) or to the federal geologic repository for final disposal. In addition to the SBW, roughly 4,000 m3 of calcined high-level wastes (HLW) are currently being stored at INEEL in stainless steel bin sets. These calcined HLW may also be vitrified, either with or without a dissolution and separation process, and sent to the federal geologic repository for final disposal

Technology development activities supporting tank waste remediation

International Nuclear Information System (INIS)

Bonner, W.F.; Beeman, G.H.

1994-06-01

This document summarizes work being conducted under the U.S. Department of Energy's Office of Technology Development (EM-50) in support of the Tank Waste Remediation System (TWRS) Program. The specific work activities are organized by the following categories: safety, characterization, retrieval, barriers, pretreatment, low-level waste, and high-level waste. In most cases, the activities presented here were identified as supporting tank remediation by EM-50 integrated program or integrated demonstration lead staff and the selections were further refined by contractor staff. Data sheets were prepared from DOE-HQ guidance to the field issued in September 1993. Activities were included if a significant portion of the work described provides technology potentially needed by TWRS; consequently, not all parts of each description necessarily support tank remediation

Radioecological activity limits for radioactive waste disposal

International Nuclear Information System (INIS)

Ahmet, E. Osmanlioglu

2006-01-01

Full text: Near surface disposal is an option used by many countries for the disposal of radioactive waste containing mainly short lived radionuclides. Near surface disposal term includes broad range of facilities from simple trenches to concrete vaults. Principally, disposal of radioactive waste requires the implementation of measures that will provide safety for human health and environment now and in the future. For this reason preliminary activity limits should be determined to avoid radioecological problems. Radioactive waste has to be safely disposed in a regulated manner, consistent with internationally agreed principles and standards and with national legislations to avoid serious radioecological problems. The purpose of this study, presents a safety assessment approach to derive operational and post-closure radioecological activity limits for the disposal of radioactive waste. Disposal system has three components; the waste, the facility (incl. engineered barriers) and the site (natural barriers). Form of the waste (unconditioned or conditioned) is effective at the beginning of the migration scenerio. Existence of the engineered barriers in the facility will provide long term isolation of the waste from environment. The site characteristics (geology, groundwater, seismicity, climate etc.) are important for the safety of the system. Occupational exposure of a worker shall be controlled so that the following dose limits are not exceeded: an effective dose of 20mSv/y averaged over 5 consecutive years; and an effective dose of 50mSv in any single year. The effective dose limit for members of the public recommended by ICRP and IAEA is 1 mSv/y for exposures from all man-made sources [1,2]. Dose constraints are typically a fraction of the dose limit and ICRP recommendations (0.3 mSv/y) could be applied [3,4]. Radioecological activity concentration limits of each radionuclide in the waste (Bq/kg) were calculated. As a result of this study radioecological activity

Low and medium activity solid wastes processing and encapsulation

International Nuclear Information System (INIS)

Taillard, D.; Claes, J.; Hennart, D.

1983-01-01

This work, carried out under contract with the European Atomic Energy Community, describes the techniques in use for waste management. The activity of low and medium activity solid wastes is from few curies to few tens of curies per cubic meter, they are produced by nuclear facilities and are often complex mixtures. Radioactive wastes are characterized and processing and conditioning are described. Leaching, stability, mechanical resistance and radiolysis of encapsulated wastes are examined. Handling, storage and disposal are treated

Aube very low activity waste storage Centre. Annual report 2009

International Nuclear Information System (INIS)

2010-01-01

After a presentation of the ANDRA (the French national agency for radioactive waste management), its role and missions, its sites, its strategy with respect to a sustainable development, this report contains a description of waste storage installations and key figures of the activity in 2009 (origin and nature of very low activity wastes, brief description of the Aube centre installations, stored volumes, performed works). It describes arrangements related to security, safety and radioprotection, presents results of the radiological survey activity performed in the environment and on wastes, and activities related to public information

Quarterly Briefing Book on Environmental and Waste Management Activities

Energy Technology Data Exchange (ETDEWEB)

Brown, M.C.

1991-06-01

The purpose of the Quarterly Briefing Book on Environmental and Waste Management Activities is to provide managers and senior staff at the US Department of Energy-Richland Operations Office and its contractors with timely and concise information on Hanford Site environmental and waste management activities. Each edition updates the information on the topics in the previous edition, deletes those determined not to be of current interest, and adds new topics to keep up to date with changing environmental and waste management requirements and issues. Section A covers current waste management and environmental restoration issues. In Section B are writeups on national or site-wide environmental and waste management topics. Section C has writeups on program- and waste-specific environmental and waste management topics. Section D provides information on waste sites and inventories on the site. 15 figs., 4 tabs.

Quarterly Briefing Book on Environmental and Waste Management Activities

International Nuclear Information System (INIS)

Brown, M.C.

1991-06-01

The purpose of the Quarterly Briefing Book on Environmental and Waste Management Activities is to provide managers and senior staff at the US Department of Energy-Richland Operations Office and its contractors with timely and concise information on Hanford Site environmental and waste management activities. Each edition updates the information on the topics in the previous edition, deletes those determined not to be of current interest, and adds new topics to keep up to date with changing environmental and waste management requirements and issues. Section A covers current waste management and environmental restoration issues. In Section B are writeups on national or site-wide environmental and waste management topics. Section C has writeups on program- and waste-specific environmental and waste management topics. Section D provides information on waste sites and inventories on the site. 15 figs., 4 tabs

Activity monitoring of alpha-bearing wastes

International Nuclear Information System (INIS)

Birkhoff, G.; Bondar, L.

1980-01-01

The paper aims at the survey on the actual situation in activity monitoring of alpha-bearing wastes. Homogeneous materials such as liquid-, gaseous- and homogeneous solid wastes are amenable to destructive analyses of representative samples. Available destructive analyses methods are sensitive and precise enough to cope with all requirements in alpha-waste monitoring. The more difficult problems are encountered with alpha-contaminated solids, when representative sampling is not practicable. Non-destructive analysis techniques are applied for monitoring this category of solid wastes. The techniques for nondestructive analysis of alpha-bearing wastes are based on the detection of gamma and/or neutron-emission of actinides. Principles and a theory of non-destructive radiometric assay of plutonium contaminated solid waste streams are explained. Guidelines for the calibration of instruments and interpretation of experimental data are given. Current theoretical and experimental development work in this problem area is reviewed. Evaluations concerning capabilities and limitations of monitoring systems for alpha-bearing solid wastes are very complex and out of the scope of this paper

Activities of the IAEA in the area of radioactive waste management

International Nuclear Information System (INIS)

Efremenkov, V.M.

1998-01-01

The IAEA activity in the area of radioactive waste management mainly concentrates on three areas, namely: (i) the establishing of international principles and standards for the safe management of radioactive waste; (ii) to promote the development and improvements of waste processing technologies, including handling, treatment, conditioning, packaging, storage and disposal of waste; and (iii) assisting developing Member States in establishing good waste management practice through dissemination of technical information, providing technical support and training. These activities are carried out by the Waste Technology Section, Department of Nuclear Energy, and the Waste Safety Section, Department of Nuclear Safety. The Waste Technology Section's activities are organized into four subprogrammes covering: the handling, processing and storage of radioactive waste; radioactive waste disposal; technology and management aspects of decontamination, decommissioning and environmental restoration; and waste management information and support services

Carbon-14 in sludge

International Nuclear Information System (INIS)

Fowler, J.R.; Coleman, C.J.

1983-01-01

The level of C-14 in high-level waste is needed to establish the amount of C-14 that will be released to the environment either as off-gas from the Defense Waste Processing Facility (DWPF) or as a component of saltstone. Available experimental data confirmed a low level of C-14 in soluble waste, but no data was available for sludge. Based on the processes used in each area, Purex LAW sludge in F-area and HM HAW sludge in H-area will contain the bulk of any sludge produced by the cladding. Accordingly, samples from Tank 8F containing Purex LAW and Tank 15H containing HM HAW were obtained and analyzed for C-14. These two waste types constitute approximately 70% of the total sludge inventory now stored in the waste tanks. Results from analyses of these two sludge types show: the total C-14 inventory in sludge now stored in the waste tanks is 6.8 Ci; C-14 releases to the atmosphere from the DWPF will average approximately 0.6 Ci annually at the projected sludge processing rate in the DWPF. 4 references, 2 tables

Disposal of high-activity nuclear wastes

International Nuclear Information System (INIS)

Hamilton, E.I.

1983-01-01

A discussion is presented on the deep sea ocean disposal for high-activity nuclear wastes. The following topics are covered: effect of ionizing radiation on marine ecosystems; pathways by which radionuclides are transferred to man from the marine environment; information about releases of radioactivity to the sea; radiological protection; storage and disposal of radioactive wastes and information needs. (U.K.)

Radioactive waste characterisation by neutron activation

International Nuclear Information System (INIS)

Nicol, Tangi

2016-01-01

Nuclear activities produce radioactive wastes classified following their radioactive level and decay time. an accurate characterization is necessary for efficient classification and management. Medium and high level wastes containing long lived radioactive isotopes will be stored in deep geological storage for hundreds of thousands years. at the end of this period, it is essential to ensure that the wastes do not represent any risk for humans and environment, not only from radioactive point of view, but also from stable toxic chemicals. This PhD thesis concerns the characterization of toxic chemicals and nuclear material in radioactive waste, by using neutron activation analysis, in the frame of collaboration between the Nuclear Measurement Laboratory of CEA Cadarache, France, and the Institute of Nuclear Waste Management and Reactor Safety of the research center, FZJ (Forschungszentrum Juelich GmbH), Germany. The first study is about the validation of the numerical model of the neutron activation cell MEDINA (FZJ), using MCNP Monte Carlo transport code. Simulations and measurements of prompt capture gamma rays from small samples measured in MEDINA have been compared for a number of elements of interest (beryllium, aluminum, chlorine, copper, selenium, strontium, and tantalum). The comparison was performed using different nuclear databases, resulting in satisfactory agreement and validating simulation in view of following studies. Then, the feasibility of fission delayed gamma-ray measurements of "2"3"9Pu and "2"3"5U in 225 L waste drums has been studied, considering bituminized or concrete matrixes representative of wastes produced in France and Germany. The delayed gamma emission yields were first determined from uranium and plutonium metallic samples measurements in REGAIN, the neutron activation cell of LMN, showing satisfactory consistency with published data. The useful delayed gamma signals of "2"3"9Pu and "2"3"5U, homogeneously distributed in the 225 L

Characterization plan for the immobilized low-activity waste borehole

International Nuclear Information System (INIS)

Reidel, S.P.; Reynolds, K.D.

1998-03-01

The US Department of Energy's (DOE's) Hanford Site has the most diverse and largest amounts of radioactive tank waste in the US. High-level radioactive waste has been stored at Hanford in large underground tanks since 1944. Approximately 209,000 m 3 (54 Mgal) of waste are currently stored in 177 tanks. Vitrification and onsite disposal of low activity tank waste (LAW) are embodied in the strategy described in the Tri-Party Agreement. The tank waste is to be retrieved, separated into low- and high-level fractions, and then immobilized by private vendors. The DOE will receive the vitrified waste from private vendors and dispose of the low-activity fraction in the Hanford Site 200 East Area. The Immobilized Low-Activity Waste Disposal Complex (ILAWDC) is part of the disposal complex. This report is a plan to drill the first characterization borehole and collect data at the ILAWDC. This plan updates and revises the deep borehole portion of the characterization plan for the ILAWDC by Reidel and others (1995). It describes data collection activities for determining the physical and chemical properties of the vadose zone and the saturated zone at and in the immediate vicinity of the proposed ILAWDC. These properties then will be used to develop a conceptual geohydrologic model of the ILAWDC site in support of the Hanford ILAW Performance Assessment

Distinguishing method for contamination/radio-activation of radioactive wastes

International Nuclear Information System (INIS)

Fukazawa, Takuji; Kato, Keiichiro; Koda, Satoshi.

1994-01-01

The present invention concerns a method of distinguishing the contamination/radio-activation of radioactive wastes used in processing wastes generated upon dismantling of exhausted nuclear reactors. Especially, contaminated/radio-activation is distinguished for wastes having openings such as pipes and valves, by utilizing scattering of γ-rays or γ-ray to β-ray ratio. That is, ratio of scattered γ-rays and direct γ-rays or ratio of β-rays and γ-rays from radioactive wastes are measured and compared by a radiation detector, to distinguish whether the radioactive wastes contaminated materials or radio-activated materials. For example, when an object to be measured having an opening is contaminated at the inner side, the radiation detector facing to the opening mainly detects high direct γ-rays emitted from the object to be measured while a radiation detector not facing the opening mainly detects high scattered γ-rays relatively. On the other hand, when the object is a radio-activated material, any of the detectors detect scattered γ-rays, so that they can be distinguished by these ratios. (I.S.)

Neutron Activation analysis of waste water

International Nuclear Information System (INIS)

Hernandez H, V.

1997-01-01

An instrumental neutron activation analysis for the simultaneous determination of chlorine, bromine, sodium, manganese, cobalt, copper, chromium, zinc, nickel, antimony and iron in waste water is described. They were determined in waste water samples under normal conditions by non-destructive neutron activation simultaneously using a suitable monostandard method. Standardized water samples were used and irradiated in polyethylene ampoules at a neutron flux of 10 13 cm -2 s -1 for periods of 1 minute, 1 and 10 hours. A Ge hyperpure detector was used for your activity determination, with count times of 60, 180, 300 and 600 seconds. The obtained results show than the method can be utilized for the determination of this elements without realize anything previous treatment of the samples. (Author)

15 years return transport of vitrified high-level waste from France. The long way from La Hague to Gorleben

International Nuclear Information System (INIS)

Horn, Thomas

2012-01-01

The operators of German nuclear power plants have contracts since 1977 with the French company AREVA NC (former COGEMA) and since 1980 with the British company NDA (former BNFL) for reprocessing of spent nuclear fuel. Since July 2005 the delivery of irradiated fuel element into a reprocessing plant is prohibited. Until 2005 fuel elements with about 6.080 tSM were shipped abroad, about 5.309 tSM to France. The contribution deals with the history of the transports from La Hague to Gorleben, including the contamination problems in 1988 that caused restrictions by the German authorities. A catalogue of safety requirements had to be fulfilled for the allowance of further return transports. The development of appropriate transport casks to cope with changing heat generation of the high-level waste is described. During the complete transport cycle extensive radiological measurements were performed. By the end of 2011 the HAW (high-level waste) glass coquilles were completely returned to Gorleben.

Logistics worldwide for the whole nuclear cycle. Nuclear Cargo + Service GmbH

International Nuclear Information System (INIS)

Geiger, Horst; Schymke, Klaus

2011-01-01

Nuclear Cargo + Service GmbH (NCS) offers logistics worldwide for the whole nuclear cycle to fuel manufacturers, reactor operators, and waste management companies. Transport equipment and interim stores are part of the company's facilities. The firm's Front End unit conducts transnational transports of yellow cake, uranium hexafluoride, and enriched uranium and uranium from reprocessing. In the Back End unit, the company performs worldwide transports of spent fuel elements of research reactors. Another key area of activity is shipment of radioactive waste ranging from low-level waste to HAW (highly active waste generating heat). In its Component Disposal area, NCS offers a variety of transport services up to and including large components, e.g. reactor pressure vessels, both on the road and by rail and ship. NCS operates storage halls of its own for storing radioactive materials including radioactive waste. The technical equipment of NCS comprises a large pool of road and rail transport vehicles as well as a great number of vessels for radioactive materials. (orig.)

Prebiotic Potential of Agave angustifolia Haw Fructans with Different Degrees of Polymerization

Directory of Open Access Journals (Sweden)

José Rodolfo Velázquez-Martínez

2014-08-01

Full Text Available Inulin-type fructans are the most studied prebiotic compounds because of their broad range of health benefits. In particular, plants of the Agave genus are rich in fructans. Agave-derived fructans have a branched structure with both β-(2→1 and β-(2→6 linked fructosyl chains attached to the sucrose start unit with a degree of polymerization (DP of up to 80 fructose units. The objective of this work was to assess the prebiotic potential of three Agave angustifolia Haw fructan fractions (AFF with different degrees of polymerization. The three fructan fractions were extracted from the agave stem by lixiviation and then purified by ultrafiltration and ion exchange chromatography: AFF1, AFF2 and AFF3 with high (3–60 fructose units, medium (2–40 and low (2–22 DP, respectively. The fructan profile was determined with high-performance anion exchange chromatography with pulsed amperometric detection (HPAEC-PAD, which confirmed a branched fructan structure. Structural elucidation was performed by Fourier Transform Infra-Red Spectroscopy. The AFF spectrum shows characteristic fructan bands. The prebiotic effect of these fractions was assessed in vitro through fermentation by Bifidobacterium and Lactobacillus strains. Four growth patterns were observed. Some bacteria did not grow with any of the AFF, while other strains grew with only AFF3. Some bacteria grew according to the molecular weight of the AFF and some grew indistinctly with the three fructan fractions.

Wastes from selected activities in two light-water reactor fuel cycles

International Nuclear Information System (INIS)

Palmer, C.R.; Hill, O.F.

1980-07-01

This report presents projected volumes and radioactivities of wastes from the production of electrical energy using light-water reactors (LWR). The projections are based upon data developed for a recent environmental impact statement in which the transuranic wastes (i.e., those wastes containing certain long-lived alpha emitters at concentrations of at least 370 becquerels, or 10 nCi, per gram of waste) from fuel cycle activities were characterized. In addition, since the WG.7 assumed that all fuel cycle wastes except mill tailings are placed in a mined geologic repository, the nontransuranic wastes from several activities are included in the projections reported. The LWR fuel cycles considered are the LWR, once-through fuel cycle (Strategy 1), in which spent fuel is packaged in metal canisters and then isolated in geologic formations; and the LWR U/Pu recycle fuel cycle (Strategy 2), wherein spent fuel is reprocessed for recovery and recycle of uranium and plutonium in LWRs. The wastes projected for the two LWR fuel cycles are summarized. The reactor operations and decommissioning were found to dominate the rate of waste generation in each cycle. These activities account for at least 85% of the fuel cycle waste volume (not including head-end wastes) when normalized to per unit electrical energy generated. At 10 years out of reactor, however, spent fuel elements in Strategy 1 represent 98% of the fuel cycle activity but only 4% of the volume. Similarly, the packaged high-level waste, fuel hulls and hardware in Strategy 2 concentrate greater than 95% of the activity in 2% of the waste volume

Anaerobic bioleaching of metals from waste activated sludge

KAUST Repository

Meulepas, Roel J W

2015-05-01

Heavy metal contamination of anaerobically digested waste activated sludge hampers its reuse as fertilizer or soil conditioner. Conventional methods to leach metals require aeration or the addition of leaching agents. This paper investigates whether metals can be leached from waste activated sludge during the first, acidifying stage of two-stage anaerobic digestion without the supply of leaching agents. These leaching experiments were done with waste activated sludge from the Hoek van Holland municipal wastewater treatment plant (The Netherlands), which contained 342μgg-1 of copper, 487μgg-1 of lead, 793μgg-1 of zinc, 27μgg-1 of nickel and 2.3μgg-1 of cadmium. During the anaerobic acidification of 3gdry weightL-1 waste activated sludge, 80-85% of the copper, 66-69% of the lead, 87% of the zinc, 94-99% of the nickel and 73-83% of the cadmium were leached. The first stage of two-stage anaerobic digestion can thus be optimized as an anaerobic bioleaching process and produce a treated sludge (i.e., digestate) that meets the land-use standards in The Netherlands for copper, zinc, nickel and cadmium, but not for lead.

Activation and characterization of waste coffee grounds as bio-sorbent

Science.gov (United States)

Mariana; Marwan; Mulana, F.; Yunardi; Ismail, T. A.; Hafdiansyah, M. F.

2018-03-01

As the city well known for its culture of coffee drinkers, modern and traditional coffee shops are found everywhere in Banda Aceh, Indonesia. High number of coffee shops in the city generates large quantities of spent coffee grounds as waste without any effort to convert them as other valuable products. In an attempt to reduce environmental problems caused by used coffee grounds, this research was conducted to utilize waste coffee grounds as an activated carbon bio-sorbent. The specific purpose of this research is to improve the performance of coffee grounds bio-sorbent through chemical and physical activation, and to characterize the produced bio-sorbent. Following physical activation by carbonization, a chemical activation was achieved by soaking the carbonized waste coffee grounds in HCl solvent and carbonization process. The activated bio-sorbent was characterized for its morphological properties using Scanning Electron Microscopy (SEM), its functional groups by Fourier Transform Infra-Red Spectrophotometer (FTIR), and its material characteristics using X-Ray Diffraction (XRD). Characterization of the activated carbon prepared from waste coffee grounds shows that it meets standard quality requirement in accordance with Indonesian National Standard, SNI 06-3730-1995. Activation process has modified the functional groups of the waste coffee grounds. Comparing to natural waste coffee grounds, the resulted bio-sorbent demonstrated a more porous surface morphology following activation process. Consequently, such bio-sorbent is a potential source to be used as an adsorbent for various applications.

Problems with the disposal of run-out high-activity fission product solution in the Hot Cells of Karlsruhe Nuclear Research Center

International Nuclear Information System (INIS)

Schreibmaier, J.

1979-05-01

During decanting of 50 l high-level radioactive waste (120 Ci/l) from a transport container about 1 l HAW leaked to the floor of the transfer chamber. The causes for the incident and the removal of the consequences are described. The costs incurred and the losses resulting from the cell facility not having been used are said to amount to 6-8 million DM. Decontamination and repair work took more than 18 months, sometimes more than 80 persons were occupied. The radiation exposure of all persons involved amounted to 80 man-rem. (HP) [de

R ampersand D activities at DOE applicable to mixed waste

International Nuclear Information System (INIS)

Erickson, M.D.; Devgun, J.S.; Brown, J.J.; Beskid, N.J.

1991-01-01

The Department of Energy (DOE) has established the Office of Environmental Restoration and Waste Management. Within the new organization, the Office of Technology Development (OTD) is responsible for research, development, demonstration, testing and evaluation (RDDT ampersand E) activities aimed at meeting DOE cleanup goals, while minimizing cost and risk. Because of US governmental activities dating back to the Manhattan project, mixed radioactive and hazardous waste is an area of particular concern to DOE. The OTD is responsible for a number of R ampersand D activities aimed at improving capabilities to characterize, control, and properly dispose of mixed waste. These activities and their progress to date will be reviewed. In addition, needs for additional R ampersand D on managing mixed waste will be presented. 5 refs., 2 tabs

Phase 2B experimental design for the INEEL glass composition variation study

International Nuclear Information System (INIS)

Peeler, D.

2000-01-01

The U.S. Department of Energy's (DOE's) Offices of Science and Technology (through the Tanks Focus Area [TFA]) and Waste Management are sponsoring a partnership among Idaho National Engineering and Environmental Laboratory (INEEL), Pacific Northwest National Laboratory (PNNL), and the Savannah River Technology Center (SRTC) for a collaborative glass composition variation study (CVS). The purpose of the CVS is to investigate property - composition relationships within a glass-composition region compatible with the expected range of Idaho Nuclear Technology and Engineering Center (INTEC) high-activity wastes (HAWs). The CVS has been conducted in phases to allow INEEL, PNNL, and SRTC researchers to adjust the glass composition region of interest as flowsheet options are refined and/or waste-stream compositions become more defined

Anaerobic bioleaching of metals from waste activated sludge

International Nuclear Information System (INIS)

Meulepas, Roel J.W.; Gonzalez-Gil, Graciela; Teshager, Fitfety Melese; Witharana, Ayoma; Saikaly, Pascal E.; Lens, Piet N.L.

2015-01-01

Heavy metal contamination of anaerobically digested waste activated sludge hampers its reuse as fertilizer or soil conditioner. Conventional methods to leach metals require aeration or the addition of leaching agents. This paper investigates whether metals can be leached from waste activated sludge during the first, acidifying stage of two-stage anaerobic digestion without the supply of leaching agents. These leaching experiments were done with waste activated sludge from the Hoek van Holland municipal wastewater treatment plant (The Netherlands), which contained 342 μg g −1 of copper, 487 μg g −1 of lead, 793 μg g −1 of zinc, 27 μg g −1 of nickel and 2.3 μg g −1 of cadmium. During the anaerobic acidification of 3 g dry weight L −1 waste activated sludge, 80–85% of the copper, 66–69% of the lead, 87% of the zinc, 94–99% of the nickel and 73–83% of the cadmium were leached. The first stage of two-stage anaerobic digestion can thus be optimized as an anaerobic bioleaching process and produce a treated sludge (i.e., digestate) that meets the land-use standards in The Netherlands for copper, zinc, nickel and cadmium, but not for lead. - Highlights: • Heavy metals were leached during anaerobic acidification of waste activated sludge. • The process does not require the addition of chelating or oxidizing agents. • The metal leaching efficiencies (66 to 99%) were comparable to chemical leaching. • The produced leachate may be used for metal recovery and biogas production. • The produced digested sludge may be used as soil conditioner

Waste management activities and carbon emissions in Africa

International Nuclear Information System (INIS)

Couth, R.; Trois, C.

2011-01-01

This paper summarizes research into waste management activities and carbon emissions from territories in sub-Saharan Africa with the main objective of quantifying emission reductions (ERs) that can be gained through viable improvements to waste management in Africa. It demonstrates that data on waste and carbon emissions is poor and generally inadequate for prediction models. The paper shows that the amount of waste produced and its composition are linked to national Gross Domestic Product (GDP). Waste production per person is around half that in developed countries with a mean around 230 kg/hd/yr. Sub-Saharan territories produce waste with a biogenic carbon content of around 56% (+/-25%), which is approximately 40% greater than developed countries. This waste is disposed in uncontrolled dumps that produce large amounts of methane gas. Greenhouse gas (GHG) emissions from waste will rise with increasing urbanization and can only be controlled through funding mechanisms from developed countries.

International Symposium on Disposal of Low Activity Radioactive Waste, Cordoba, Spain, 13-17 December 2004

CERN Document Server

2004-01-01

The topical issues addressed by the symposium were: policies and strategies for low activity radioactive waste; very low activity radioactive waste; low activity radioactive waste from decommissioning; long lived low activity radioactive waste and other materials; and unique low activity radioactive waste.

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

Science.gov (United States)

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

2006-11-01

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

Leaching of gold from a mechanically and mechanochemically activated waste

Directory of Open Access Journals (Sweden)

Jana Ficeriová

2010-03-01

Full Text Available The intensification of leaching of gold from a waste using mechanical activation (milling in water and mechanochemical activation(milling in thiourea solution were studied as the pretreatment steps. The leaching of “as-received“ sample in an acid thiourea solutionresulted in 78 % Au dissolution, after mechanical activation 98 % and mechanochemical activation up to 99 % of the gold was leachedduring 120 min. The mechanochemical activation resulted in an increase of the specific surface area of the waste from 0.6 m2g-1to a maximum value of 20.5 m2g-1. The activation was performed in an attritor using variable milling times. The physico-chemical changesin the waste as a consequence of mechanochemical activation had a pronounced influence on the subsequent gold extraction.

Learning the ABCs: Activity based costing in waste operations

International Nuclear Information System (INIS)

Zocher, Marc A.

1992-01-01

The United States Department of Energy (DOE) is facing a challenging new national role based on current world events, changing public perception and awareness, and a legacy of wastes generated in the past. Clearly, the DOE must put mechanisms in place to comply with environmental rules, regulations, and good management practices so that public health risk is minimized while programmatic costs are controlled. DOE has begun this process and has developed a Five-Year Plan to describe the activities necessary to comply with both cleanup, or environmental restoration, and waste management of existing waste streams. The focus of this paper is how to best manage the treatment, storage, disposal, and transportation of waste throughout the DOE weapons complex by using Activity Based Costing (ABC) to both plan and control expenditures in DOE Waste Management (WM). The basics of ABC, along with an example, will be detailed. (author)

Anaerobic bioleaching of metals from waste activated sludge

Energy Technology Data Exchange (ETDEWEB)

Meulepas, Roel J.W., E-mail: roel.meulepas@wetsus.nl [UNESCO-IHE, Westvest 7, 2611 AX Delft (Netherlands); Gonzalez-Gil, Graciela [UNESCO-IHE, Westvest 7, 2611 AX Delft (Netherlands); King Abdullah University of Science and Technology, Water Desalination and Reuse Center, Thuwal 13955-69000 (Saudi Arabia); Teshager, Fitfety Melese; Witharana, Ayoma [UNESCO-IHE, Westvest 7, 2611 AX Delft (Netherlands); Saikaly, Pascal E. [King Abdullah University of Science and Technology, Water Desalination and Reuse Center, Thuwal 13955-69000 (Saudi Arabia); Lens, Piet N.L. [UNESCO-IHE, Westvest 7, 2611 AX Delft (Netherlands)

2015-05-01

Heavy metal contamination of anaerobically digested waste activated sludge hampers its reuse as fertilizer or soil conditioner. Conventional methods to leach metals require aeration or the addition of leaching agents. This paper investigates whether metals can be leached from waste activated sludge during the first, acidifying stage of two-stage anaerobic digestion without the supply of leaching agents. These leaching experiments were done with waste activated sludge from the Hoek van Holland municipal wastewater treatment plant (The Netherlands), which contained 342 μg g{sup −1} of copper, 487 μg g{sup −1} of lead, 793 μg g{sup −1} of zinc, 27 μg g{sup −1} of nickel and 2.3 μg g{sup −1} of cadmium. During the anaerobic acidification of 3 g{sub dry} {sub weight} L{sup −1} waste activated sludge, 80–85% of the copper, 66–69% of the lead, 87% of the zinc, 94–99% of the nickel and 73–83% of the cadmium were leached. The first stage of two-stage anaerobic digestion can thus be optimized as an anaerobic bioleaching process and produce a treated sludge (i.e., digestate) that meets the land-use standards in The Netherlands for copper, zinc, nickel and cadmium, but not for lead. - Highlights: • Heavy metals were leached during anaerobic acidification of waste activated sludge. • The process does not require the addition of chelating or oxidizing agents. • The metal leaching efficiencies (66 to 99%) were comparable to chemical leaching. • The produced leachate may be used for metal recovery and biogas production. • The produced digested sludge may be used as soil conditioner.

Gravitational sedimentation of flocculated waste activated sludge.

Science.gov (United States)

Chu, C P; Lee, D J; Tay, J H

2003-01-01

The sedimentation characteristics of flocculated wastewater sludge have not been satisfactorily explored using the non-destructive techniques, partially owing to the rather low solid content (ca. 1-2%) commonly noted in the biological sediments. This paper investigated, for the first time, the spatial-temporal gravitational settling characteristics of original and polyelectrolyte flocculated waste activated sludge using Computerized Axial Tomography Scanner. The waste activated sludge possessed a distinct settling characteristic from the kaolin slurries. The waste activated sludges settled more slowly and reached a lower solid fraction in the final sediment than the latter. Flocculation markedly enhanced the settleability of both sludges. Although the maximum achievable solid contents for the kaolin slurries were reduced, flocculation had little effects on the activated sludge. The purely plastic rheological model by Buscall and White (J Chem Soc Faraday Trans 1(83) (1987) 873) interpreted the consolidating sediment data, while the purely elastic model by Tiller and Leu (J. Chin. Inst. Chem. Eng. 11 (1980) 61) described the final equilibrated sediment. Flocculation produced lower yield stress during transient settling, thereby resulting in the more easily consolidated sludge than the original sample. Meanwhile, the flocculated activated sludge was stiffer in the final sediment than in the original sample. The data reported herein are valuable to the theories development for clarifier design and operation.

Reportable Nuclide Criteria for ORNL Radioactive Waste Management Activities - 13005

International Nuclear Information System (INIS)

McDowell, Kip; Forrester, Tim; Saunders, Mark

2013-01-01

The U.S. Department of Energy's Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee generates numerous radioactive waste streams. Many of those streams contain a large number of radionuclides with an extremely broad range of concentrations. To feasibly manage the radionuclide information, ORNL developed reportable nuclide criteria to distinguish between those nuclides in a waste stream that require waste tracking versus those nuclides of such minimal activity that do not require tracking. The criteria include tracking thresholds drawn from ORNL onsite management requirements, transportation requirements, and relevant treatment and disposal facility acceptance criteria. As a management practice, ORNL maintains waste tracking on a nuclide in a specific waste stream if it exceeds any of the reportable nuclide criteria. Nuclides in a specific waste stream that screen out as non-reportable under all these criteria may be dropped from ORNL waste tracking. The benefit of these criteria is to ensure that nuclides in a waste stream with activities which meaningfully affect safety and compliance are tracked, while documenting the basis for removing certain isotopes from further consideration. (authors)

Dispersão zoocórica e hidrocórica marítima de Opuntia monacantha (Willd. Haw. (Cactaceae

Directory of Open Access Journals (Sweden)

Maurício Lenzi

2011-12-01

Full Text Available http://dx.doi.org/10.5007/2175-7925.2012v25n1p47 Adaptações evolutivas na morfologia e fisiologia das cactáceas têm sido associadas aos seus mecanismos de dispersão e colonização. Os mecanismos e modos de dispersão de Opuntia monacantha (Willd. Haw. (Cactaceae foram caracterizados em duas praias de Florianópolis, SC, Brasil. Um marsupial do gênero Didelphis (Mammalia: Didelphidae foi o único frugívoro e, portanto, dispersor de frutos, apresentando locais específicos para alimentação. A hidrocoria marítima ocorreu após a invasão marinha sobre a vegetação de restinga, caracterizando-se pela dispersão de cladódios e frutos em várias épocas do ano. Descreve-se pela primeira vez a ação do mar como potencial dispersor para uma espécie de cactos.

Effect of phosphate solubilizing bacteria on the growth of Agave angustifolia Haw (Maguey Espadin)

International Nuclear Information System (INIS)

Cruz, A.B.; Gutierrez, G.M.

2015-01-01

Experiments were conducted to evaluate the potential effects of phosphate solubilizing bacteria (PSB) on the growth of maguey espadin (Agave angustifolia Haw.). A total of nine strains of PSB, previously isolated in the maguey rhizosphere and identified as PSBVa, PSBVb, PSBVf, PSBHa, PSBHc, PSBHd, PSBMg, PSBMh and PSBMi were tested on maguey plants grown in phosphorus-deficient sterilized and unsterilized soils of three sites where maguey is grown (valley, hill and mountain) under greenhouse conditions. Aerial dry weight and the total weight of maguey plants inoculated with PSBMh in unsterile mountain soil increased by 12.14% and 10.99% respectively, compared with the uninoculated control. Total root dry weight increased by 17.85% with PSBMh in sterile mountain soils and by 11.64% with PSBMg in unsterile mountain soils, with respect to the uninoculated sterile and unsterile control respectively. Plant stem diameter increased by 13.61% with PSBVb in unsterile valley soil, compared to the uninoculated control. Root length was 56.84% higher with PSBMi in unsterile mountain soils than the uninoculated control. Plant leaf number increased by 35% with PSBHd in unsterile hill soil, with respect to the uninoculated control. In all treatments, the available phosphorus at harvest was higher than pre-planting levels. This study suggests that isolated PSBMh, PSBMg and PSBMi are the most efficient biofertilizers for maguey espadin cultivation. (author)

Fluidized bed steam reformed mineral waste form performance testing to support Hanford Supplemental Low Activity Waste Immobilization Technology Selection

Energy Technology Data Exchange (ETDEWEB)

Jantzen, C. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Pierce, E. M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bannochie, C. J. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Burket, P. R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Cozzi, A. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Crawford, C. L. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Daniel, W. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Fox, K. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Herman, C. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Miller, D. H. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Missimer, D. M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nash, C. A. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Williams, M. F. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Brown, C. F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Qafoku, N. P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Neeway, J. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Valenta, M. M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gill, G. A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Swanberg, D. J. [Washington River Protection Solutions (WRPS), Richland, WA (United States); Robbins, R. A. [Washington River Protection Solutions (WRPS), Richland, WA (United States); Thompson, L. E. [Washington River Protection Solutions (WRPS), Richland, WA (United States)

2015-10-01

This report describes the benchscale testing with simulant and radioactive Hanford Tank Blends, mineral product characterization and testing, and monolith testing and characterization. These projects were funded by DOE EM-31 Technology Development & Deployment (TDD) Program Technical Task Plan WP-5.2.1-2010-001 and are entitled “Fluidized Bed Steam Reformer Low-Level Waste Form Qualification”, Inter-Entity Work Order (IEWO) M0SRV00054 with Washington River Protection Solutions (WRPS) entitled “Fluidized Bed Steam Reforming Treatability Studies Using Savannah River Site (SRS) Low Activity Waste and Hanford Low Activity Waste Tank Samples”, and IEWO M0SRV00080, “Fluidized Bed Steam Reforming Waste Form Qualification Testing Using SRS Low Activity Waste and Hanford Low Activity Waste Tank Samples”. This was a multi-organizational program that included Savannah River National Laboratory (SRNL), THOR® Treatment Technologies (TTT), Pacific Northwest National Laboratory (PNNL), Oak Ridge National Laboratory (ORNL), Office of River Protection (ORP), and Washington River Protection Solutions (WRPS). The SRNL testing of the non-radioactive pilot-scale Fluidized Bed Steam Reformer (FBSR) products made by TTT, subsequent SRNL monolith formulation and testing and studies of these products, and SRNL Waste Treatment Plant Secondary Waste (WTP-SW) radioactive campaign were funded by DOE Advanced Remediation Technologies (ART) Phase 2 Project in connection with a Work-For-Others (WFO) between SRNL and TTT.

CRNL active waste incinerator

International Nuclear Information System (INIS)

McQuade, D.W.

1965-02-01

At CRNL the daily collection of 1200 pounds of active combustible waste is burned in a refractory lined multi-chamber incinerator. Capacity is 500-550 pounds per hour; volume reduction 96%. Combustion gases are cooled by air dilution and decontaminated by filtration through glass bags in a baghouse dust collector. This report includes a description of the incinerator plant, its operation, construction and operating costs, and recommendations for future designs. (author)

Activation of waste brewer's yeast Saccharomyces cerevisiae for bread production

OpenAIRE

Popov Stevan D.; Dodić Siniša N.; Mastilović Jasna S.; Dodić Jelena M.; Popov-Raljić Jovanka V.

2005-01-01

The waste brewer's yeast S. cerevisiae (activated and non-activated) was compared with the commercial baker's yeast regarding the volume of developed gas in dough, volume and freshness stability of produced bread. The activation of waste brewer's yeast resulted in the increased volume of developed gas in dough by 100% compared to non-activated brewer's yeast, and the obtained bread is of more stable freshness compared to bread produced with baker's yeast. The activation of BY affects positive...

Waste production and regional growth of marine activities an econometric model.

Science.gov (United States)

Bramati, Maria Caterina

2016-11-15

Coastal regions are characterized by intense human activity and climatic pressures, often intensified by competing interests in the use of marine waters. To assess the effect of public spending on the regional economy, an econometric model is here proposed. Not only are the regional investment and the climatic risks included in the model, but also variables related to the anthropogenic pressure, such as population, economic activities and waste production. Feedback effects of economic and demographic expansion on the pollution of coastal areas are also considered. It is found that dangerous waste increases with growing shipping and transportation activities and with growing population density in non-touristic coastal areas. On the other hand, the amount of non-dangerous wastes increases with marine mining, defense and offshore energy production activities. However, lower waste production occurs in areas where aquaculture and touristic industry are more exploited, and accompanied by increasing regional investment in waste disposal. Copyright © 2016 Elsevier Ltd. All rights reserved.

Hanford Immobilized Low-Activity Waste Product Acceptance Test Plan

International Nuclear Information System (INIS)

Peeler, D.

1999-01-01

'The Hanford Site has been used to produce nuclear materials for the U.S. Department of Energy (DOE) and its predecessors. A large inventory of radioactive and mixed waste, largely generated during Pu production, exists in 177 underground single- and double-shell tanks. These wastes are to be retrieved and separated into low-activity waste (LAW) and high-level waste (HLW) fractions. The DOE is proceeding with an approach to privatize the treatment and immobilization of Handord''s LAW and HLW.'

Underground disposal of high active waste

International Nuclear Information System (INIS)

Engelmann, H.J.

1982-01-01

This paper is concerned with the engineering aspects relating to the deep burial of high active waste in stable geological formations. The design of a repository depends upon a number of factors not least of which is the type of rock in which it is to be constructed. High level wastes must be isolated from man's environment for such periods that subsequent release will not result in an unacceptable hazard to human population. Design aspects of repositories are reviewed and conceptual design are present in relation to the geological formations under consideration. Over long time periods the most probable mode of release of radionuclides is through groundwater contacting the waste. The proposed concepts therefore include the use of engineered and natural barriers to delay the eventual release of waterborne radionuclides into mans environment. In all cases the ultimate barrier will be the geological formation. Nevertheless, depending upon the type of host rock, use will be made of various additional engineered barriers to delay water contacting the high level waste for several hundreds of years. During this time the level of radiation and associated heat emitted by the waste, will fall by several orders of magnitude and the rock temperatures within a repository will be returning to ambient. Thereafter the residual activity will mainly arise from the actinides. Containment may be enhanced by surrounding the canisters with materials having high sorption capabilities for many of the radionuclides involved. The depth at which a repository is excavated must be sufficient to ensure that the overburden will withstand changes in environmental conditions. The depth of cover required in different rock types may vary. In clay excavating at depth of up to -250 m appears feasible, while in hard rocks and salts working at depth of up to -1000 m is entirely practicable. (orig./RW)

Co-conditioning and dewatering of chemical sludge and waste activated sludge.

Science.gov (United States)

Chang, G R; Liu, J C; Lee, D J

2001-03-01

The conditioning and dewatering behaviors of chemical and waste activated sludges from a tannery were studied. Capillary suction time (CST), specific resistance to filtration (SRF), and bound water content were used to evaluate the sludge dewatering behaviors. Zeta potentials were also measured. Experiments were conducted on each sludge conditioned and dewatered separately, and on the sludge mixed at various ratios. Results indicate that the chemical sludge was relatively difficult to be dewatered, even in the presence of polyelectrolyte. When the waste activated sludge was mixed with the chemical sludge at ratios of 1:1 and 2:1, respectively, the dewaterability of chemical sludge improved remarkably while the relatively better dewaterability of the waste activated sludge deteriorated only to a limited extent. As the mixing ratios became 4:1 and 8:1, the dewaterability of the mixed sludge was equal to that of the waste activated sludge. The optimal polyelectrolyte dosage for the mixed sludge was equal to or less than that of the waste activated sludge. It is proposed that the chemical sludges act as skeleton builders that reduce the compressibility of the mixed sludge whose dewaterability is enhanced. Bound water contents of sludge decreased at low polyelectrolyte dosage and were not significantly affected as polyelectrolyte dosage increased. Advantages and disadvantages of co-conditioning and dewatering chemical sludge and waste activated sludge were discussed.

Activity measurements at a waste volume reduction facility

International Nuclear Information System (INIS)

Richardson, J.; Lee, D.A.

1979-01-01

The monitoring program for Ontario Hydro's radioactive waste management site will be described, several aspects of which will be discussed in detail. The program at this facility includes categorization, volume reduction processing, and storage of solid radioactive wastes from nuclear generating stations of the CANDU type. At the present time, two types of volume reduction process are in operation - incineration and compaction. Following categorization and processing, wastes are stored in in-ground concrete trenches or tile-holes, or in above-ground quadricells. The monitoring program is divided into three areas: public safety, worker safety, and structural integrity. Development projects with respect to the monitoring program have been undertaken to achieve activity accounting for the total waste management program. In particular, a field measurement for the radioactivity content of radioactive ash containers and compacted waste drums

Hanford Immobilized Low-Activity Waste Product Acceptance Test Plan

Energy Technology Data Exchange (ETDEWEB)

Peeler, D.

1999-06-22

'The Hanford Site has been used to produce nuclear materials for the U.S. Department of Energy (DOE) and its predecessors. A large inventory of radioactive and mixed waste, largely generated during Pu production, exists in 177 underground single- and double-shell tanks. These wastes are to be retrieved and separated into low-activity waste (LAW) and high-level waste (HLW) fractions. The DOE is proceeding with an approach to privatize the treatment and immobilization of Handord''s LAW and HLW.'

Regulation of Federal radioactive waste activities. Report to Congress on extending the Nuclear Regulatory Commission's licensing or regulatory authority to Federal radioactive waste storage and disposal activities

International Nuclear Information System (INIS)

1979-09-01

The report contains two recommendations for extending the Commission's regulatory authority: (1) NRC licensing authority should be extended to cover all new DOE facilities for disposal of transuranic (TRU) waste and nondefense low-level waste. (2) A pilot program, focused on a few specific DOE waste management activities, should be established to test the feasibility of extending NRC regulatory authority on a consultative basis to DOE waste management activities not now covered by NRC's licensing authority or its extension as recommended in Recommendation 1

Development of acceptance specifications for low-activity waste from the Hanford tanks

International Nuclear Information System (INIS)

Cunnane, J.C.; Kier, P.H.; Brown, N.R.

1997-01-01

Low-activity products will be in the form of soldified waste and optional matrix and filler materials enclosed in sealed metal boxes. Acceptance specifications limit the physical characteristics of the containers, the chemical and physical characteristics of the waste form and other materials that may be in the container, the waste loading, and the radionuclide leaching characteristics of the waste form. The specifications are designed to ensure that low-activity waste products will be compatible with the driving regulatory and operational requirements and with existing production technologies

Processing method and processing device for liquid waste containing surface active agent and radioactive material

International Nuclear Information System (INIS)

Nishi, Takashi; Matsuda, Masami; Baba, Tsutomu; Yoshikawa, Ryozo; Yukita, Atsushi.

1998-01-01

Washing liquid wastes containing surface active agents and radioactive materials are sent to a deaerating vessel. Ozone is blown into the deaerating vessel. The washing liquid wastes dissolved with ozone are introduced to a UV ray irradiation vessel. UV rays are irradiated to the washing liquid wastes, and hydroxy radicals generated by photodecomposition of dissolved ozone oxidatively decompose surface active agents contained in the washing liquid wastes. The washing liquid wastes discharged from the UV ray irradiation vessel are sent to an activated carbon mixing vessel and mixed with powdery activated carbon. The surface active agents not decomposed in the UV ray irradiation vessel are adsorbed to the activated carbon. Then, the activated carbon and washing liquid wastes are separated by an activated carbon separating/drying device. Radioactive materials (iron oxide and the like) contained in the washing liquid wastes are mostly granular, and they are separated and removed from the washing liquid wastes in the activated carbon separating/drying device. (I.N.)

Decision for counting condition of radioactive waste activities measuring by Ludlum detector

International Nuclear Information System (INIS)

Bambang-Purwanto

2000-01-01

Radioactive waste must measured for activities before be throw out to environment. Measuring will be important in ordered to know activities can be given management direction. For activities radioactive waste on limit threshold value must processed, but for under limit threshold value activities can be throw out to environment. Activities measuring for solid radioactive waste and liquid by (Total, β, γ) Ludlum detector connected Mode-1000 Scaler Counting. Before measuring for solid waste activities was decisioned optimally counting condition, and be obtained are : sample weight 3.5 gram, heating temperature of 125 o C and heating time at 60 minutes. Activities measuring result by total detector ranges from (0.68-0.71) 10 -1 μCi/gram, β detector ranges from (0.24-0.25) 10 -1 μCi/gram and γ detector ranges from (0.35-0.37) μCi/gram

Active and passive computed tomography mixed waste focus area final report

International Nuclear Information System (INIS)

Becker, G K; Camp, D C; Decman, D J; Jackson, J A; Martz, H E; Roberson, G P.

1998-01-01

The Mixed Waste Focus Area (MWFA) Characterization Development Strategy delineates an approach to resolve technology deficiencies associated with the characterization of mixed wastes. The intent of this strategy is to ensure the availability of technologies to support the Department of Energy s (DOE) mixed-waste, low-level or transuranic (TRU) contaminated waste characterization management needs. To this end the MWFA has defined and coordinated characterization development programs to ensure that data and test results necessary to evaluate the utility of non-destructive assay technologies are available to meet site contact handled waste management schedules. Requirements used as technology development project benchmarks are based in the National TRU Program Quality Assurance Program Plan. These requirements include the ability to determine total bias and total measurement uncertainty. These parameters must be completely evaluated for waste types to be processed through a given nondestructive waste assay system constituting the foundation of activities undertaken in technology development projects. Once development and testing activities have been completed, Innovative Technology Summary Reports are generated to provide results and conclusions to support EM-30, -40, or -60 end user or customer technology selection. The active and passive computed tomography non-destructive assay system is one of the technologies selected for development by the MWFA. Lawrence Livermore National Laboratory (LLNL) has developed the active and passive computed tomography (A ampersand XT) nondestructive assay (NDA) technology to identify and accurately quantify all detectable radioisotopes in closed containers of waste. This technology will be applicable to all types of waste regardless of their classification-low level, transuranic or mixed. Mixed waste contains radioactivity and hazardous organic species. The scope of our technology is to develop a non-invasive waste-drum scanner that

Long-term management of wastes resulting from dismantling operations. Storing the very low-level activity wastes at Morvilliers

International Nuclear Information System (INIS)

Duret, F.; Dutzer, M.; Beranger, V.; Lecoq, P.

2003-01-01

Extension of dismantling operations in France in the years to come poses the question of availability of long-term waste facility. Large amount of such wastes will be produced after progressive shutdown of the 58 pressurized water reactors now in operation, not before 2010. However, France is already confronted with dismantling of 9 power reactors (6 of which of gas cooled graphite type), the first reprocessing plant at Marcoule, as well as, dismantling of other installations, for instance the CEA reactors or laboratories. The systems of processing the dismantling waste are not different from those used for wastes resulting from nuclear operations. For the high-level or long-term intermediate level activity disposal the debates must start by 2006, as based on the results of the research conducted according to different provisions of the December 30, 1991 law. These wastes represent however small amounts from the dismantling (around 2000 t for the 9 reactors at shutdown) and they will be stored until a decision will be made. A specific storing system should be implemented by 2008-2010 for the graphite wastes (around 23,000 t) which contain significant amount of long-lived radioelements, although their gross activity is low. But the most significant amount will come from low-level or intermediate-level of short lifetime or from wastes of very low activity. The first category is stored at Storage Center at Aube (CSA), its capacity being of 1,000,000 m 3 of drums. The total volume stored by the end of 2002 amounted 136,500 m 3 with an annual delivering of 12-15,000 m 3 at design rate of 30,000 m 3 /y. This center will be able to absorb the flux increase resulting from dismantling of the decommissioned nuclear installations (around 50,000 t from the dismantling of the 9 power reactor). The Center at Aube can be also adapted for storing wastes of large sizes as for instance the lid of the reactor vessel. According to the French regulation, the wastes produced within a

Activation analyses updating the ITER radioactive waste assessment

International Nuclear Information System (INIS)

Pampin, R.; Zheng, S.; Lilley, S.; Na, B.C.; Loughlin, M.J.; Taylor, N.P.

2012-01-01

Highlights: ► Comprehensive updated of ITER radwaste assessment. ► Latest coupled neutronics and activation methods. ► Type A waste at shutdown decays to TFA within 100 years. ► Most type B waste at shutdown is still type B after 100 years. - Abstract: A study is reported which computes the radiation transport and activation response throughout the ITER machine and updates the ITER radioactive waste assessment using modern 3D models and up-to-date methods. The latest information on component design, maintenance, replacement schedules and materials is adopted. The radwaste classification is revised for all the major components of ITER, as well as several representative port plugs. Results include categorisation snapshots at different decay times, time histories of radiological quantities throughout the machine, and guidelines on interim decay times for components. All plasma-facing materials except tungsten are found to classify as type B due to the transmutation of their main constituents. Major contributors to the IRAS index of all materials are reported. Elemental concentration limits for type A classification of first wall and divertor materials are obtained; for the steels, only a reduction in service lifetime can reduce the waste class. Comparison of total waste amounts with earlier assessments is limited by the fact that analyses of some components are still preliminary; the trend, however, indicates a potential reduction in the total amount of waste if component segregation is demonstrated.

Volume reduction through incineration of low-activity radioactive wastes

International Nuclear Information System (INIS)

Eymeri, J.; Gauthey, J.C.; Chaise, D.; Lafite, G.

1993-01-01

The aim of the waste treatment plant, designed by Technicatome (CEA) for an Indonesian Nuclear Research Center, is to reduce through incineration the volume of low-activity radioactive wastes such as technological solids (cotton, PVC, paper board), biological solids (animal bones) and liquids (cutting fluids...). The complete combustion is realized with a total air multi-fuel burner (liquid wastes) and flash pyrolysis-complete combustion (solid wastes). A two stage flue gas filtration system, a flue gas washing system, and an ash recovery system are used. A test platform has been built. 3 figs

Activated Carbon from the Chinese Herbal Medicine Waste by H3PO4 Activation

Directory of Open Access Journals (Sweden)

Tie Mi

2015-01-01

Full Text Available Large amounts of Chinese herbal medicine wastes produced by the medicinal factories have been mainly landfilled as waste. In this study, via phosphoric acid activation, a Chinese herbal medicine waste from Magnolia officinalis (CHMW-MO was prepared for activated carbon (CHMW-MO-AC. The effect of preparation conditions (phosphoric acid/CHMW-MO impregnation ratio, activation temperature, and time of activated carbon on yield of CHMW-MO-AC was investigated. The surface area and porous texture of the CHMW-MO-ACs were characterized by nitrogen adsorption at 77 K. The SBET and pore volume were achieved in their highest value of 920 m2/g and 0.703 cm3/g, respectively. Thermal gravity analysis and scanning electron microscope images showed that CHMW-MO-ACs have a high thermal resistance and pore development. The results indicated that CHMW-MO is a good precursor material for preparing activated carbon, and CHMW-MO-AC with well-developed mesopore volume can be prepared by H3PO4 activation.

Progress report of the ECN contribution to the experiments in the HAW project

International Nuclear Information System (INIS)

Duijves, K.A.; Vonka, V.

1991-08-01

This report documents the progress of the ECN contribution in the High Active Waste Experiment, a large-scale in-situ test being performed underground in the Asse salt mine, Remlingen, FRG, during the period January 1st through March 31st, 1991. (A.S.). 3 refs.; 10 figs

Radioactivity evaluation method for pre-packed concrete packages of low-level dry active wastes

International Nuclear Information System (INIS)

Sakai, Toshiaki; Funahashi, Tetsuo; Watabe, Kiyomi; Ozawa, Yukitoshi; Kashiwagi, Makoto

1998-01-01

Low-level dry active wastes of nuclear power plants are grouted with cement mortal in a container and planned to disposed into the shallow land disposal site. The characteristics of radionuclides contained in dry active wastes are same as homogeneous solidified wastes. In the previous report, we reported the applicability of the radioactivity evaluation methods established for homogeneous solidified wastes to pre-packed concrete packages. This report outlines the developed radioactivity evaluation methods for pre-packed concrete packages based upon recent data. Since the characteristics of dry active wastes depend upon the plant system in which dry active wastes originate and the types of contamination, sampling of wastes and activity measurement were executed to derive scaling factors. The radioactivity measurement methods were also verified. The applicability of non-destructive methods to measure radioactivity concentration of pre-packed concrete packages was examined by computer simulation. It is concluded that those methods are accurate enough to measure actual waste packages. (author)

Design requirements document for project W-520, immobilized low-activity waste disposal

International Nuclear Information System (INIS)

Ashworth, S.C.

1998-01-01

This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity

Design requirements document for project W-520, immobilized low-activity waste disposal

Energy Technology Data Exchange (ETDEWEB)

Ashworth, S.C.

1998-08-06

This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity.

Transportation research activities in support of nuclear waste management programs

International Nuclear Information System (INIS)

Allen, G.C. Jr.; Cashwell, J.W.; Jefferson, R.M.

1983-01-01

Transportation Technology Center has been conducting a wide range of technical research activities to assure the ability to transport radioactive materials in a safe, reliable manner. These activities include tasks in basic, analysis methodology and system research areas. Recently, the requirements of defense waste shipments have served as a focal point for development tasks with the expectation that they would serve as a precursor for commercial activities. The passage of the Nuclear Waste Policy Act has placed additional responsibility on the Department of Energy for concerns involving the shipments of civilian materials. The development of additional research responsibilities is expected to proceed concurrently with the evolution of the transportation mission plan for civilian spent fuel and high-level wastes

Sizing and melting development activities using noncontaminated metal at the Waste Experimental Reduction Facility

International Nuclear Information System (INIS)

Larsen, M.M.; Logan, J.A.

1984-05-01

EG and G Idaho, Inc., has established the Waste Experimental Reduction Facility (WERF) at the Idaho National Engineering Laboratory (INEL) to develop the capability to reduce the volume that low-level beta/gamma wastes occupy at the disposal site. The work effort at WERF includes a waste sizing development activity (WSDA), a waste melting development activity (WMDA), and a waste incineration development activity (WIDA). This report describes work and developments to date in the WSDA and WMDA with noncontaminated metallic waste in preparation for operations at WERF involving beta/gamma-contaminated metal

Active waste disposal monitoring at the Radioactive Waste Management Complex, Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Hubbell, J.M.

1990-10-01

This report describes an active waste disposal monitoring system proposed to be installed beneath the low-level radioactive disposal site at the Radioactive Waste Management Complex (RWMC), Idaho National Engineering Laboratory, Idaho. The monitoring instruments will be installed while the waste is being disposed. Instruments will be located adjacent to and immediately beneath the disposal area within the unsaturated zone to provide early warning of contaminant movement before contaminants reach the Snake River Plain Aquifer. This study determined the optimum sampling techniques using existing monitoring equipment. Monitoring devices were chosen that provide long-term data for moisture content, movement of gamma-emitting nuclides, and gas concentrations in the waste. The devices will allow leachate collection, pore-water collection, collection of gasses, and access for drilling through and beneath the waste at a later time. The optimum monitoring design includes gas sampling devices above, within, and below the waste. Samples will be collected for methane, tritium, carbon dioxide, oxygen, and volatile organic compounds. Access tubes will be utilized to define the redistribution of radionuclides within, above, and below the waste over time and to define moisture content changes within the waste using spectral and neutron logging, respectively. Tracers will be placed within the cover material and within waste containers to estimate transport times by conservative chemical tracers. Monitoring the vadose zone below, within, and adjacent to waste while it is being buried is a viable monitoring option. 12 refs., 16 figs., 1 tab

Radioactive waste from non-licensed activities - identification of waste, compilation of principles and guidance, and proposed system for final management

International Nuclear Information System (INIS)

Jones, C.; Pers, K.

2001-07-01

Presently national guidelines for the handling of radioactive waste from non-licensed activities are lacking in Sweden. Results and information presented in this report are intended to form a part of the basis for decisions on further work within the Swedish Radiation Protection Institute on regulations or other guidelines on final management and final disposal of this type of waste. An inventory of radioactive waste from non-licensed activities is presented in the report. In addition, existing rules and principles used in Sweden - and internationally - on the handling of radioactive and toxic waste and non-radioactive material are summarized. Based on these rules and principles a system is suggested for the final management of radioactive material from non-licensed activities. A model is shown for the estimation of dose as a consequence of leaching of radio-nuclides from different deposits. The model is applied on different types of waste, e.g. peat ashes, light concrete and low-level waste from a nuclear installation

Low activation material design methodology for reduction of radio-active wastes of nuclear power plant

International Nuclear Information System (INIS)

Hasegawa, A.; Satou, M.; Nogami, S.; Kakinuma, N.; Kinno, M.; Hayashi, K.

2007-01-01

Most of the concrete shielding walls and pipes around a reactor pressure vessel of a light water reactor become low level radioactive waste at decommission phase because they contain radioactive nuclides by thermal-neutron irradiation during its operation. The radioactivity of some low level radioactive wastes is close to the clearance level. It is very desirable in terms of life cycle cost reduction that the radioactivity of those low level radioactive wastes is decreased below clearance level. In case of light water reactors, however, methodology of low activation design of a nuclear plant has not been established yet because the reactor is a large-scale facility and has various structural materials. The Objectives of this work are to develop low activation material design methodology and material fabrication for reduction of radio-active wastes of nuclear power plant such as reinforced concrete. To realize fabrication of reduced radioactive concrete, it is necessary to develop (1) the database of the chemical composition of raw materials to select low activation materials, (2) the tool for calculation of the neutron flux and the spectrum distribution of nuclear plants to evaluate radioactivity of reactor components, (3) optimization of material process conditions to produce the low activation cement and the low activation steels. Results of the data base development, calculation tools and trial production of low activation cements will be presented. (authors)

226Ra adsorption on active coals from waste waters

International Nuclear Information System (INIS)

Panturu, E.; Georgescu, D.P.; Serban, N.; Filip, D.; Radulescu, R.

2000-01-01

During the mining and extraction of uranium, the principle means of protection measurement is to prevent uranium and its products diffusing into the environment. The main carriers of radioactive elements in the environment are air and water. Therefore, reduction of the pollution at a uranium mine can be achieved by the treatment of waste waters contaminated with 226 Ra Radium contaminated waste waters represent a major biological risk. This paper presents the results of the study of the sorption of 226 Ra on active coal mechanisme and the influence of the physical and chemical characteristics of fluid. The 226 Ra removal from the residue pond water at the uranium ore processing plant was studied using eight types of indigenous active coals. The experimental results for each type of active coal and their effect on removal of 226 Ra from waste waters are presented in this paper. (author)

Chromium removal from water by activated carbon developed from waste rubber tires.

Science.gov (United States)

Gupta, Vinod Kumar; Ali, Imran; Saleh, Tawfik A; Siddiqui, M N; Agarwal, Shilpi

2013-03-01

Because of the continuous production of large amount of waste tires, the disposal of waste tires represents a major environmental issue throughout the world. This paper reports the utilization of waste tires (hard-to-dispose waste) as a precursor in the production of activated carbons (pollution-cleaning adsorbent). In the preparation of activated carbon (AC), waste rubber tire (WRT) was thermally treated and activated. The tire-derived activated carbon was characterized by means of scanning electron microscope, energy-dispersive X-ray spectroscopy, FTIR spectrophotometer, and X-ray diffraction. In the IR spectrum, a number of bands centred at about 3409, 2350, 1710, 1650, and 1300-1000 cm(-1) prove the present of hydroxyl and carboxyl groups on the surface of AC in addition to C═C double bonds. The developed AC was tested and evaluated as potential adsorbent removal of chromium (III). Experimental parameters, such as contact time, initial concentration, adsorbent dosage and pH were optimized. A rapid uptake of chromium ions was observed and the equilibrium is achieved in 1 h. It was also found that the adsorption process is pH dependent. This work adds to the global discussion of the cost-effective utilization of waste rubber tires for waste water treatment.

Development plan. High activity-long living wastes project. Abstract

International Nuclear Information System (INIS)

2007-01-01

This brochure presents the actions that the ANDRA (the French national agency of radioactive wastes) has to implement in the framework of the project of high activity-long living (HALL) radioactive wastes (HAVL project) conformably to the requirements of the program defined in the law from June 28, 2006 (law no 2006-739). This law precises the three, complementary, research paths to explore for the management of this type of wastes: separation and transmutation of long-living radioactive elements, reversible disposal in deep geologic underground, and long duration storage. The ANDRA's action concerns the geologic disposal aspect. The following points are presented: the HALL wastes and their containers, the reversible disposal procedure, the HAVL project: financing of researches, storage concepts, development plan of the project (dynamics, information and dialogue approach, input data, main steps, schedule); the nine programs of the HAVL project (laboratory experiments and demonstration tests, surface survey, scientific program, simulation program, surface engineering studies and technological tests, information and communication program, program of environment and facilities surface observation and monitoring, waste packages management, monitoring and transport program, disposal program); the five transverse technical and scientific activities (safety, reversibility, cost, health and occupational safety, impact study). (J.S.)

Radioactive waste packages stored at the Aube facility for low-intermediate activity wastes. A selective and controlled storage

International Nuclear Information System (INIS)

2005-01-01

The waste package is the first barrier designed to protect the man and the environment from the radioactivity contained in wastes. Its design is thus particularly stringent and controlled. This brochure describes the different types of packages for low to intermediate activity wastes like those received and stored at the Aube facility, and also the system implemented by the ANDRA (the French national agency of radioactive wastes) and by waste producers to safely control each step of the design and fabrication of these packages. (J.S.)

Maintenance Plan for the Hanford Immobilized Low-Activity Tank Waste Performance Assessment

International Nuclear Information System (INIS)

MANN, F.M.

2000-01-01

The plan for maintaining the Hanford Immobilized Low-Activity Tank Waste Performance Assessment (PA) is described. The plan includes expected work on PA reviews and revisions, waste reports, monitoring, other operational activities, etc

Scenarios for the Hanford Immobilized Low-Activity Waste (ILAW) performance assessment

International Nuclear Information System (INIS)

MANN, F.M.

1999-01-01

Scenarios describing representative exposure cases associated with the disposal of low activity waste from the Hanford Waste Tanks have been defined. These scenarios are based on guidance from the Department of Energy, the U.S. Nuclear Regulatory Commission, and previous Hanford waste disposal performance assessments

Reconstruction of the isotope activity content of heterogeneous nuclear waste drums.

Science.gov (United States)

Krings, Thomas; Mauerhofer, Eric

2012-07-01

Radioactive waste must be characterized in order to verify its conformance with national regulations for intermediate storage or its disposal. Segmented gamma scanning (SGS) is a most widely applied non-destructive analytical technique for the characterization of radioactive waste drums. The isotope specific activity content is generally calculated assuming a homogeneous matrix and activity distribution for each measured drum segment. However, real radioactive waste drums exhibit non-uniform isotope and density distributions most affecting the reliability and accuracy of activities reconstruction in SGS. The presence of internal shielding structures in the waste drum contributes generally to a strong underestimation of the activity and this in particular for radioactive sources emitting low energy gamma-rays independently of their spatial distribution. In this work we present an improved method to quantify the activity of spatially concentrated gamma-emitting isotopes (point sources or hot spots) in heterogeneous waste drums with internal shielding structures. The isotope activity is reconstructed by numerical simulations and fits of the angular dependent count rate distribution recorded during the drum rotation in SGS using an analytical expression derived from a geometric model. First results of the improved method and enhancements of this method are shown and are compared to each other as well as to the conventional method which assumes a homogeneous matrix and activity distribution. It is shown that the new model improves the accuracy and the reliability of the activity reconstruction in SGS and that the presented algorithm is suitable with respect to the framework requirement of industrial application. Copyright © 2011 Elsevier Ltd. All rights reserved.

Low-activity waste feed delivery -- Minimum duration between successive batches

International Nuclear Information System (INIS)

Peters, B.B.

1998-01-01

The purpose of this study is to develop a defensible basis for establishing what ''minimum duration'' will provide acceptable risk mitigation for low-activity waste feed delivery to the privatization vendors. The study establishes a probabilistic-based duration for staging of low-activity waste feed batches. A comparison is made of the durations with current feed delivery plans and potential privatization vendor facility throughput rates

Low-activity waste feed delivery -- Minimum duration between successive batches

Energy Technology Data Exchange (ETDEWEB)

Peters, B.B.

1998-08-25

The purpose of this study is to develop a defensible basis for establishing what ``minimum duration`` will provide acceptable risk mitigation for low-activity waste feed delivery to the privatization vendors. The study establishes a probabilistic-based duration for staging of low-activity waste feed batches. A comparison is made of the durations with current feed delivery plans and potential privatization vendor facility throughput rates.

Transportation research activities in support of nuclear waste management programs

International Nuclear Information System (INIS)

Allen, G.C.; Luna, R.E.; Jefferson, R.M.; Wowak, W.E.

1983-01-01

The Transportation Technology Center has been conducting a wide range of technical and non-technical research activities to assure the ability to transport radioactive materials in a safe, reliable, and publicly acceptable manner. These activities include tasks in Information and Intergovernmental issues, Safety Assessment and Environmental Analysis and Technology Development. Until recently, the requirements of defense waste shipments have served as a focal point for development tasks with the expectation that they would serve as a precursor for commercial activities. The passage of the Nuclear Waste Policy Act has placed additional responsibility on DOE for concerns involving the shipments of civilian materials. The development of additional research responsibilities is expected to proceed concurrently with the evolution of the transportation mission plan for civilian spent fuel and high-level wastes

Potential low-level waste disposal limits for activation products from fusion

International Nuclear Information System (INIS)

Kennedy, W.E. Jr.; Peloquin, R.A.

1983-09-01

Hanford Engineering Development Laboratory (HEDL) scientists are involved in studies considering alternative construction materials for the first wall of commercial fusion reactors. To permit a comparison of radioactivity levels, both the level of activation and an acceptable limit for the radionuclides present must be known. Generic material composition guidelines can be developed using the US Nuclear Regulatory Commission (NRC) regulations governing the near-surface disposal of low-level radioactive wastes. These regulations consider wastes defined as containing source, special nuclear, or by-product materials arising from research, industrial, medical, and nuclear fuel-cycle activities. However, not all of the activation products produced in low-level wastes from fusion reactors are considered by the NRC in their regulations. The purpose of this report is to present potential low-level waste-disposal limits for ten radionuclides resulting from fusion reactor operations that are not considered in the NRC low-level waste regulations. These potential limits will be used by HEDL scientists to complete their generic material composition guidelines for the first wall of commercial fusion reactors

Production of activated carbons from waste tyres for low temperature NOx control.

Science.gov (United States)

Al-Rahbi, Amal S; Williams, Paul T

2016-03-01

Waste tyres were pyrolysed in a bench scale reactor and the product chars were chemically activated with alkali chemical agents, KOH, K2CO3, NaOH and Na2CO3 to produce waste tyre derived activated carbons. The activated carbon products were then examined in terms of their ability to adsorb NOx (NO) at low temperature (25°C) from a simulated industrial process flue gas. This study investigates the influence of surface area and porosity of the carbons produced with the different alkali chemical activating agents on NO capture from the simulated flue gas. The influence of varying the chemical activation conditions on the porous texture and corresponding NO removal from the flue gas was studied. The activated carbon sorbents were characterized in relation to BET surface area, micropore and mesopore volumes and chemical composition. The highest NO removal efficiency for the waste tyre derived activated carbons was ∼75% which was obtained with the adsorbent treated with KOH which correlated with both the highest BET surface area and largest micropore volume. In contrast, the waste tyre derived activated carbons prepared using K2CO3, NaOH and Na2CO3 alkali activating agents appeared to have little influence on NO removal from the flue gases. The results suggest problematic waste tyres, have the potential to be converted to activated carbons with NOx removal efficiency comparable with conventionally produced carbons. Copyright © 2016 Elsevier Ltd. All rights reserved.

High activity waste disposal

International Nuclear Information System (INIS)

Gaul, W.C.

1990-01-01

Chem-Nuclear Environmental Services (CNES) has developed a container that is capable of containing high activity waste and can be shipped as a regular DOT Type A shipment. By making the container special form the amount of activity that can be transported in a Type A shipment is greatly enhanced. Special form material presents an extra degree of protection to the environment by requiring the package to be destroyed to get access to the radioactive material and must undergo specific testing requirements, whereas normal form material can allow access to the radioactive material. With the special form container up to 10 caries of radium can be transported in a single package. This paper will describe the considerations that were taken to develop these products

Characterization and application of municipal solid waste incineration (MSWI) bottom ash and waste granite powder in alkali activated slag

NARCIS (Netherlands)

Gao, X.; Yuan, B.; Yu, Q. L.; Brouwers, H. J.H.

2017-01-01

In this paper, the feasibility of using two solid wastes in alkali activated slag composites as construction and building materials is evaluated. One waste is the municipal solid waste incineration (MSWI) bottom ash, and the other one is fine granite powder from aggregate manufacturing. These two

Waste production and regional growth of marine activities an econometric model

International Nuclear Information System (INIS)

Bramati, Maria Caterina

2016-01-01

Coastal regions are characterized by intense human activity and climatic pressures, often intensified by competing interests in the use of marine waters. To assess the effect of public spending on the regional economy, an econometric model is here proposed. Not only are the regional investment and the climatic risks included in the model, but also variables related to the anthropogenic pressure, such as population, economic activities and waste production. Feedback effects of economic and demographic expansion on the pollution of coastal areas are also considered. It is found that dangerous waste increases with growing shipping and transportation activities and with growing population density in non-touristic coastal areas. On the other hand, the amount of non-dangerous wastes increases with marine mining, defense and offshore energy production activities. However, lower waste production occurs in areas where aquaculture and touristic industry are more exploited, and accompanied by increasing regional investment in waste disposal. - Highlights: • We use an econometric model as a tool for assessing the effects of regional policies on the development of economic activities related to the use of the sea and on the impact on the marine environment. • Through scenario simulation we provide strategic guidelines for policy makers and economic planners • The model features feedback effects of economic and demographic expansion on the pollution of coastal areas.

Optimisation of the Management of Higher Activity Waste in the UK - 13537

Energy Technology Data Exchange (ETDEWEB)

Walsh, Ciara; Buckley, Matthew [Nuclear Decommissioning Authority, Building 587, Curie Avenue, Harwell Oxford, Didcot, Oxfordshire, OX11 0RH (United Kingdom)

2013-07-01

The Upstream Optioneering project was created in the Nuclear Decommissioning Authority (UK) to support the development and implementation of significant opportunities to optimise activities across all the phases of the Higher Activity Waste management life cycle (i.e. retrieval, characterisation, conditioning, packaging, storage, transport and disposal). The objective of the Upstream Optioneering project is to work in conjunction with other functions within NDA and the waste producers to identify and deliver solutions to optimise the management of higher activity waste. Historically, optimisation may have occurred on aspects of the waste life cycle (considered here to include retrieval, conditioning, treatment, packaging, interim storage, transport to final end state, which may be geological disposal). By considering the waste life cycle as a whole, critical analysis of assumed constraints may lead to cost savings for the UK Tax Payer. For example, it may be possible to challenge the requirements for packaging wastes for disposal to deliver an optimised waste life cycle. It is likely that the challenges faced in the UK are shared in other countries. It is therefore likely that the opportunities identified may also apply elsewhere, with the potential for sharing information to enable value to be shared. (authors)

Safe management of waste from health-care activities

International Nuclear Information System (INIS)

Pruess, A.; Giroult, E.; Rushbrook, P.

1999-01-01

The waste produced in the course of health-care activities, from contaminated needles to radioactive isotopes, carries a greater potential for causing infection and injury than any other type of waste, and inadequate or inappropriate management is likely to have serious public health consequences and deleterious effects on the environment. This handbook - the result of extensive international consultation and collaboration - provides comprehensive guidance on safe, efficient, and environmentally sound methods for the handling and disposal of health-care wastes. The various categories of waste are clearly defined and the particular hazards that each poses are described. Considerable prominence is given to the careful planning that is essential for the success of waste management; workable means of minimizing waste production are outlined and the role of reuse and recycling of waste is discussed. Most of the text, however, is devoted to the collection, segregation, storage, transport, and disposal of wastes. Details of containers for each category of waste, labelling of waste packages, and storage conditions are provided, and the various technologies for treatment of waste and disposal of final residues are discussed at length. Advice is given on occupational safety for all personnel involved with waste handling, and a separate chapter is devoted to the closely related topic of hospital hygiene and infection control. The handbook pays particular attention to basic processes and technologies that are not only safe but also affordable, sustainable, and culturally appropriate. For health-care settings in which resources are severely limited there is a separate chapter on minimal programmes; this summarizes all the simplest and least costly techniques that can be employed for the safe management of health-care wastes. The guide is aimed at public health managers and policy-makers, hospital managers, environmental health professionals, and all administrators with an

Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

International Nuclear Information System (INIS)

Pickett, W.W.

1997-01-01

This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations

Immobilized low-activity waste interim storage facility, Project W-465 conceptual design report

Energy Technology Data Exchange (ETDEWEB)

Pickett, W.W.

1997-12-30

This report outlines the design and Total Estimated Cost to modify the four unused grout vaults for the remote handling and interim storage of immobilized low-activity waste (ILAW). The grout vault facilities in the 200 East Area of the Hanford Site were constructed in the 1980s to support Tank Waste disposal activities. The facilities were to serve project B-714 which was intended to store grouted low-activity waste. The existing 4 unused grout vaults, with modifications for remote handling capability, will provide sufficient capacity for approximately three years of immobilized low activity waste (ILAW) production from the Tank Waste Remediation System-Privatization Vendors (TWRS-PV). These retrofit modifications to the grout vaults will result in an ILAW interim storage facility (Project W465) that will comply with applicable DOE directives, and state and federal regulations.

Waste management assessment and technical review programme. WATRP. An international peer review service for radioactive waste management activities

International Nuclear Information System (INIS)

1994-09-01

International Atomic Energy Agency provides international peer review services in radioactive waste management to those Member States that have established radioactive waste management programmes. Such services are provided within Waste Management Assessment and Technical Review Programme (WATRP). The main objective of WATRP is to provide international expertise and information on a requested subject in the field of radioactive waste management and to validate that programmes and activities are sound and performing well. Refs, figs and tabs

Considerations for an active and passive scanner to assay nuclear waste drums

International Nuclear Information System (INIS)

Martz, H.E.; Azevedo, S.G.; Roberson, G.P.; Schneberk, D.J.; Koenig, Z.M.; Camp, D.C.

1990-01-01

Radioactive wastes are generated at many DOE laboratories, military facilities, fuel fabrication and enrichment plants, reactors, hospitals, and university research facilities. At all of these sites, wastes must be separated, packaged, categorized, and packed into some sort of container--usually 208-L (55-gal) drums--for shipment to waste-storage sites. Prior to shipment, the containers must be labeled, assayed, and certified; the assay value determines the ultimate disposition of the waste containers. An accurate nondestructive assay (NDA) method would identify all the radioisotopes present and provide a quantitative measurement of their activity in the drum. In this way, waste containers could be routed in the most cost-effective manner and without having to reopen them. Currently, the most common gamma-ray method used to assay nuclear waste drums is segmented gamma-ray scanning (SGS) spectrometer that crudely measures only the amount of 235 U or 239 Pu present in the drum. This method uses a spatially-averaged, integrated, emitted gamma-ray-intensity value. The emitted intensity value is corrected by an assumed constant-attenuation value determined by a spatially-averaged, transmission (or active) measurement. Unfortunately, this typically results in an inaccurate determination of the radioactive activities within a waste drum because this measurement technique is valid only for homogeneous-attenuation or known drum matrices. However, since homogeneous-attenuation matrices are not common and may be unknown, other NDA techniques based on active and Passive CT (A ampersand PCT) are under development. The active measurement (ACT) yields a better attenuation matrix for the drum, while the passive measurement (PCT) more accurately determines the identity of the radioisotopes present and their activities. 9 refs., 2 figs

Characterization of activated carbon produced from urban organic waste

Directory of Open Access Journals (Sweden)

Abdul Gani Haji

2013-10-01

Full Text Available The difficulties to decompose organic waste can be handled naturally by pyrolisis so it can  decomposes quickly that produces charcoal as the product. This study aims to investigate the characteristics of activated carbon from urban organic waste. Charcoal results of pyrolysis of organic waste activated with KOH 1.0 M at a temperature of 700 and 800oC for 60 to 120 minutes. Characteristics of activated carbon were identified by Furrier Transform Infra Red (FTIR, Scanning Electron Microscopy (SEM, and X-Ray Diffraction (XRD. However, their quality is determined yield, moisture content, ash, fly substances, fixed carbon, and the power of adsorption of iodine and benzene. The identified functional groups on activated carbon, such as OH (3448,5-3436,9 cm-1, and C=O (1639,4 cm-1. In general, the degree and distance between the layers of active carbon crystallites produced activation in all treatments showed no significant difference. The pattern of activated carbon surface topography structure shows that the greater the pore formation in accordance with the temperature increase the more activation time needed. The yield of activated carbon obtained ranged from 72.04 to 82.75%. The results of characterization properties of activated carbon was obtained from 1.11 to 5.41% water, 13.68 to 17.27% substance fly, 20.36 to 26.59% ash, and 56.14 to 62.31% of fixed carbon . Absorption of activated carbon was good enough at 800oC and 120 minutes of activation time, that was equal to 409.52 mg/g of iodine and 14.03% of benzene. Activated carbon produced has less good quality, because only the water content and flying substances that meet the standards.Doi: 10.12777/ijse.5.2.89-94 [How to cite this article: Haji, A.G., Pari, G., Nazar, M., and Habibati.  (2013. Characterization of activated carbon produced from urban organic waste . International Journal of Science and Engineering, 5(2,89-94. Doi: 10.12777/ijse.5.2.89-94

Removing radio-active wastes from nuclear power stations by the STEAG system

International Nuclear Information System (INIS)

Baatz, H.

1978-01-01

The mobile STEAG System for conditioning radio-active wastes from nuclear power stations represents a particularly safe and economic method of removing them in present day conditions. Cementation by the FAFNIR System is used for the greater part of the waste, the liquid concentrate (evaporator concentrate and filter slurry). For the special case of the medium active resin balls from the primary circuits, embedding in plastic by the FAMA process has proved to be the only available successful process so far. The highly active solid waste from the reactor core is decomposed by the MOSAIK System, is packed in transportable and storable containers and is removed from the fuel element storage pond. The systems are so safe that faults or interruptions of power station operation due to faults in removing radio-active wastes can be excluded. (orig.) [de

Dissolution test for low-activity waste product acceptance

International Nuclear Information System (INIS)

Ebert, W. L.

1998-01-01

We have measured the mean and standard deviation of the solution concentrations of B, Na, and Si attained in replicate dissolution tests conducted at temperatures of 20, 40, and 70 C, for durations of 3 and 7 days, and at glass/water mass ratios of 1:10 and 1:1. These and other tests were conducted to evaluate the adequacy of the test methods specified in privatization contracts and to develop a data base that can be used to evaluate the reliability of reported results for tests performed on the waste products. Tests were conducted with a glass that we formulated to be similar to low-activity waste products that will be produced during the remediation of Hanford tank wastes. Statistical analyses indicated that, while the mean concentrations of B, Na, and Si were affected by the values of test parameters, the standard deviation of replicate tests was not. The precision of the tests was determined primarily by uncertainties in the analysis of the test solutions. Replicate measurements of other glass properties that must be reported for Hanford low-activity waste products were measured to evaluate the possible adoption of the glass used in these tests as a standard test material for the product acceptance process

Preparation of activated Carbons from extracted waste biomass by chemical activation

International Nuclear Information System (INIS)

Toteva, V.; Nickolov, R.

2013-01-01

Full text: Novel biomass precursors for the production of activated carbons (ACs) were studied. ACs were prepared from extracted coffee husks and extracted spent ground coffee - separately or as mixtures with 10, 20 and 30 mass % Bulgarian lignite coal. Activation by potassium hydroxide was employed for all samples. The results obtained show that the surface and porous parameters of the ACs depend on the nature of the initial materials used. The specific surface areas (BET) and the microporosities of ACs obtained from extracted spent ground coffee mixed with 20 mass % Bulgarian lignite coals, are greater than those of the ACs from extracted coffee husks. It is likely that the reason for this result is the chemical composition of the precursors. The coffee husks have less lignin and more holocellulose. The latter undergoes more significant destructive changes in the process of chemical activation. On the contrary, waste ground coffee precursors contain more lignin and less holocellulose. As a result, after the chemical activation, the carbons prepared from extracted spent ground coffee exhibit better porous parameters and higher specific surface areas. key words: activated carbons, extraction, waste biomass

Analysis of alternatives for immobilized low activity waste disposal

Energy Technology Data Exchange (ETDEWEB)

Burbank, D.A.

1997-10-28

This report presents a study of alternative disposal system architectures and implementation strategies to provide onsite near-surface disposal capacity to receive the immobilized low-activity waste produced by the private vendors. The analysis shows that a flexible unit strategy that provides a suite of design solutions tailored to the characteristics of the immobilized low-activity waste will provide a disposal system that best meets the program goals of reducing the environmental, health, and safety impacts; meeting the schedule milestones; and minimizing the life-cycle cost of the program.

Analysis of alternatives for immobilized low-activity waste disposal

International Nuclear Information System (INIS)

Burbank, D.A.

1997-01-01

This report presents a study of alternative disposal system architectures and implementation strategies to provide onsite near-surface disposal capacity to receive the immobilized low-activity waste produced by the private vendors. The analysis shows that a flexible unit strategy that provides a suite of design solutions tailored to the characteristics of the immobilized low-activity waste will provide a disposal system that best meets the program goals of reducing the environmental, health, and safety impacts; meeting the schedule milestones; and minimizing the life-cycle cost of the program

Incineration of alpha-active solid waste by microwaves

Energy Technology Data Exchange (ETDEWEB)

Mallik, G K; Bhargava, V K; Kamath, H S; Purushotham, D S.C. [Bhabha Atomic Research Centre, Tarapur (India). Advanced Fuel Fabrication Facility

1996-12-31

The conventional techniques for treatment of alpha-active compressible solid waste involve incineration using electrically heated incinerators and subsequent recovery of special nuclear materials (SNM) from the ash by acid leaching. A microwave incineration followed by microwave digestion and SNM recovery from ash has specific advantages from maintenance and productivity consideration. The paper describes a preliminary work carried out with simulated uranium containing compressible solid waste using microwave heating technique. (author). 3 refs., 1 tab.

Waste treatment activities incineration

International Nuclear Information System (INIS)

Weber, D.A.

1985-01-01

The waste management policy at SRP is to minimize waste generation as much as possible and detoxify and/or volume reduce waste materials prior to disposal. Incineration is a process being proposed for detoxification and volume reduction of combustion nonradioactive hazardous, low-level mixed and low-level beta-gamma waste. Present operation of the Solvent Burner Demonstration reduces the amount of solid combustible low-level beta-gamma boxed waste disposed of by shallow land burial by approximately 99,000 ft 3 per year producing 1000 ft 3 per year of ash and, by 1988, will detoxify and volume reduce 150,000 gallons or organic Purex solvent producing approximately 250 ft 3 of ash per year

Bacteriological studies on dairy waste activated sludge

NARCIS (Netherlands)

Adamse, A.D.

1966-01-01

Dairy-waste activated sludge was examined for bacterial composition and response to different conditions. Strains isolated were classified mainly into three groups: predominantly coryneform bacteria (largely Arthrobacter), some Achromobacteraceae and a small groups of Pseudomonadaceae.

Regulation of Federal radioactive waste activities. Summary of report to Congress on extending the Nuclear Regulatory Commission's licensing or regulatory authority to Federal radioactive waste storage and disposal activities

International Nuclear Information System (INIS)

Smith, R.D.

1979-09-01

The NRC Authorization Bill for FY 1979 directed NRC to conduct a study of extending the Commission's licensing or regulatory authority to include categories of existing and future Federal radioactive waste storage and disposal activities not presently subject to such authority. The report includes a complete listing and inventory of all radioactive waste storage and disposal activities now being conducted or planned by Federal agencies. The NRC study has attempted to present a general comparison of the relative hazards associated with defense-generated and commercial wastes. Options for extending Commission authority were developed and analyzed. The implications of NEPA were analyzed in the context of these options. The national security implications of extending NRC's regulatory authority over DOE programs are examined and evaluated. Costs and benefits are identified and assessed. The Commission's recommendations, based on the study, are to extend licensing authority over new DOE disposal activities involving transuranic wastes and non-defense low-level waste and to initiate a pilot program to test the feasibility of NRC playing a consultative role in the evaluation of existing DOE activities

An overview of the AECB's strategy for regulating radioactive waste management activities

International Nuclear Information System (INIS)

Hamel, P.E.; Smythe, W.D.; Duncan, R.M.; Coady, J.R.

1982-07-01

The goal of the Canadian Atomic Energy Control Board in regulating the management of radioactive wastes is to ensure the protection of people and the environment. A program of cooperation with other agencies, identification and adoption of baselines for describing radioactive wastes, development of explicit criteria and requirements, publication of related regulatory documents, establishment of independent consultative processes with technical experts and the public, and maintenance of awareness and compatibility with international activities is underway. Activities related to high-level radioactive waste, uranium mine and mill tailings, low- and medium-level wastes, radioactive effluents from nuclear facilities, and decommissioning and decontamination are described

Alkali activated slag cements using waste glass as alternative activators. Rheological behaviour

Directory of Open Access Journals (Sweden)

Manuel Torres-Carrasco

2015-03-01

The findings show that AAS paste behaviour of rheology when the activator was a commercial waterglass solution or NaOH/Na2CO3 with waste glass was similar, fit the Herschel-Bulkley model. The formation of primary C-S-H gel in both cases were confirmed. However, the rheological behaviour in standard cements fit the Bingham model. The use of the waste glass may be feasible from a rheological point of view in pastes can be used.

Solid radioactive waste: evaluation of residual activity in nuclear medicine services

International Nuclear Information System (INIS)

Alabarse, Frederico G.; Xavier, Ana M.; Magalhaes, Maisa H.; Guerrero, Jesus S.P.

2009-01-01

An experimental programme to estimate, with a better degree of accuracy, the activity that remains adsorbed in flasks and syringes used in Nuclear Medicine Services for the administration of radionuclides to patients submitted to diagnostic or therapy is been conducted under the coordination of the Radioactive Waste Division of the Brazilian Nuclear Energy Commission, CNEN. The adopted recommendation in Brazil to allow an expedite solid waste management in nuclear medicine facilities, up to the present, is to consider that 2% of the initial activity remains adsorbed in the solid waste, which easily allows the calculation of the storage time to achieve regulatory clearance levels by decay. This research evaluates 17 different kinds of radiopharmaceuticals and three radioisotopes: 99m Tc, 67 Ga and 201 Tl. Results obtained by means of a weighting method to estimate the residual mass in flasks show that the ratio of the mass of the liquid that remains in the solid waste to the mass of the empty flask is constant. This suggests that the residual activity depends on the initial activity concentration of radiopharmaceutical contained in each flask, as assumed by the regulatory body. Additionally, results obtained by determining the remaining activity in flasks, shortly after the injection of its radionuclide contents in patients, indicate that an average value for the residual activity of the order of 10% of the initial activity contained in the flasks or syringes should be adopted to determine the decay storage time before the release of solid waste in the urban conventional land fill disposal system. The 'rule of thumb' of 10 half-lives for storage before clearance is also discussed in the present work. (author)

PPARβ/δ regulates glucocorticoid- and sepsis-induced FOXO1 activation and muscle wasting.

Directory of Open Access Journals (Sweden)

Estibaliz Castillero

Full Text Available FOXO1 is involved in glucocorticoid- and sepsis-induced muscle wasting, in part reflecting regulation of atrogin-1 and MuRF1. Mechanisms influencing FOXO1 expression in muscle wasting are poorly understood. We hypothesized that the transcription factor peroxisome proliferator-activated receptor β/δ (PPARβ/δ upregulates muscle FOXO1 expression and activity with a downstream upregulation of atrogin-1 and MuRF1 expression during sepsis and glucocorticoid treatment and that inhibition of PPARβ/δ activity can prevent muscle wasting. We found that activation of PPARβ/δ in cultured myotubes increased FOXO1 activity, atrogin-1 and MuRF1 expression, protein degradation and myotube atrophy. Treatment of myotubes with dexamethasone increased PPARβ/δ expression and activity. Dexamethasone-induced FOXO1 activation and atrogin-1 and MuRF1 expression, protein degradation, and myotube atrophy were inhibited by PPARβ/δ blocker or siRNA. Importantly, muscle wasting induced in rats by dexamethasone or sepsis was prevented by treatment with a PPARβ/δ inhibitor. The present results suggest that PPARβ/δ regulates FOXO1 activation in glucocorticoid- and sepsis-induced muscle wasting and that treatment with a PPARβ/δ inhibitor may ameliorate loss of muscle mass in these conditions.

Performance Enhancements to the Hanford Waste Treatment and Immobilization Plant Low-Activity Waste Vitrification System

International Nuclear Information System (INIS)

Hamel, W. F.; Gerdes, K.; Holton, L. K.; Pegg, I.L.; Bowan, B.W.

2006-01-01

The U.S Department of Energy Office of River Protection (DOE-ORP) is constructing a Waste Treatment and Immobilization Plant (WTP) for the treatment and vitrification of underground tank wastes stored at the Hanford Site in Washington State. The WTP comprises four major facilities: a pretreatment facility to separate the tank waste into high level waste (HLW) and low-activity waste (LAW) process streams, a HLW vitrification facility to immobilize the HLW fraction; a LAW vitrification facility to immobilize the LAW fraction, and an analytical laboratory to support the operations of all four treatment facilities. DOE has established strategic objectives to optimize the performance of the WTP facilities and the LAW and HLW waste forms to reduce the overall schedule and cost for treatment and vitrification of the Hanford tank wastes. This strategy has been implemented by establishing performance expectations in the WTP contract for the facilities and waste forms. In addition, DOE, as owner-operator of the WTP facilities, continues to evaluate 1) the design, to determine the potential for performance above the requirements specified in the WTP contract; and 2) improvements in production of the LAW and HLW waste forms. This paper reports recent progress directed at improving production of the LAW waste form. DOE's initial assessment, which is based on the work reported in this paper, is that the treatment rate of the WTP LAW vitrification facility can be increased by a factor of 2 to 4 with a combination of revised glass formulations, modest increases in melter glass operating temperatures, and a second-generation LAW melter with a larger surface area. Implementing these improvements in the LAW waste immobilization capability can benefit the LAW treatment mission by reducing the cost of waste treatment. (authors)

EPA's approach to the commercial low-activity mixed waste problem

International Nuclear Information System (INIS)

Foutes, C.; Schultheisz, D.; Gruhlke, J.

1999-01-01

The US Environmental Protection Agency is proposing an environmental standard for the disposal of commercial low-activity mixed waste (LAMW), waste characterized by the presence of both hazardous chemicals and very low-level radioactive materials. LAMW is and will be generated in large amounts by environmental restoration efforts, nuclear power production and, in smaller amounts, by medical and educational facilities, industrial activities, and the process of research and development. The dual regulatory nature of this waste (covered by two very different statutes) is currently an impediment to its permanent disposal. The proposed standard addresses this issue by creating a voluntary regulatory option under which LAMW that meets the proposed radionuclide concentration limits may be disposed of via disposal technology based upon the Resource Conservation and Recovery Act (RCRA) hazardous waste disposal requirements. Such a facility would also have to be licensed by the NRC. EPA will explore the attributes of this disposal technology to develop concentration limits that are protective of the public health for LAMW. (author)

Desactivation of liquid radioactive wastes of low and medium activity

International Nuclear Information System (INIS)

Golinski, M.; Charomska, K.

1978-01-01

The results of research made according to the prodranm of scientific and technical cooperation of the CMEA countries are discussed. The main direction of these research works is on future improvement of installations for purification of liquid radioactive wastes by chemical methods of coprecipitation and coagulation, ion exchange, sorption, distillation and electrolysis. It was shown that methods of coprecipitation and coagulation have low efficiency and the activity reduction factor seldom was more than 10. In sorption processes different sorbents, both organic and nonorganic were used. The modified bentonite used as a sorbent agent has shown high selectivity towards zesium ions. Waste concentration by means of distillation is an universal but rather expensive method and is applied mainly in the cases of high salts concentration and high specific activity of liquid wastes. Electrolysis, as a method of the liquid wastes purification is used in the USSR and has high efficiency with low energy consumption. (I.T.) [ru

Removal of phenol from radioactive waste solutions using activated granular Carbon and activated vermiculite

International Nuclear Information System (INIS)

Ezz El-Din, M.R.; Atta, E.R.

2006-01-01

The efficiency of both activated granular carbon (AGC) and activated vermiculite (AV) in removal of phenol from aqueous waste solutions is of great interest. The aim of the present study is to compare the absorbance capacities of both AGC and AV for the removal of phenol from radioactive waste solutions and to identify the factors affecting the sorption process. The experimental results were in the form of batch sorption measurements for the removal of phenol at ambient temperature (29 ± 1 degree C) and for times up to 40 min and 180 min for AGC and AV, respectively. The results indicated that activated carbon has good efficiency to adsorb phenol. Freundlich equation has been fitted to both AGC and AV for the contaminant removal. The adsorption capacities of both AGC and AV to phenol were 17.4 mg g-1 and 4.5 mg g-1, respectively. The maximum desorption percent of phenol from both loaded AGC and loaded AV were 9 % and 0 %, respectively, and it attained within about 200 min. accordingly, it is recommended that activated carbon is preferred in the applied field for removing phenol from radioactive aqueous wastes

ANDRA - National Radioactive Waste Management Agency. Activity report 2015. Financial report 2015

International Nuclear Information System (INIS)

2016-01-01

Created in 1979 within the CEA, the National Radioactive Waste Management Agency (ANDRA) was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act: - a R and D mission to propose safe long-term solution for radioactive waste without current disposal system; this mission includes long-term storage, since the 2006 Planning Act, in order to propose interim solutions while final ones are being studied; - an industrial mission concerning, on one hand, waste acceptance criteria and control and, on the other hand, siting, construction, operation, closure and monitoring of repositories. This mission includes as well a public service mission in terms of i) collection of waste of the 'small-scale nuclear activities' producers or owners (including the so-called 'household' radioactive waste, i.e. waste owned by private individuals) and ii) clean-up and rehabilitation of orphan polluted sites; - an information mission, notably through the regular publication of the National Inventory of radioactive materials and waste. This mission includes as well an active policy of dialogue with stakeholders both at national and local level. This document is the activity and financial report of the Andra for the year 2015

ANDRA - National Radioactive Waste Management Agency. Activity report 2016. Financial report 2016

International Nuclear Information System (INIS)

2017-01-01

Created in 1979 within the CEA, the National Radioactive Waste Management Agency (ANDRA) was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act: - a R and D mission to propose safe long-term solution for radioactive waste without current disposal system; this mission includes long-term storage, since the 2006 Planning Act, in order to propose interim solutions while final ones are being studied; - an industrial mission concerning, on one hand, waste acceptance criteria and control and, on the other hand, siting, construction, operation, closure and monitoring of repositories. This mission includes as well a public service mission in terms of i) collection of waste of the 'small-scale nuclear activities' producers or owners (including the so-called 'household' radioactive waste, i.e. waste owned by private individuals) and ii) clean-up and rehabilitation of orphan polluted sites; - an information mission, notably through the regular publication of the National Inventory of radioactive materials and waste. This mission includes as well an active policy of dialogue with stakeholders both at national and local level. This document is the activity and financial report of the Andra for the year 2016

Final Report for Crucible -Scale Radioactive Vitrification and Product Test of Waste Envelope B (AZ-102) Low-Activity Waste Glass

International Nuclear Information System (INIS)

CRAWFORD, CHARLES

2004-01-01

A proof-of-technology demonstration for the Hanford River Protection Project (RPP) Waste treatment and Immobilization Plant (WTP) was performed by the Savannah River Technology Center (SRTC). As part of this demonstration, treated AZ-102 Low-Activity Waste supernate was vitrified using a crucible-scale furnace. Initial glass samples were quench-cooled and characterized for metals and radionuclides. The glass was also durability tested using the American Society for Testing and Materials (ASTM) Product Consistency Test (PCT) protocol. These tests used the AZ-102 glass formulation Low Activity Waste (LAW) B88 that targeted AZ-102 waste loading at 5 wt% Na2O. After these initial results were obtained with the quench-cooled LAWB88 glass, a prototypical container centerline cooling (CCC) program was supplied to SRTC by WTP. A portion of the quench-cooled LAWB88 glass was remelted and centerline cooled. Samples from the CCC low-activity AZ-102 glass waste form were durability tested using the PCT and characterized for crystalline phase identification.This final report documents the characterization and durability of this AZ-102 glass

Low-Activity Waste Feed Data Quality Objectives

Energy Technology Data Exchange (ETDEWEB)

MJ Truex; KD Wiemers

1998-12-11

This document describes characterization requirements for the Tank Waste Remediation System (TWRS) Waste Disposal Program's privatization efforts in support of low-activity waste (LAW) treatment and immobilization, This revised Data Quality Objective (DQO) replaces earlier documents (PNNL 1997; DOE-W 1998zq Wiemers 1996). Revision O of this DQO was completed to meet Tri-Party Agreement (TPA) target milestone M-60-14-TO1. Revision 1 updates the data requirements based on the contract issued `August 1998 (DOE-RL 1998b). In addition, sections of Revision O pertaining to "environmental planning" were not acceptable to the Washington State Department of Ecology (Ecology) and have been removed. Regulatory compliance for TWRS Privatization is being addressed in a separate DQO (Wiemers et al. 1998). The Project Hanford Management Contract (PHMC) Contractors and the private contractor may elect to complete issue-specific DQOS to accommodate their individual work scope.

Radioprotection and physical surveillance during activities of liquid wastes of high and low activity in italian ITREC plant

International Nuclear Information System (INIS)

Petagna, Edoardo; Tortorelli, Pietro

1997-03-01

Many studies were made in ITREC Plant, located in ENEA - Trisaia Research Center, in the field of the nuclear fuel reprocessing, in the past years. During these activities liquid wastes of high and low activity were yielded and stored in the special area of tanks named Waste-1. In order to condition the low activity liquid wastes, essentially fission products, beta and gamma emitters, was built the SIRTE Plant (Integrate System for the Raise and Effluents Treatment) based on cementation process. In the present work, the radiological monitoring performed within the plant during the first campaign of cementation, is showed

Experiment of Industrial Waste Absorption using Activated Carbon from Coal of Tanjung Tabalong, South Kalimantan

Directory of Open Access Journals (Sweden)

M. Ulum Gani

2014-06-01

Full Text Available DOI: 10.17014/ijog.v6i4.130Activated carbon made from Tanjung Tabalong coal was investigated its absorption capability to organic and inorganic elements in industrial waste. Coal was carbonized at low temperature of 600C to produce semicoke, and then was activated at temperature of 700C with activation time of 120 minutes with water steam flow. The absorption capability of activated carbon to chemical oxygen demand (COD was performed using 2.5 and 9.0 g activated carbon for 250 ml and 300 ml COD waste respectively. The agitation time of each experiment were 30, 60, and 90 minutes. Atomic absorption spectrophotometer (AAS was used to analyze the COD waste. The result shows that 2.5 g activated carbon could absorb COD waste ranging from 6.9-67.5 %, while the utilization of 9 g could absorb COD waste ranging from 88.9 - 100 %. The more activated carbon and the longer time of agitation used in this experiment, the more the absorption of COD waste.

Incineration plant for low active waste at Inshass, LAWI

International Nuclear Information System (INIS)

Krug, W.; Thoene, L.; Schmitz, H.J.; Abdelrazek, I.D.

1993-10-01

The LAWI (Low Active Waste Incinerator) prototype incinerating plant was devised and constructed according to the principle of the Juelich thermoprocess and installed at the Egyptian research centre Inshass. In parallel, AEA Cairo devised and constructed their own operations building for this plant with all the features, infrastructural installations and rooms required for operating the plant and handling and treating low-level radioactive wastes. The dimensions of this incinerator were selected so as to be sufficient for the disposal of solid, weakly radioactive combustible wastes from the Inshass Research Centre and the environment (e.g. Cairo hospitals). (orig./DG) [de

Human health and ecological risks from environmental restoration and waste management activities

International Nuclear Information System (INIS)

Pehlman, P.A.; Wollert, D.A.; Phillippi, R.H.

1994-01-01

This paper summarizes the methodologies for estimating human health and ecological risks resulting from Environmental Restoration and Waste Management activities across the Department of Energy (DOE) complex. DOE is currently assessing these activities as part of the Environmental Restoration and Waste Management Programmatic Environmental Impact Statement (EM-PEIS)

40 CFR 260.41 - Procedures for case-by-case regulation of hazardous waste recycling activities.

Science.gov (United States)

2010-07-01

... of hazardous waste recycling activities. 260.41 Section 260.41 Protection of Environment... Rulemaking Petitions § 260.41 Procedures for case-by-case regulation of hazardous waste recycling activities... hazardous waste recycling activities described in § 261.6(a)(2)(iii) under the provisions of § 261.6 (b) and...

The management of low activity radioactive waste: IAEA guidance and perspectives

International Nuclear Information System (INIS)

Louvat, D.; Rowat, J.H.; Potier, J.M.

2005-01-01

This paper describes the safety standards and reports of the International Atomic Energy Agency (IAEA) applicable to the management and disposal of low activity radioactive waste and provides some historical perspective on their development. Some of the most important current issues in the area of low activity radioactive waste management are discussed in the context of related ongoing IAEA activities. At the end of the paper, a number of issues and questions are raised for consideration and discussion at this symposium. (author)

Scaling factors for the activity determination of radioactive waste from nuclear power reactors

International Nuclear Information System (INIS)

Medici, Marcela A.; Piumetti, Elsa H.

2007-01-01

Specific information of the total activity and activity concentration of the radionuclides contained is required for conditioning, transporting and final disposal of radioactive waste. Due to the complexity associated to alpha and beta measurements for these emitters it is worldwide used, particularly in the case of heterogeneous radioactive waste, the Scaling Factor Method. As in other cases, inputs of the results of the analysis of waste samples taking from waste streams are necessary. The Scaling Factor Method is based on the determination of averaged correlations between the activity concentrations of Difficult to Measure (DTM) nuclides (i.e. alpha and beta emitters) and the activity concentration of easy to measure nuclides (i.e. strong gamma emitters) called Key Nuclides (KN). In the application of this method two phases may be identified: in the first one the degree of correlation between averaged activities of DTM and a given KN is verified, and specific Scaling Factors are derived for every DTM radionuclide. In the second stage the total activity and the activity concentration of the selected KN is determined in each waste item and, by applying the SFs obtained previously, the activities of DTM nuclides are calculated. It is concluded that this method is appropriate and cost-effective and it is stressed that it is only applicable while the Nuclear Power Reactor is in operation. (author)

(Bio)degradation of RDX and HMX in Marine/Estuarine Water and Sediments

Science.gov (United States)

2006-09-01

four fungal strains Rhodotorula sp . HAW-OCF1, Bullera sp . HAW-OCF2, Acremonium sp . HAW-OCF3 and Penicillium sp . HAW-OCF5, were isolated as RDX...represent four novel species of Shewanella described as follows: Shewanella sediminis sp . nov.: Strain HAW-EB3T contains lysine decarboxylase that is...We proposed Shewanella sediminis sp . nov. with HAW-EB3T (= NCIMB 14036T = DSM 17055T) as the type strain (Zhao et al. 2005). Shewanella halifaxensis

Fluidized Bed Steam Reforming For Treatment And Immobilization Of Low-Activity Waste

International Nuclear Information System (INIS)

Hewitt, W.M.

2011-01-01

This report is one of four reports written to provide background information regarding immobilization technologies remaining under consideration for supplemental immobilization of Hanford's low-activity waste. This paper provides the reader a general understanding of fluidized bed steam reforming and its possible application to treat and immobilize Hanford low-activity waste.

Recent IAEA activities to support utilisation of cementitious materials in radioactive waste management

International Nuclear Information System (INIS)

Ojowan, M.I.; Samanta, S.K.

2015-01-01

The International Atomic Energy Agency promotes a safe and effective management of radioactive waste and has suitable programmes in place to serve the needs of Member States in this area. In support of these programmes the Waste Technology Section fosters technology transfer, promotes information exchange and cooperative research, as well as builds capacity in Member States to manage radioactive wastes, resulting both from the nuclear fuel cycle and nuclear applications. Technical assistance in pre disposal area covers all of these activities and is delivered through established Agency mechanisms including publication of technical documents. While the Agency does not conduct any in-house research activities, its Coordinated Research Projects (CRPs) foster research in Member States. There are 2 CRPs concerning cementitious materials: a CRP on cements and an on-going CRP on irradiated graphite waste. The CRP on cements has resulted in the recent IAEA publication TECDOC-1701. An important activity concerned with characterisation of cementitious waste forms is the LABONET network of laboratory-based centres of expertise involved in the characterization of low and intermediate level radioactive wastes. The Waste Technology Section is preparing a series of comprehensive state of the art technical handbooks

Progress report of the ECN contribution to the experiments in the HAW project

International Nuclear Information System (INIS)

Duijves, K.A.; Vonka, V.

1990-12-01

This progress report documents the progress of the ECN contribution in the High Active Waste experiment, a large-scale in situ test being performed underground at the Asse salt mine in Remlingen FRG, during the period April 1st through June 30th, 1990. In ch. 2 a general overview is given of the experiment development. Problems and solutions are discussed in ch. 3. (author). 4 refs.; 10 figs

Considerations on the construction testing of the CASTOR registered HAW 28M cask with respect to the traffic law in the view of the responsible authority BAM

International Nuclear Information System (INIS)

Wille, Frank; Droste, Bernhard; Zencker, Uwe; Komann, Steffen

2010-01-01

The authors reflect the construction testing of the CASTOR registered HAW 28M cask with respect to the traffic law in the view of the responsible authority BAM. The test procedures are based on the recommendations of the IAEA and the respective national and international legal regulations for the transport of radioactive materials. BAM is performing mechanical and thermal tests to investigate the safety of the containers in case of a severe accident. The radionuclide release has to be restricted to a defined limiting value, the radiation shielding and the nuclear safety have to be ensured. The component test is performed using prototypes of model containers combined with calculations or transferability considerations. The safety evaluation is usually based on experimental tests and numerical analyses.

Electrolysis of Gold from Filtration Waste by Means of Mechanical Activation

Directory of Open Access Journals (Sweden)

Jana Ficeriová

2012-12-01

Full Text Available The intensification of the gold thiourea leaching from a filtration waste (Košice, Slovakia using mechanical activationas the pretreatment step has been studied. The leaching of “as-received“ sample in an acid thiourea solution resulted in 65 % Audissolution. However, after mechanical activation in a planetary mill 99 % of the gold was leached. The optimum redox potential forelectrolysis is in the range 500-523 mV for the gold extraction 99.79 % from the mechanically activated sample. The mechanicalactivation resulted in an increase of the specific surface area of the waste from 0.7 m2g-1 to a maximum value of 13.5 m2g-1. The physicochemicalchanges in the filtration waste as a consequence of mechanical activation had a pronounced influence on the subsequent goldextraction.

Bulk Vitrification Technology For The Treatment And Immobilization Of Low-Activity Waste

International Nuclear Information System (INIS)

Ard, K.E.

2011-01-01

This report is one of four reports written to provide background information regarding immobilization technologies under consideration for supplemental immobilization of Hanford's low-activity waste. This paper is intended to provide the reader with general understanding of Bulk Vitrification and how it might be applied to immobilization of Hanford's low-activity waste.

FLUIDIZED BED STEAM REFORMING FOR TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE

Energy Technology Data Exchange (ETDEWEB)

HEWITT WM

2011-04-08

This report is one of four reports written to provide background information regarding immobilization technologies remaining under consideration for supplemental immobilization of Hanford's low-activity waste. This paper provides the reader a general understanding of fluidized bed steam reforming and its possible application to treat and immobilize Hanford low-activity waste.

Recycling of radioactive mineral waste by activity separation

International Nuclear Information System (INIS)

Schartmann, F.; Cramer, T.; Meier-Kortwig, J.; Diedenhofen, S.; Wotruba, H.

2005-01-01

The AST process is a device for the recycling of building rubble originating from the dismantling of nuclear installations. Due to the activity separation in the process, a major part of rubble which would have otherwise been radioactive waste can now be cleared. The AST process has been developed in the course of the combined research project ''Aufbereitung radioaktiver mineralischer Rueckstaede durch Aktivitaetsseparation (Recycling of radioactive mineral waste by activity separation)'' which was sponsored by the BMBF (Federal Ministry for Education and Research). The first step was to investigate the activity distribution between the various constituents of activated heavy concrete (additions: hematite, magnetite, iron cuttings), of contaminated heavy and normal concrete, as well as of composition floor. Heavy concrete with metal additions showed a selective activation of the various constituents. Contaminated rubble often exhibits a selective enrichment of the activity in the cement in contrast to the aggregate. The AST facility for activity separation was designed on the basis of these results. Trial operation with various types of building rubble was carried out using three methods for sorting, screening according to grain size, magnetic separation and radiometric sorting. The use of these three methods was adapted to the material. (orig.)

Long-term α-hazard of high activity waste from nuclear fuel reprocessing

International Nuclear Information System (INIS)

Girardi, F.; Bertozzi, G.

1974-01-01

The concentration and decay of α-emitters in high activity waste arising from spent nuclear fuel reprocessing was calculated under specified reference conditions. An attempt to evaluate the long-term hazard of such waste is being made by applying the ''barrier'' approach derived from reactor safety studies. Four barriers were identified, which could be evaluated in a probabilistic way by taking into account the great uncertainties present in each of them. The barriers are: 1) quality of the segregation afforded by deep geological formations, 2) stability of conditioned waste (chemical and physical), 3) retention by immediate surrounding, 4) distribution pattern of actinides in the environment. The analysis of a fictional accident showed that the uncertainties connected with the evaluation of the barriers' value are rather large. Additional studies particularly on the stability of conditioned waste and ecological properties of the environment towards actinides, would considerably improve our knowledge of the value of the barrier system. Chemical separation of actinides from high activity waste would be an additional option of undoubted value for the disposal of high activity waste. Its value for the overall safety of the entire waste inventory depends on many factors which need better evaluation, such as safety of the disposal of the separated actinides and the amount and quality of the additional waste generated by the separation process. An analysis of various levels of possible separations suggests that a reasonable target might be: Pu, Am and Cm, decontamination factor 10 3 ; Np, coextraction with U and Pu with a 90% yield

TWRS retrieval and storage mission. Immobilized low-activity waste disposal plan

International Nuclear Information System (INIS)

Shade, J.W.

1998-01-01

The TWRS mission is to store, treat, and immobilize highly radioactive Hanford waste (current and future tank waste and the encapsulated cesium and strontium) in a safe, environmentally sound, and cost-effective manner (TWRS JMN Justification for mission need). The mission includes retrieval, pretreatment, immobilization, interim storage and disposal, and tank closure. As part of this mission, DOE has established the TWRS Office to manage all Hanford Site tank waste activities. The TWRS program has identified the need to store, treat, immobilize, and dispose of the highly radioactive Hanford Site tank waste and encapsulated cesium and strontium materials in an environmentally sound, safe, and cost-effective manner. To support environmental remediation and restoration at the Hanford Site a two-phase approach to using private contractors to treat and immobilize the low-activity and high-level waste currently stored in underground tanks is planned. The request for proposals (RFP) for the first phase of waste treatment and immobilization was issued in February 1996 (Wagoner 1996) and initial contracts for two private contractor teams led by British Nuclear Fuels Ltd. and Lockheed-Martin Advanced Environmental Services were signed in September 1996. Phase 1 is a proof-of-concept and commercial demonstration effort to demonstrate the technical and business feasibility of using private facilities to treat Hanford Site waste, maintain radiological, nuclear, process, and occupational safety; and maintain environmental protection and compliance while reducing lifecycle costs and waste treatment times. Phase 1 production of ILAW is planned to begin in June 2002 and could treat up to about 13 percent of the waste. Phase 1 production is expected to be completed in 2007 for minimum order quantities or 2011 for maximum order quantities. Phase 2 is a full-scale production effort that will begin after Phase 1 and treat and immobilize most of the waste. Phase 2 production is

Phase 1 immobilized low-activity waste operational source term

International Nuclear Information System (INIS)

Burbank, D.A.

1998-01-01

This report presents an engineering analysis of the Phase 1 privatization feeds to establish an operational source term for storage and disposal of immobilized low-activity waste packages at the Hanford Site. The source term information is needed to establish a preliminary estimate of the numbers of remote-handled and contact-handled waste packages. A discussion of the uncertainties and their impact on the source term and waste package distribution is also presented. It should be noted that this study is concerned with operational impacts only. Source terms used for accident scenarios would differ due to alpha and beta radiation which were not significant in this study

Anaerobic bioleaching of metals from waste activated sludge

KAUST Repository

Meulepas, Roel J W; Gonzalez-Gil, Graciela; Teshager, Fitfety Melese; Witharana, Ayoma; Saikaly, Pascal; Lens, Piet Nl L

2015-01-01

Heavy metal contamination of anaerobically digested waste activated sludge hampers its reuse as fertilizer or soil conditioner. Conventional methods to leach metals require aeration or the addition of leaching agents. This paper investigates whether

Gamma irradiation induced disintegration of waste activated sludge for biological hydrogen production

International Nuclear Information System (INIS)

Yin, Yanan; Wang, Jianlong

2016-01-01

In this paper, gamma irradiation was applied for the disintegration and dissolution of waste activated sludge produced during the biological wastewater treatment, and the solubilized sludge was used as substrate for bio-hydrogen production. The experimental results showed that the solubilization of waste activated sludge was 53.7% at 20 kGy and pH=12, and the SCOD, polysaccharides, protein, TN and TP contents in the irradiated sludge solutions was 3789.6 mg/L, 268.3 mg/L, 1881.5 mg/L, 132.3 mg/L and 80.4 mg/L, respectively. The irradiated sludge was used for fermentative hydrogen production, and the hydrogen yield was 10.5±0.7 mL/g SCOD consumed . It can be concluded that the irradiated waste activated sludge could be used as a low-cost substrate for fermentative hydrogen production. - Highlights: • The waste activated sludge could be disintegrated by gamma irradiation. • The disintegrated sludge could be used for biohydrogen production. • The hydrogen yield was 10.5±0.7 mL/g SCOD consumed .

Waste monitoring of the uranium ore processing activities in Romania

International Nuclear Information System (INIS)

Nica, L.

2002-01-01

The uranium ore processing activities at the Feldioara site produce a range of liquid and solid waste that are monitored. Liquids are treated through decantation, pH correction and uranium precipitation before their release into the environment. The solid waste is gathered into ore specific area and are covered regularly with clay materials. (author)

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

Identification of items and activities important to waste form acceptance by Westinghouse GoCo sites

International Nuclear Information System (INIS)

Plodinec, M.J.; Marra, S.L.; Dempster, J.; Randklev, E.H.

1993-01-01

The Department of Energy has established specifications (Waste Acceptance Product Specifications for Vitrified High-Level Waste Forms, or WAPS) for canistered waste forms produced at Hanford, Savannah River, and West Valley. Compliance with these specifications requires that each waste form producer identify the items and activities which must be controlled to ensure compliance. As part of quality assurance oversight activities, reviewers have tried to compare the methodologies used by the waste form producers to identify items and activities important to waste form acceptance. Due to the lack of a documented comparison of the methods used by each producer, confusion has resulted over whether the methods being used are consistent. This confusion has been exacerbated by different systems of nomenclature used by each producer, and the different stages of development of each project. The waste form producers have met three times in the last two years, most recently on June 28, 1993, to exchange information on each producer's program. These meetings have been sponsored by the Westinghouse GoCo HLW Vitrification Committee. This document is the result of this most recent exchange. It fills the need for a documented comparison of the methodologies used to identify items and activities important to waste form acceptance. In this document, the methodology being used by each waste form producer is summarized, and the degree of consistency among the waste form producers is determined

BULK VITRIFICATION TECHNOLOGY FOR THE TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE

Energy Technology Data Exchange (ETDEWEB)

ARD KE

2011-04-11

This report is one of four reports written to provide background information regarding immobilization technologies under consideration for supplemental immobilization of Hanford's low-activity waste. This paper is intended to provide the reader with general understanding of Bulk Vitrification and how it might be applied to immobilization of Hanford's low-activity waste.

Quality checking task force destructive testing of active waste forms

International Nuclear Information System (INIS)

James, J.M.; Smith, D.L.

1987-03-01

The implications of sampling and testing of full size active packages of intermediate level wastes are summarised in this report. Sampling operations are technically feasible but a major difficulty will be the disposal of secondary waste. A literature survey indicated that destructive testing of wasteforms is not carried out as a routine operation in Europe or the USA. (author)

The Transuranic Waste Program's integration and planning activities and the contributions of the TRU partnership

International Nuclear Information System (INIS)

Harms, T.C.; O'Neal, W.; Petersen, C.A.; McDonald, C.E.

1994-02-01

The Technical Support Division, EM-351 manages the integration and planning activities of the Transuranic Waste Program. The Transuranic Waste Program manager provides transuranic waste policy, guidance, and issue resolution to Headquarters and the Operations Offices. In addition, the program manager is responsible for developing and implementing an integrated, long-range waste management plan for the transuranic waste system. A steering committee, a core group of support contractors, and numerous interface working groups support the efforts of the program manager. This paper provides an overview of the US Department of Energy's transuranic waste integration activities and a long-range planning process that includes internal and external stakeholder participation. It discusses the contributions and benefits provided by the Transuranic Partnership, most significantly, the integration activities and the body of data collected and assembled by the Partnership

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.

Waste reduction by re-use of low activated material - 16035

International Nuclear Information System (INIS)

Ehrlicher, Ulrich; Pauli, Heinz

2009-01-01

A multidisciplinary institute, equipped with research reactors and accelerator-driven research installations produces and, in the case of PSI, collects radioactive waste on one hand and requires material, especially for shielding purpose, on the other hand. The legislative framework for radiation protection, financial reasons and limited storage capacity strongly force Paul Scherrer Institute and comparable facilities to minimize radioactive waste. Besides free release of inactive components, recycling and re-use of low-level radioactive material in controlled areas are the best means for waste minimization. The re-use of slightly activated steel plates as a shielding material and the recycling of irradiated reactor graphite as a filling material embedded in mortar may give examples and encouragement for similar activities. Besides the advantages for radiation protection, the financial benefit can be measured in millions of dollars. (authors)

15 years return transport of vitrified high-level waste from France. The long way from La Hague to Gorleben; 15 Jahre Rueckfuehrung von verglasten hochaktiven Abfaellen aus Frankreich. Der lange Weg von La Hague nach Gorleben

Energy Technology Data Exchange (ETDEWEB)

Horn, Thomas [GNS Gesellschaft fuer Nuklear Service mbH, Essen (Germany)

2012-11-01

The operators of German nuclear power plants have contracts since 1977 with the French company AREVA NC (former COGEMA) and since 1980 with the British company NDA (former BNFL) for reprocessing of spent nuclear fuel. Since July 2005 the delivery of irradiated fuel element into a reprocessing plant is prohibited. Until 2005 fuel elements with about 6.080 tSM were shipped abroad, about 5.309 tSM to France. The contribution deals with the history of the transports from La Hague to Gorleben, including the contamination problems in 1988 that caused restrictions by the German authorities. A catalogue of safety requirements had to be fulfilled for the allowance of further return transports. The development of appropriate transport casks to cope with changing heat generation of the high-level waste is described. During the complete transport cycle extensive radiological measurements were performed. By the end of 2011 the HAW (high-level waste) glass coquilles were completely returned to Gorleben.

Notes on the typification of some species of Aloe (Asphodelaceae/Aloaceae

Directory of Open Access Journals (Sweden)

H. F. Glen

1995-10-01

Full Text Available Lecto- or neotypes are designated for Aloe thompsoniae Groenew.. A. micracantha Haw .. A. schmidticma Regel (a synonym of/4,  cooperi Baker. A. longistyla Baker. A. aristata Haw., A. longiaristata Schult. & Schult. f„ (a synonym of the preceding name, A. humilis (L. Mill. var.  incurva Haw.. A. glauca Mill., A. niuricata Schult. (a synonym of the preceding name. A. saponaria (Aiton Haw. var.  latifolia Haw. (a new synonym of A. maculata All. and A. pluridens Haw. The confusing citation of the type of A. thomcroftii Pole Evans is clarified.

The very-low activity waste storage facility. A new waste management system; Le centre de stockage des dechets de tres faible activite. Une nouvelle filiere de gestion

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

Very-low activity wastes have a radioactivity level close to the natural one. This category of waste is taken into consideration by the French legislation and their storage is one of their point of achievement. This document gives a complete overview of the principles of storage implemented at the storage center for very-low activity wastes (CSTFA) sited in the Aube departement in the vicinity of the storage center for low- and intermediate activity wastes: storage concept, wastes confinement, center organization, environmental monitoring. (J.S.)

Disposal Activities and the Unique Waste Streams at the Nevada National Security Site (NNSS)

International Nuclear Information System (INIS)

Arnold, P.

2012-01-01

This slide show documents waste disposal at the Nevada National Security Site. Topics covered include: radionuclide requirements for waste disposal; approved performance assessment (PA) for depleted uranium disposal; requirements; program approval; the Waste Acceptance Review Panel (WARP); description of the Radioactive Waste Acceptance Program (RWAP); facility evaluation; recent program accomplishments, nuclear facility safety changes; higher-activity waste stream disposal; and, large volume bulk waste streams

Activation of waste brewer's yeast Saccharomyces cerevisiae for bread production

Directory of Open Access Journals (Sweden)

Popov Stevan D.

2005-01-01

Full Text Available The waste brewer's yeast S. cerevisiae (activated and non-activated was compared with the commercial baker's yeast regarding the volume of developed gas in dough, volume and freshness stability of produced bread. The activation of waste brewer's yeast resulted in the increased volume of developed gas in dough by 100% compared to non-activated brewer's yeast, and the obtained bread is of more stable freshness compared to bread produced with baker's yeast. The activation of BY affects positively the quality of produced bread regarding bread volume. The volume of developed gas in dough prepared with the use of non-activated BY was not sufficient, therefore, it should not be used as fermentation agent, but only as an additive in bread production process for bread freshness preservation. Intense mixing of dough results in more compressible crumb 48 hrs after baking compared to high-speed mixing.

Neutron activation analysis of alternative waste forms at the Savannah River Laboratory

International Nuclear Information System (INIS)

Johns, R.A.

1981-01-01

A remotely controlled system for neutron activation of candidate high-level waste (HLW) isolation forms was built by the Savannah River Laboratory at a Savannah River Plant reactor. With this system, samples can be irradiated for up to 24 hours and transferred through pneumatic tubing to a shielded repository unitl their activity is low enough for them to be handled in a radiobench. The principal use of the system is to support the Alternative Waste Forms Leach Testing (AWFLT) Program in which the comparative leachability of the various waste forms will be determined. The experimental method used in this work is based on neutron activation analysis techniques. Neutron irradiation of the solid waste form containing simulated HLW sludge activates elements in the sample. After suitable leaching of the solid matrix in standard solutions, the leachate and solid are assayed for gamma-emitting nuclides. From these measurements, the fraction of a specific element leached can be determined al half-lives with experimental ones, over a range of 24 orders of magnitude was obtained. This is a strong argument that the alpha decay could be considered a fission process with very high mass asymmetry and charge density asymmetry

Mixed-waste minimization activities in the nuclear weapons complex

International Nuclear Information System (INIS)

Marchetti, J.A.; Suffern, J.S.

1991-01-01

Over the past 40 years, the US Department of Energy (DOE) and the nuclear weapons complex have successfully executed their mission of providing the country with a strong nuclear deterrent. Now, however, they must attain another mission at the same time: to eliminate or greatly reduce the environmental, safety, and health problems in the complex. Mixed-waste minimization activities have taken place in 11 of the complex production plants and laboratories: the Pinellas plant, the Mount plant, the Kansas City plant, the Y-12 plant, the Rocky Flats plant, the Savannah River Site (SRS), the Savannah River Site (SRS), the Pantex plant, the Nevada Test Site, Sandia National Laboratories, Los Alamos National Laboratory, and the Lawrence Livermore National Laboratory. The mixed-waste minimization opportunities that have been implemented to date by the production facilities are different from those that have been implemented by the laboratories. Areas of opportunity at the plants involve the following activities: (1) process design or improvement; (2) substitution of materials; (3) waste segregation; (4) recycling; and (5) administrative controls

Waste management, decommissioning and environmental restoration for Canada's nuclear activities. Proceedings

International Nuclear Information System (INIS)

2011-01-01

The Canadian Nuclear Society conference on Waste Management, Decommissioning and Environmental Restoration for Canada's Nuclear Activities was held in Toronto, Ontario, Canada on September 11-14, 2011. The conference provided a forum for discussion of the status and proposed future directions of technical, regularly, environmental, social and economic aspects of radioactive waste management, nuclear facility decommissioning, and environmental restoration activities for Canadian nuclear facilities. The conference included both plenary sessions and sessions devoted to more detailed technical issues. The plenary sessions were focussed on three broad themes: the overall Canadian program; low and intermediate waste; and, international perspectives. Topics of the technical sessions included: OPG's deep geologic repository for low and intermediate level waste; stakeholder interactions; decommissioning projects; uranium mine waste management; used fuel repository - design and safety assessment; federal policies, programs and oversight; regulatory considerations; aboriginal traditional knowledge; geological disposal - CRL site classification; geological disposal - modelling and engineered barriers; Port Hope Area Initiative; waste characterization; LILWM - treatment and processing; decommissioning projects and information management; international experience; environmental remediation; fuel cycles and waste processing.

Waste Composite Sensor Designed by Cellulose and Activated Carbon as Ethylene Absorber

Directory of Open Access Journals (Sweden)

S. Ummartyotin

2016-01-01

Full Text Available Activated carbon was successfully derived from scrap tile waste from thermochemical conversion. Chemical and physical modifications were therefore employed to modify the specific surface area and porosity of activated carbon. Cellulose was successfully extracted from palm front. Designation of waste composite was prepared by cellulose and activated carbon. Less than 30 wt% of activated carbon was integrated into cellulose sheet matrix. It was important to note that there is no change in mechanical and morphological properties. Small amount of activated carbon was well dispersed. In order to investigate the feasibility of composite as active packaging, oxygen permeation rate and ethylene gas adsorption ability were preliminary investigated.

Performance objectives for the Hanford Immobilized Low-Activity Waste (ILAW) performance assessment

International Nuclear Information System (INIS)

MANN, F.M.

1999-01-01

Performance objectives for the disposal of low activity waste from Hanford Waste Tanks have been developed. These objectives have been based on DOE requirements, programmatic requirements, and public involvement. The DOE requirements include regulations that direct the performance assessment and are cited within the Radioactive Waste Management Order (DOE Order 435.1). Performance objectives for other DOE complex performance assessments have been included

75 FR 65625 - Agency Information Collection Activities; Proposed Collection; Comment Request; Hazardous Waste...

Science.gov (United States)

2010-10-26

... Activities; Proposed Collection; Comment Request; Hazardous Waste Specific Unit Requirements, and Special Waste Processes and Types, EPA ICR Number 1572.08, OMB Control Number 2050-0050 AGENCY: Environmental..., and Special Waste Processes and Types. ICR numbers: EPA ICR No. 1572.08, OMB Control No. 2050-0050...

Vitrification of Three Low-Activity Radioactive Waste Streams from Hanford

International Nuclear Information System (INIS)

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

1998-09-01

As part of a demonstration for British Nuclear Fuels Limited, Incorporated (BNFL), the Immobilization Technology Section (ITS) of the Savannah River Technology Center (SRTC) has produced and characterized three low-activity waste (LAW) glasses from Hanford radioactive waste samples. The three LAW glasses were produced from radioactive supernate samples that had been treated by the Waste Processing Technology Section (WPTS) at SRTC to remove most of the radionuclides. These three glasses were produced by mixing the waste streams with between four and nine glass-forming chemicals in platinum/gold crucibles and heating the mixture to between 1120 and 1150 degrees C. Compositions of the resulting glass waste forms were close to the target compositions. Low concentrations of radionuclides in the LAW feed streams and, therefore, in the glass waste forms supported WPTS conclusions that pretreatment had been successful. No crystals were detected in the LAW glasses. In addition, all glass waste forms passed the leach tests that were performed. These included a 20 degrees C Product Consistency Test (PCT) and a modified version of the United States Environmental Protection Agency Toxicity Characteristic Leaching Procedure (TCLP)

Characterization of selected waste tanks from the active LLLW system

International Nuclear Information System (INIS)

Keller, J.M.; Giaquinto, J.M.; Griest, W.H.

1996-08-01

From September 1989 through January of 1990, there was a major effort to sample and analyze the Active Liquid-Low Level Waste (LLLW) tanks at ORNL which include the Melton Valley Storage Tanks (MVST) and the Bethel Valley Evaporator Service Tanks (BVEST). The purpose of this report is to summarize additional analytical data collected from some of the active waste tanks from November 1993 through February 1996. The analytical data for this report was collected for several unrelated projects which had different data requirements. The overall analyte list was similar for these projects and the level of quality assurance was the same for all work reported. the new data includes isotopic ratios for uranium and plutonium and an evaluation of the denature ratios to address criticality concerns. Also, radionuclides not previously measured in these waste tanks, including 99Tc and 237Np, are provided in this report

Melter feed viscosity during conversion to glass: Comparison between low-activity waste and high-level waste feeds

Energy Technology Data Exchange (ETDEWEB)

Jin, Tongan [Pacific Northwest National Laboratory, Richland Washington; Chun, Jaehun [Pacific Northwest National Laboratory, Richland Washington; Dixon, Derek R. [Pacific Northwest National Laboratory, Richland Washington; Kim, Dongsang [Pacific Northwest National Laboratory, Richland Washington; Crum, Jarrod V. [Pacific Northwest National Laboratory, Richland Washington; Bonham, Charles C. [Pacific Northwest National Laboratory, Richland Washington; VanderVeer, Bradley J. [Pacific Northwest National Laboratory, Richland Washington; Rodriguez, Carmen P. [Pacific Northwest National Laboratory, Richland Washington; Weese, Brigitte L. [Pacific Northwest National Laboratory, Richland Washington; Schweiger, Michael J. [Pacific Northwest National Laboratory, Richland Washington; Kruger, Albert A. [U.S. Department of Energy, Office of River Protection, Richland Washington; Hrma, Pavel [Pacific Northwest National Laboratory, Richland Washington

2017-12-07

During nuclear waste vitrification, a melter feed (generally a slurry-like mixture of a nuclear waste and various glass forming and modifying additives) is charged into the melter where undissolved refractory constituents are suspended together with evolved gas bubbles from complex reactions. Knowledge of flow properties of various reacting melter feeds is necessary to understand their unique feed-to-glass conversion processes occurring within a floating layer of melter feed called a cold cap. The viscosity of two low-activity waste (LAW) melter feeds were studied during heating and correlated with volume fractions of undissolved solid phase and gas phase. In contrast to the high-level waste (HLW) melter feed, the effects of undissolved solid and gas phases play comparable roles and are required to represent the viscosity of LAW melter feeds. This study can help bring physical insights to feed viscosity of reacting melter feeds with different compositions and foaming behavior in nuclear waste vitrification.

Effect of ultrasonic specific energy on waste activated sludge ...

African Journals Online (AJOL)

The effect of ultrasonic specific energy on waste activated sludge (WAS) solubilization and enzyme activity was investigated in this study. Experimental results showed that the increase of ultrasonic specific energy in the range of 0 - 90000 kJ/kg dried sludge (DS) benefited WAS particle size reduction and the solubilization ...

Update of Nuclear Waste Policy Act transportation activities

International Nuclear Information System (INIS)

Callaghan, E.F.

1987-01-01

As directed by the Nuclear Waste Policy Act of 1982 (NWPA), the Department of Energy (DOE) is developing a nationwide system for transporting spent nuclear fuel and high-level radioactive waste from commercial power plants to deep geologic repositories for disposal. Plans for the transportation system will consider the following factors: the President's 1985 decision to co-locate some defense high-level waste with commercial waste in a repository, the NWPA requirement that the private sector be used to the fullest extent possible in developing and operating the system, and the possible approval by Congress of the DOE's proposal for a Monitored Retrievable Storage (MRS) facility, submitted in March 1987. (The MRS, if approved, would provide for the consolidation, packaging, and perhaps the temporary storage of spent fuel from reactors.) The ''Transportation Business Plan'', published in January 1986, reflects these considerations. The transportation system, when operational, will consist of two elements: (1) the cask system, which includes the transportation casks, the vehicular conveyances, tie-downs, and associated equipment for handling the casks; and (2) the transportation support system which is comprised of facilities, equipment, and services to support waste transportation. Development of the transportation system incorporates the following work elements: operational planning, support systems development, cash system development, systems analysis, and institutional activities. This paper focusses on the technical aspects of the system

State and Federal activities on low-level waste

International Nuclear Information System (INIS)

1983-01-01

With the passage of the Low-Level Waste Policy Act in December 1980, the states have assumed the management responsibility and the federal government has become a facilitator. State and Federal roles in regulation have not altered. This paper reviews the developments over the last two years to point out the progress made and critical steps that lie ahead. Both technological and political aspects are covered, and a conclusion is presented with a look to the future. Since compact development in the tool chosen by the politicans for low-level waste management, the author reviews the present status starting with the northwest compact which has been introduced into the House and Senate and is subject to hearings. The past two years have seen real progress in technology in the broadest sense. An information development and dissemination system was established in 1978 wih the state-by-state assessment of low-level waste disposal. Annual examinations have been made through 1981 which enables one to understand the generation of low-level wastes. Policy level planning by states can be supported by the base level of information available. Incineration of dry active waste and other non-fuel cycle waste is ready to be fully accepted. Much work has been done on volume reduction of liquids. The increased understanding of the ways to make a disposal site work represents a major technolological improvement. Within the DOE system, there is beginning to be a real understanding of the critical parameters in disposal site performance in the East

Low-level waste research and development activities of the Department of Energy

International Nuclear Information System (INIS)

Barainca, M.J.

1986-01-01

This paper presents an overview of the technical activities of the Department of Energy's Defense and Nuclear Energy Low-Level Radioactive Waste Management Programs (LLWPs). Although each Program was established with a different purpose, the technologies developed and demonstrated by each are transferable for use in both the commercial and DOE sectors. This paper presents an overview of the technical activities being pursued through both the Defense and Nuclear Energy LLWP's. These technologies have been placed in the following categories; Criteria and Standards, Systems Analysis, Information and Technology Transfer, Waste Treatment and Wast Form, Improved Near Surface Disposal, Greater Confinement Disposal, Corrective Measures, and Monitoring

Remedial investigation report on waste area grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 4, Appendix C, Risk assessment

International Nuclear Information System (INIS)

1995-09-01

Waste Area Grouping (WAG) 5 is part of Oak Ridge National Laboratory (ORNL) and is located on the United States Department of Energy's Oak Ridge Reservation (DOE-ORR). The site lies southeast of Haw Ridge in Melton Valley and comprises approximately 32 ha (80 ac) [12 ha (30 ac) of forested area and the balance in grassed fields]. Waste Area Grouping 5 consists of several contaminant source areas for the disposal of low-level radioactive, transuranic (TRU), and fissile wastes (1959 to 1973) as well as inorganic and organic chemical wastes. Wastes were buried in trenches and auger holes. Radionuclides from buried wastes are being transported by shallow groundwater to Melton Branch and White Oak Creek. Different chemicals of potential concern (COPCs) were identified (e.g., cesium-137, strontium-90, radium-226, thorium-228, etc.); other constituents and chemicals, such as vinyl chloride, bis(2-ethylhexyl)phthalate, trichloroethene, were also identified as COPCs. Based on the results of this assessment contaminants of concern (COCs) were subsequently identified. The objectives of the WAG 5 Baseline Human Health Risk Assessment (BHHRA) are to document the potential health hazards (i.e., risks) that may result from contaminants on or released from the site and provide information necessary for reaching informed remedial decisions. As part of the DOE-Oak Ridge Operations (ORO), ORNL and its associated waste/contamination sites fall under the auspices of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), also known as Superfund under the Superfund Amendments and Reauthorization Act (SARA). The results of the BHHRA will (1) document and evaluate risks to human health, (2) help determine the need for remedial action, (3) determine chemical concentrations protective of current and future human receptors, and (4) help select and compare various remedial alternatives.

Institut fuer Nukleare Entsorgungstechnik: Status report on research and development 1984

International Nuclear Information System (INIS)

1985-02-01

Some of the main points tackled by the Institute during 1984 included: Testing the glassification technique for radioactive waste and design and construction of a glassification plant; examination of the properties of glass products, testing of incineration of waste containing plutonium; solidification of concentrate containing alpha particles; separation of actinides and fission products from MAW; examination of the release procedures of radio-nuclides from waste solidified with cement; development of long-term containers for the final storage of HAW glass products in salt; model calculations for thermo-mechanical processes and for release mechanisms in final storage. (RB) [de

1993 annual report of hazardous waste activities for the Oak Ridge K-25 site

International Nuclear Information System (INIS)

1994-02-01

This report is a detailed listing of all of the Hazardous Waste activities occurring at Martin Marietta's K-25 site. Contained herein are hazardous waste notification forms, waste stream reports, generator fee forms and various TSDR reports

Report on the emergency response training and equipment activities through 1991 for the transportation of transuranic waste to the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1992-04-01

The Waste Isolation Pilot Plant (WIPP) is a research and development facility with the mission of demonstrating the safe shipment, emplacement and retrieval of radioactive transuranic (TRU) wastes resulting from the defense activities and programs of the United States. It is the only long-term storage facility constructed for TRU waste. This report provides the status on the Department of Energy (DOE) efforts as of December 31, 1991, regarding emergency response training and equipment funding provided to local, state, and tribal governments for waste shipments to the WIPP. Because of a growing public awareness of transportation activities involving nuclear materials, this report has been prepared to provide a status of the DOE's activities in this regard, as well as the cooperative efforts between the DOE and state and tribal governments

Waste minimization activities in the Materials Fabrication Division at Lawrence Livermore National Laboratory

International Nuclear Information System (INIS)

Dini, J.W.

1991-08-01

The mission of the Materials Fabrication Division (MFD) is to provide fabrication services and technology in support of all programs at Lawrence Livermore National Laboratory (LLNL). MFD involvement is called for when fabrication activity requires levels of expertise, technology, equipment, process development, hazardous processes, security, or scheduling that is typically not commercially available. Customers are encouraged to utilize private industry for fabrication activity requiring routine processing or for production applications. Our waste minimization (WM) program has been directed at source reduction and recycling in concert with the working definition of waste minimization used by EPA. The principal focus of WM activities has been on hazardous wastes as defined by RCRA, however, all pollutant emissions into air, water and land are being considered as part of the program. The incentives include: (1) economics, (2) regulatory conformance, (3) public image and (4) environmental concern. This report discusses the waste minimization program at LLNL

Los Alamos Scientific Laboratory waste management technology development activities. Summary progress report, 1979

International Nuclear Information System (INIS)

Johnson, L.J.

1980-10-01

Summary reports on the Department of Energy's Nuclear Energy-sponsored waste management technology development projects at the Los Alamos Scientific Laboratory describe progress for calendar year 1979. Activities in airborne, low-level, and transuranic waste management areas are discussed. Work progress on waste assay, treatment, disposal, and environmental monitoring is reviewed

1993 annual report of hazardous waste activities for the Oak Ridge K-25 site

Energy Technology Data Exchange (ETDEWEB)

1994-02-01

This report is a detailed listing of all of the Hazardous Waste activities occurring at Martin Marietta`s K-25 site. Contained herein are hazardous waste notification forms, waste stream reports, generator fee forms and various TSDR reports.

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

International Nuclear Information System (INIS)

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

1989-01-01

A primary objective of low-level radioactive waste management in the United States is to protect the health and safety of the public and the quality of the environment. In support of this objective is the development of waste treatment and disposal technologies designed to provide stabilization and long-term institutional control of low-level radioactive wastes. Presented herein is a technical review of specific low-level radioactive waste management activities in the United States. Waste treatment and disposal technologies are discussed along with the performance objectives of the technologies aimed at protecting the health and safety of the public and the quality of the environment. 13 refs., 4 figs

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

International Nuclear Information System (INIS)

1987-01-01

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

Los Alamos Scientific Laboratory waste management technology development activities. Summary progress report, 1979

Energy Technology Data Exchange (ETDEWEB)

Johnson, L.J. (comp.)

1980-10-01

Summary reports on the Department of Energy's Nuclear Energy-sponsored waste management technology development projects at the Los Alamos Scientific Laboratory describe progress for calendar year 1979. Activities in airborne, low-level, and transuranic waste management areas are discussed. Work progress on waste assay, treatment, disposal, and environmental monitoring is reviewed.

Volume reduction of dry active waste by use of a waste sorting table at the Brunswick nuclear power plant

International Nuclear Information System (INIS)

Snead, P.B.

1988-01-01

Carolina Power and Light Company's Brunswick nuclear power plant has been using a National Nuclear Corporation Model WST-18 Waste Sorting Table to monitor and sort dry active waste for segregating uncontaminated material as a means of low-level waste volume reduction. The WST-18 features 18 large-area, solid scintillation detectors arranged in a 3 x 6 array underneath a sorting/monitoring surface that is shielded from background radiation. An 11-week study at Brunswick showed that the use of the waste sorting table resulted in dramatic improvements in both productivity (man-hours expended per cubic foot of waste processed) and monitoring quality over the previous hand-probe frisking method. Use of the sorting table since the study has confirmed its effectiveness in volume reduction. The waste sorting table paid for its operation in volume reduction savings alone, without accounting for the additional savings from recovering reusable items

Development of MHI's induction melting system for low level radio active solid waste treatment

International Nuclear Information System (INIS)

Murakami, Tadashi; Hashiba, Kenji; Fukui, Hiroshi; Sato, Akio; Minemoto, Masaki

1999-01-01

Mitsubishi Heavy Industries, Ltd., (MHI) has developed melting facilities that reduce radioactive waste volume. The system uses a high-frequency induction to separately melt nonmetallic waste in SUS containers and metallic waste. Use of system extends refractory life. To validate system feasibility, major components were tested with the following results: (1) Two 200-liter drum cans of molten solid waste are produced per work day, (2) Radioactivity in molten solid was homogeneous with a coefficient of variation ≤10%, clarifying residue properties, (3) The radioactive decontamination factor of off-gas facilities --DF=Activity to system/Activity at the system exit --exceeded 10 7 . We confirmed system to fill the requirements for molten solid waste and have the merit of high volume-reduction and long-life refractory. (author)

Low-level dry active waste management planning for Calvert Cliffs Nuclear Power Plant

International Nuclear Information System (INIS)

Butler, C.N.; Feizollani, F.; Jarboe, Th.B.

1984-01-01

To offset the rising cost of low-level radioactive waste disposal and to provide contingency measures for disposal space unavailability after January 1, 1986, Baltimore Gas and Electric (BG and E) has undertake efforts to establish a long-term waste management program. This plan, which was developed after detailed study of a number of options, consists of four elements: management of dry active wastes; implementation of 10CFR61 requirements; storage of process wastes; and enhancement of liquid/solid waste systems and equipment performance. Each element was scheduled for implementation in accordance with an established set of priorities. Accordingly, detailed engineering for implementation of the first two elements was initiated in December of 1982. This paper focuses on BGandE's experience in implementation of the first element o the program, i.e., the management of dry active waste (DAW). DAW is managed by providing a new buildin dedicated to its handling, processing, volume-reduction, and storage. This building, which is equipped with state-of-the-art decontamination and processing techniques, allows for implementation of waste minimization and for interim storage of DAW in a safe and cost effective manner

Idaho Nuclear Technology and Engineering Center Low-Activity Waste Process Technology Program FY-98 Status Report

International Nuclear Information System (INIS)

Herbst, A.K.; McCray, J.A.; Rogers, A.Z.; Simmons, R.F.; Palethrope, S.J.

1999-01-01

The Low-Activity Waste Process Technology Program at the Idaho Nuclear Technology and Engineering Center (INTEC) anticipates that large volumes of low-level/low-activity wastes will need to be grouted prior to near-surface disposal. During fiscal year 1998, three grout formulations were studied for low-activity wastes derived from INTEC liquid sodium-bearing waste. Compressive strength and leach results are presented for phosphate bonding cement, acidic grout, and alkaline grout formulations. In an additional study, grout formulations are recommended for stabilization of the INTEC underground storage tank residual heels

IAEA decadal activities in the field of radioactive gaseous waste management

International Nuclear Information System (INIS)

Plumb, G.R.

1991-01-01

The IAEA has long recognized that gaseous waste management is vital in the design and safe operation of all nuclear facilities such that in the decade of the 1980's the IAEA program covered the important aspects of the entire field. The activities reviewed in this paper were marked at the outset by a comprehensive international symposium on the subject in February 1980 organized by the IAEA jointly with the Nuclear Energy Agency of the OECD when the detailed state-of-the-art was established in 43 papers. In the interim, experts have been convened in IAEA sponsored meetings to result in sixteen technical documents which included summaries of three substantial Co-ordinated Research Programs. Early IAEA activities paid particular attention to management of gas radionuclides which from a matured nuclear industry, could be judged to build-up to long-term sources of irradiation for regional and global populations. Mid-term ongoing activities in handling and retention of gaseous radionuclides arising from abnormal operations in nuclear power plants were given much emphasis following the Chernobyl accident. In the latter years the IAEA activities included detailed examinations of the design and operation of gas cleaning systems for the range of nuclear facilities. Technical reports on gaseous waste management were issued relating to high-level liquid waste conditioning plants (including control of semi-volatiles), nuclear power plants, low- and intermediate-level radioactive materials handling facilities and radioactive waste incinerators

Developments in the management of low and intermediate activity solid wastes at the Cadarache Centre

International Nuclear Information System (INIS)

Barbreau, A.; Marcaillou, J.; Mery, J.; Pinto, D.; Rancon, D.

1975-01-01

The Cadarache Nuclear Studies Centre is located in a thinly populated region. Covering a total area of 1600 hectares, it has been able to accommodate numerous and important research facilities. In 1970, 11 reactors or critical assemblies were in operation. More than 164000 m 2 are devoted to laboratories, testing areas, installations for the inspection of irradiated fuel elements and plutonium technology workshops. Up to 1968 the low- and intermediate-activity solid wastes (categories 1, 2 and 30) collected at the Centre were divided into two classes for disposal purposes: (a) burnable wastes which, after sorting, were destroyed in an incinerator; (b) compressible wastes which were compacted in concrete containers after recovery of the packing, by means of a 250-ton press. The situation at Cadarache and the results obtained in hydrogeological studies have prompted the Centre to improve the processing of these wastes and reduce the cost. The treatment of solid wastes should, in effect, be regarded as a step towards their final elimination. The measure envisaged at Cadarache were thus aimed at permitting final storage on site, in order to reduce the volume of waste, contain the activity and keep the cost to a minimum. The management of solid wastes is at present based on the following methods: (a) storage in trenches with PVC packing for non-burnable solid wastes of categories 1 and 4, after monitoring of specific activities; (b) compacting and storage in leak-proof pools for solid wastes of categories 2 and 3, the most highly active undergoing a period of decay storage beforehand; (c) incineration of burnable solid wastes of categories 1 and 2 and also of contaminated oils and solvents. (author)

Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics

International Nuclear Information System (INIS)

Hulse, R.A.

1991-08-01

Planning for storage or disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of that waste to estimate volumes, radionuclide activities, and waste forms. Data from existing literature, disposal records, and original research were used to estimate the characteristics and project volumes and radionuclide activities to the year 2035. GTCC LLW is categorized as: nuclear utilities waste, sealed sources waste, DOE-held potential GTCC LLW; and, other generator waste. It has been determined that the largest volume of those wastes, approximately 57%, is generated by nuclear power plants. The Other Generator waste category contributes approximately 10% of the total GTCC LLW volume projected to the year 2035. Waste held by the Department of Energy, which is potential GTCC LLW, accounts for nearly 33% of all waste projected to the year 2035; however, no disposal determination has been made for that waste. Sealed sources are less than 0.2% of the total projected volume of GTCC LLW

Levels for the specific activity at disposing low-level contaminated municipal wastes

International Nuclear Information System (INIS)

Poschner, J.; Schaller, G.

1995-01-01

Using radioecological models, nuclide specific values were calculated for the specific activity of low contaminated radioactive waste, which is disposed in conventional waste deposits or burned in incineration plants. The calculation of these values is based on a limit of 10 μSv effective dose in one year, i.e. effective dose possibly resulting from waste disposal or burning should not exceed a 'de-minimis'-value of some 10 μSv per year. The applied radioecological models describe exposure of the public by direct radiation, inhalation and ingestion for the operational period of a deposit or an incineration plant, but also cover post-operational scenarios, collecting and sorting of waste and road accidents of the waste-truck. Referring to the dose limit of 10 μSv/a, a value for the specific activity of waste was calculated for each scenario and each radionuclide considered. The smallest of these values for a radionuclide, the 'basic value' was rounded to a 'reference value'. For about 600 radionuclides reference values were derived. About 90% of the reference values are ranging between 1 and 1 000 Bq/g. For about 90% of the radionuclides direct radiation or inhalation at the deposit proved to be the critical path of exposure. (orig.) [de

ANDRA - National Radioactive Waste Management Agency. Activity report 2006. Management report - Financial statements 2006

International Nuclear Information System (INIS)

2007-06-01

Created in 1979 within the CEA, the National Radioactive Waste Management Agency (ANDRA) was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act: - a R and D mission to propose safe long-term solution for radioactive waste without current disposal system; this mission includes long-term storage, since the 2006 Planning Act, in order to propose interim solutions while final ones are being studied; - an industrial mission concerning, on one hand, waste acceptance criteria and control and, on the other hand, siting, construction, operation, closure and monitoring of repositories. This mission includes as well a public service mission in terms of i) collection of waste of the 'small-scale nuclear activities' producers or owners (including the so-called 'household' radioactive waste, i.e. waste owned by private individuals) and ii) clean-up and rehabilitation of orphan polluted sites; - an information mission, notably through the regular publication of the National Inventory of radioactive materials and waste. This mission includes as well an active policy of dialogue with stakeholders both at national and local level. This document is the activity report with the management and financial statements report of the Andra for the year 2006

Office of River Protection Advanced Low-Activity Waste Glass Research and Development Plan

International Nuclear Information System (INIS)

Kruger, A. A.; Peeler, D. K.; Kim, D. S.; Vienna, J. D.; Piepel, G. F.; Schweiger, M. J.

2015-01-01

The U.S. Department of Energy Office of River Protection (ORP) has initiated and leads an integrated Advanced Waste Glass (AWG) program to increase the loading of Hanford tank wastes in glass while meeting melter lifetime expectancies and process, regulatory, and product performance requirements. The integrated ORP program is focused on providing a technical, science-based foundation for making key decisions regarding the successful operation of the Hanford Tank Waste Treatment and Immobilization Plant (WTP) facilities in the context of an optimized River Protection Project (RPP) flowsheet. The fundamental data stemming from this program will support development of advanced glass formulations, key product performance and process control models, and tactical processing strategies to ensure safe and successful operations for both the low-activity waste (LAW) and high-level waste vitrification facilities. These activities will be conducted with the objective of improving the overall RPP mission by enhancing flexibility and reducing cost and schedule.

Office of River Protection Advanced Low-Activity Waste Glass Research and Development Plan

Energy Technology Data Exchange (ETDEWEB)

Kruger, A. A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Peeler, D. K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Kim, D. S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Vienna, J. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Piepel, G. F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Schweiger, M. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-11-23

The U.S. Department of Energy Office of River Protection (ORP) has initiated and leads an integrated Advanced Waste Glass (AWG) program to increase the loading of Hanford tank wastes in glass while meeting melter lifetime expectancies and process, regulatory, and product performance requirements. The integrated ORP program is focused on providing a technical, science-based foundation for making key decisions regarding the successful operation of the Hanford Tank Waste Treatment and Immobilization Plant (WTP) facilities in the context of an optimized River Protection Project (RPP) flowsheet. The fundamental data stemming from this program will support development of advanced glass formulations, key product performance and process control models, and tactical processing strategies to ensure safe and successful operations for both the low-activity waste (LAW) and high-level waste vitrification facilities. These activities will be conducted with the objective of improving the overall RPP mission by enhancing flexibility and reducing cost and schedule.

The Remote Handled Immobilization Low Activity Waste Disposal Facility Environmental Permits & Approval Plan

Energy Technology Data Exchange (ETDEWEB)

DEFFENBAUGH, M.L.

2000-08-01

The purpose of this document is to revise Document HNF-SD-ENV-EE-003, ''Permitting Plan for the Immobilized Low-Activity Waste Project, which was submitted on September 4, 1997. That plan accounted for the interim storage and disposal of Immobilized-Low Activity Waste at the existing Grout Treatment Facility Vaults (Project W-465) and within a newly constructed facility (Project W-520). Project W-520 was to have contained a combination of concrete vaults and trenches. This document supersedes that plan because of two subsequent items: (1) A disposal authorization that was received on October 25, 1999, in a U. S. Department of Energy-Headquarters, memorandum, ''Disposal Authorization Statement for the Department of Energy Hanford site Low-Level Waste Disposal facilities'' and (2) ''Breakthrough Initiative Immobilized Low-Activity Waste (ILAW) Disposal Alternative,'' August 1999, from Lucas Incorporated, Richland, Washington. The direction within the U. S. Department of Energy-Headquarters memorandum was given as follows: ''The DOE Radioactive Waste Management Order requires that a Disposal authorization statement be obtained prior to construction of new low-level waste disposal facility. Field elements with the existing low-level waste disposal facilities shall obtain a disposal authorization statement in accordance with the schedule in the complex-wide Low-Level Waste Management Program Plan. The disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate CERCLA documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. A disposal authorization statement is a part of the required radioactive waste management basis for a disposal facility. Failure to obtain a disposal authorization statement

A Joule-Heated Melter Technology For The Treatment And Immobilization Of Low-Activity Waste

International Nuclear Information System (INIS)

Kelly, S.E.

2011-01-01

This report is one of four reports written to provide background information regarding immobilization technologies remaining under consideration for supplemental immobilization of Hanford's low-activity waste. This paper provides the reader a general understanding of joule-heated ceramic lined melters and their application to Hanford's low-activity waste.

Electrochemical ion-exchange for active liquid waste treatment

International Nuclear Information System (INIS)

Turner, A.D.; Bridger, N.J.; Jones, C.P.

1992-10-01

Electrochemical ion exchange (EIX) has been firmly established as an effective process for the treatment of a wide range of liquid radioactive wastes. Both organic (for low specific activity streams) and inorganic systems (for higher activity wastes) have been demonstrated. A low cost current feeder electrode has also been developed, with a projected lifetime of > 6 years. While cation EIX can be used for the treatment of low salt content streams, combination with anion EIX to control the pH can extend its range of application. At the same time, it is also able to remove activity complexed in an anionic form. AEIX has also demonstrated its ability to remove radionuclides with insoluble hydroxides (eg Co, U and Pu) from both high and low salt content streams. EIX has been successfully scaled-up form the bench-top scale by increasing electrode size by a factor of 11, and then by operating five units in parallel. An improvement in performance of by a factor 3 was observed over a simple increase in area, due to the minimization of edge effects in the larger units. The most significant advantage of EIX is its compactness -with plant sizes of 1000). (Author)

Quantitative analysis of impact of awareness-raising activities on organic solid waste separation behaviour in Balikpapan City, Indonesia.

Science.gov (United States)

Murase, Noriaki; Murayama, Takehiko; Nishikizawa, Shigeo; Sato, Yuriko

2017-10-01

Many cities in Indonesia are under pressure to reduce solid waste and dispose of it properly. In response to this pressure, the Japan International Cooperation Agency and the Indonesian Government have implemented a solid waste separation and collection project to reduce solid waste in the target area (810 households) of Balikpapan City. We used a cluster randomised controlled trial method to measure the impact of awareness-raising activities that were introduced by the project on residents' organic solid waste separation behaviour. The level of properly separated organic solid waste increased by 6.0% in areas that conducted awareness-raising activities. Meanwhile, the level decreased by 3.6% in areas that did not conduct similar activities. Therefore, in relative comparison, awareness-raising increased the level by 9.6%. A comparison among small communities in the target area confirmed that awareness-raising activities had a significant impact on organic solid waste separation. High frequencies of monitoring at waste stations and door-to-door visits by community members had a positive impact on organic solid waste separation. A correlation between the proximity of environmental volunteers' houses to waste stations and a high level of separation was also confirmed. The awareness-raising activities introduced by the project led to a significant increase in the separation of organic solid waste.

Development for low-activation concrete design reducing radioactive waste

International Nuclear Information System (INIS)

Kimura, Ken-ichi; Kinno, Masaharu; Hasegawa, Akira

2008-01-01

Full text: Concrete is very valuable and inexpensive material, however it can be changed to be expensive and hard to deal with in use of a nuclear plant after long operation. One of the counter plans for the above is to use low-activation concrete instead of the ordinary concrete, that will reduce radioactive waste and could be even below clearance level in decommissioning and that is very useful in term of life cycle cost. Radioactive analysis showed that Co and Eu were the major target elements which decide the radioactivity level of reinforced concrete in decommissioning stage, and a several material were selected as a low-activation raw material from wide survey of raw materials for concrete (typically aggregates and cements). With the canditate of raw materials, several low-activation concrete were proposed for various portion of light water reactor plant, which reduction ratio were 1/10 to 1/30 which were mainly consist of limestone and low heat cement or white cement, and 1/100 to 1/300 which were mainly consist of alumina aggregate or quartz and high almina cement, comparing to the ordinary concrete in ΣDi/Ci unit, where 'Di' indicates concentration of each residual radioisotope, Ci defined by IAEA as a clearance level, and suffition of 'i' indicates each radioisotope. National funded project for development of low-activation design method for reduction of radioactive waste below clearance level were started from 2005 with aiming (1) development of a database on the content of target elements, which transform radioactive nuclides, in raw materials of reinforced concrete, (2) development of calculation tools for estimation of residual radioactivity of plant components, and (3) development of low-activation materials for concrete such as cements and reinforcing steel bars for structural components. For the optimized design for applying low-activation concrete to the reactor portion, effective evaluation of neutron spectrum in the certain portion including

SWEPP PAN assay system uncertainty analysis: Active mode measurements of solidified aqueous sludge waste

International Nuclear Information System (INIS)

Blackwood, L.G.; Harker, Y.D.; Meachum, T.R.

1997-12-01

The Idaho National Engineering and Environmental Laboratory is being used as a temporary storage facility for transuranic waste generated by the US Nuclear Weapons program at the Rocky Flats Plant (RFP) in Golden, Colorado. Currently, there is a large effort in progress to prepare to ship this waste to the Waste Isolation Pilot Plant (WIPP) in Carlsbad, New Mexico. In order to meet the TRU Waste Characterization Quality Assurance Program Plan nondestructive assay compliance requirements and quality assurance objectives, it is necessary to determine the total uncertainty of the radioassay results produced by the Stored Waste Examination Pilot Plant (SWEPP) Passive Active Neutron (PAN) radioassay system. This paper is one of a series of reports quantifying the results of the uncertainty analysis of the PAN system measurements for specific waste types and measurement modes. In particular this report covers active mode measurements of weapons grade plutonium-contaminated aqueous sludge waste contained in 208 liter drums (item description codes 1, 2, 7, 800, 803, and 807). Results of the uncertainty analysis for PAN active mode measurements of aqueous sludge indicate that a bias correction multiplier of 1.55 should be applied to the PAN aqueous sludge measurements. With the bias correction, the uncertainty bounds on the expected bias are 0 ± 27%. These bounds meet the Quality Assurance Program Plan requirements for radioassay systems

Derivation of activity limits for the disposal of radioactive waste in near surface disposal facilities

International Nuclear Information System (INIS)

2003-12-01

criteria for disposal of radioactive wastes to near surface facilities. These criteria are qualitative in nature and, for example, they do not address limitations on radionuclide content of waste, waste packages or the facility as a whole. This publication is to present an approach for establishing radiological waste acceptance criteria using a safety assessment methodology and to illustrate its application in establishing limits on the total activity and the activity concentrations of radioactive waste to be disposed in near surface disposal facilities. The approach makes use of accepted methods and computational schemes currently used in assessing the safety of near surface disposal facilities both during the operational and post-closure periods. The scope of this publication covers the use of safety assessment methodology to calculate total and specific activities limits for radioactive waste in near surface disposal facilities. It is used to evaluate the potential operational and post-closure radiological impact of solid and solidified radioactive waste in near surface facilities. The radioactive waste types used to illustrate the approach range from waste containing radionuclides used for medical, industrial and research purposes to waste arising from nuclear fuel cycle activities. They also include waste arising from the decommissioning of nuclear facilities. The focus of the publication is on using of safety assessment methodology in derivation of quantitative radioactivity limits. This report deals with the role of activity limits in disposal system safety (Section 2), the relevant radiation protection criteria (Section 3), the approach to derive activity limits (Section 4), illustrations of the application of this approach (Section 5), and guidance on the use of the approach (Section 6)

Technical basis for classification of low-activity waste fraction from Hanford site tanks

Energy Technology Data Exchange (ETDEWEB)

Petersen, C.A., Westinghouse Hanford

1996-07-17

The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level wastes, for disposal in a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

Technical basis for classification of low-activity waste fraction from Hanford site tanks

Energy Technology Data Exchange (ETDEWEB)

Petersen, C.A.

1996-09-20

The overall objective of this report is to provide a technical basis to support a U.S. Nuclear Regulatory Commission determination to classify the low-activity waste from the Hanford Site single-shell and double-shell tanks as `incidental` wastes after removal of additional radionuclides and immobilization.The proposed processing method, in addition to the previous radionuclide removal efforts, will remove the largest practical amount of total site radioactivity, attributable to high-level waste, for disposal is a deep geologic repository. The remainder of the waste would be considered `incidental` waste and could be disposed onsite.

Grading of Requirements for Radioactive Waste Activities in Nuclear Research Reactors: Radioisotope Production Facilities

International Nuclear Information System (INIS)

Tawfik, Y.E.

2017-01-01

A graded approach is applicable in all stages of the life time of a research reactor. During the life time of a research reactor, any grading performed should not, in any manner, affect safety functions and operational limits and conditions are preserved, so that there are no undue radiological hazards to workers, public or environment. The grading of activities should be based on safety analyses, and regulatory requirements. Other elements to be considered in grading are the complexity and the maturity of the technology, operating experience associated with the activities and the stage in the life time of the facility. In order to ensure that proper and a de quate provision is made for the safety implications associated with the management and disposal of radioactive waste, the waste is characterized and classified. The general scheme for classifying radioactive waste as presented in the current study is based on considerations of long term safety, and thus, by implication, disposal of the waste. This classification provides a starting point for the grading of activities associated with the packaging and disposal of radioactive waste

The Activities of Nuclear Training Centre Ljubljana in the Area of Radioactive Waste Management

International Nuclear Information System (INIS)

Jencic, I.

2006-01-01

Nuclear Training Centre Ljubljana has several activities related to radioactive waste management. These activities include training of professionals in the area of nuclear physics and nuclear technology, radiation protection courses, organization of international courses and workshops in the area of radioactive waste management, and public information on radioactivity and waste management. The paper will describe the specifics and the extent of training related to radioactive waste. Recently we have participated in a European coordination action CETRAD and an overview of the results of this project will also be presented. Very important component of our activity is public information that is based on an information centre and live lectures to organized groups of visitors, mostly schoolchildren. About one half of one school generation of Slovenia visits the Information centre every year. A poll is conducted among visitors every year and its results are a very useful tool to follow the evolution of public opinion on nuclear energy and radioactive waste disposal. The latter is, at least in Slovenia, still considered as the major obstacle against the use of nuclear energy. (authors)

The Remote Handled Immobilization Low-Activity Waste Disposal Facility Environmental Permits and Approval Plan

International Nuclear Information System (INIS)

DEFFENBAUGH, M.L.

2000-01-01

The purpose of this document is to revise Document HNF-SD-ENV-EE-003, ''Permitting Plan for the Immobilized Low-Activity Waste Project, which was submitted on September 4, 1997. That plan accounted for the interim storage and disposal of Immobilized-Low Activity Waste at the existing Grout Treatment Facility Vaults (Project W-465) and within a newly constructed facility (Project W-520). Project W-520 was to have contained a combination of concrete vaults and trenches. This document supersedes that plan because of two subsequent items: (1) A disposal authorization that was received on October 25, 1999, in a U. S. Department of Energy-Headquarters, memorandum, ''Disposal Authorization Statement for the Department of Energy Hanford site Low-Level Waste Disposal facilities'' and (2) ''Breakthrough Initiative Immobilized Low-Activity Waste (ILAW) Disposal Alternative,'' August 1999, from Lucas Incorporated, Richland, Washington. The direction within the U. S. Department of Energy-Headquarters memorandum was given as follows: ''The DOE Radioactive Waste Management Order requires that a Disposal authorization statement be obtained prior to construction of new low-level waste disposal facility. Field elements with the existing low-level waste disposal facilities shall obtain a disposal authorization statement in accordance with the schedule in the complex-wide Low-Level Waste Management Program Plan. The disposal authorization statement shall be issued based on a review of the facility's performance assessment and composite analysis or appropriate CERCLA documentation. The disposal authorization shall specify the limits and conditions on construction, design, operations, and closure of the low-level waste facility based on these reviews. A disposal authorization statement is a part of the required radioactive waste management basis for a disposal facility. Failure to obtain a disposal authorization statement or record of decision shall result in shutdown of an operational

Remedial investigation report on Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 4: Appendix C, Risk assessment

International Nuclear Information System (INIS)

1995-03-01

Waste Area Grouping (WAG) 5 is part of Oak Ridge National Laboratory (ORNL) and is located on the United States Department of Energy's Oak Ridge Reservation (DOE-ORR). The site lies southeast of Haw Ridge in Melton Valley and comprises approximately 32 ha (80 ac) [12 ha (30 ac) of forested area and the balance in grassed fields]. The western and southern boundaries of WAG are contiguous with the WAG 2 area which includes White Oak Creek and Melton Branch and associated floodplains. Waste Area Grouping 5 consists of several contaminant source areas for the disposal of low-level radioactive, transuranic (TRU), and fissile wastes (1959 to 1973) as well as inorganic and organic chemical wastes. Wastes were buried in trenches and auger holes. Radionuclides from buried wastes are being transported by shallow groundwater to Melton Branch and White Oak Creek. Different chemicals of potential concern (COPCS) were identified (e.g., cesium-137, strontium-90, radium-226, thorium-228, etc.); other constituents and chemicals, such as vinyl chloride, bis(2-ethylhexyl)phthalate, trichloroethene, were also identified as COPCS. Based on the results of this assessment contaminants of concern (COCS) were subsequently identified. The human health risk assessment methodology used in this risk assessment is based on Risk Assessment Guidance for Superfund (RAGS) (EPA 1989). First, the data for the different media are evaluated to determine usability for risk assessment. Second, through the process of selecting COPCS, contaminants to be considered in the BHHRA are identified for each media, and the representative concentrations for these contaminants are determined. Third, an assessment of exposure potential is performed, and exposure pathways are identified. Subsequently, exposure is estimated quantitatively, and the toxicity of each of the COPCs is determined. The results of the exposure and toxicity assessments are combined and summarized in the risk characterization section

Will vitrified high active reactor waste be deposited on the seabed

International Nuclear Information System (INIS)

Koksvik, R.M.

1978-01-01

The NRPB in the UK has carried out a preliminary study on the consequences of the disposal of high active waste on the ocean bed at great depths. This is reported in 'Assessment of the radiological protection aspects of disposal of high level waste on the ocean floor', by P.D. Grimswood and G.A.M. Webb (NRPB-R 48). This report is here briefly summarised and commented on. It deals with the radiological consequences to man of the erosion and corrosion of glassified (vitrified) radioactive waste, in the deep (>4000m) ocean, radionuclide migration and path ways to man. The conclusion is that considerations of radiological protection do not preclude the disposal of specially treated radioactive waste on the ocean bed. (JIW)

Californium-252 neutron activation analysis of high-level processed nuclear tank waste

International Nuclear Information System (INIS)

Troyer, G.L.; Purcell, M.A.

2000-01-01

The basis for production assessment of the vitrification of Hanford nuclear fuel reprocessing wastes will be high-precision measurements of the elemental sodium content. However, the chemical analysis of both radioactive and nonradioactive components in nuclear waste can be challenged by high radiation dose rates. The dose rates compromise many analytical techniques as well as pose personnel dosimetry risks. In many cases, reduction of dose rates through dilution compromises the precision and sensitivity for certain key components. The use of neutron activation analysis (NAA) provides a method of analysis that avoids the need for dilutions or extensive sample preparation. These waste materials also contain trace quantities of fissionable isotopes, which, through neutron activation, can be estimated by delayed neutron counting of fissioned fragments

The potential significance of microbial activity in radioactive waste disposal

International Nuclear Information System (INIS)

McCabe, A.M.

1987-12-01

The aim of this report is to assess the potential significance of microbial activity in radioactive waste disposal. It outlines the major factors which need to be considered in order to evaluate the importance of microbiological action. These include water and nutritional sources (particularly carbon) hostile conditions (particularly the effects of radiation and pH), the establishment of pH micro-environments and the degradative effect of microbial metabolic by-products on the disposed waste forms. Before an active microbial population can develop there are certain basic requirements for life. These are outlined and the possibility of colonisation occurring within the chemical, radiological and nutritional constraints of a repository are considered. Once colonisation is assumed, the effect of microbial activity is discussed under five headings, i.e. (i) direct attack, (ii) physical disruption (which includes consideration of fissuring processes and void formation), (iii) gas generation (which may be of particular importance), (iv) radionuclide uptake and finally (v) alteration of groundwater chemistry. Particular attention is paid to the possibility of environments becoming established both within the waste form itself (allowing microbes to attack from the inside of the repository outward) or attack on the encapsulant materials (microbes attacking from the outside inward). (author)

Characterization of silicoaluminates for low and medium activity wastes packaging

International Nuclear Information System (INIS)

Rivoallan, A.; Berson, X.

1996-01-01

Studies are done in order to demonstrate many advantages (as an important volume reduction and a greater chemical stability) of packaging low and medium activity wastes in crystal structures compared with concrete and bitumen. In order to understand the consequences of hazardous chemical composition (especially anions) in the waste on the characteristics of the mineral packaging, a simulation study is developed with inactive concentrates. It leads to well crystallized structures which have not the same major crystallized phase. (authors)

Effects of ozonation on disinfection and microbial activity in waste activated sludge for land application

Energy Technology Data Exchange (ETDEWEB)

Ahn, Kyu-Hong; Maeng, Sung Kyu; Hong, Jun-Seok; Lim, Byung-Ran

2003-07-01

Effects of ozonation on microbial biomass activity and community structure in waste activated sludges from various treatment plants were investigated. The densities of viable cells and microbial community structure in the sludges treated with ozone at 0.1, 0.2 and 0.4 gO{sub 3}/gDS were measured on the basis of the respiratory quinone profile and LIVE/DEAD Backlight(TM). The results from the bacterial concentration and quinone profiles of the waste activated sludge showed that respiratory activities of microorganisms were detected at the ozone dose of 0.4 gO{sub 3}/gDS. However, fecal coliform, fecal streptococcus and Salmonella sp. in the ozonized sludge were not detected. This result implies that some microorganisms might be more tolerant to ozonation than the pathogenic indicators. The pathogens reduction requirements for Class A biosolids were still met by the ozonation at 0.4 gO{sub 3}/gDS.

A JOULE-HEATED MELTER TECHNOLOGY FOR THE TREATMENT AND IMMOBILIZATION OF LOW-ACTIVITY WASTE

Energy Technology Data Exchange (ETDEWEB)

KELLY SE

2011-04-07

This report is one of four reports written to provide background information regarding immobilization technologies remaining under consideration for supplemental immobilization of Hanford's low-activity waste. This paper provides the reader a general understanding of joule-heated ceramic lined melters and their application to Hanford's low-activity waste.

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

Status on the regulatory aspects in NORM/TENORM activities and waste in Malaysia

International Nuclear Information System (INIS)

Hassan, Hasmadi

2005-01-01

In Malaysia, waste associated with TENORM are generated mostly in the tin mining and smelting, processing of minerals, and oil and gas industry. As one of a major tin producer in the world and the country current activities in oil production, the amount of waste generated in this kind of activities is quite substantial. Currently the government of Malaysia did not provide any provision in the law specifically for the exclusion of TENORM waste, however, the government did imposed the criteria for exclusion of this waste by adopting the guideline limit established by the IAEA safety series 26, which is very vital for the regulatory body i.e. Atomic Energy Licensing Board (AELB) to overcome the problems in managing some of waste related to TENORM industries. As one example, this guideline has been applied to one of the mineral processing industries in the country on decommissioning and disposing of their waste. Furthermore, due to economic reason and price of tin and its by-product is not viable and profitable so much, making this industry not significant in business and trade industries, several practices have been exempted from the regulatory control under the Atomic Energy Licensing Act, 1984. (author)

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.

An overview of the hazardous waste remedial actions program: hazardous and mixed waste activities for the U.S. Departments of energy and defense

International Nuclear Information System (INIS)

Craig, Robert B.; Rothermich, Nancy E.

1991-01-01

In May 1987 all mixed waste generated at the U.S. Department of Energy (DOE) facilities became jointly regulated by the U.S. Environmental Protection Agency (EPA) and DOE. The Department of Defense (DOD) generates hazardous wastes and is also regulated by the EPA. To maintain or attain compliance, both DOE and DOD have initiated compliance activities on all hazardous and mixed waste streams. This compliance includes the development of innovative technologies and processes to avoid the generation of hazardous and mixed wastes, development of technologies to treat the process wastes that are unavoidably generated, development of technologies to restore the environment where wastes have been released to the environment, the cleanup of asbestos and the monitoring of radon in federal facilities, the completion of remedial investigation/feasibility studies, and development of the data systems that are necessary to compile this information. This paper will describe each of these activities as they relate to compliance with the Resource Conservation and Recovery Act and/or CERCLA and their implementing regulations

NDA Position on the UK Management of Waste Graphite (December 2013)

International Nuclear Information System (INIS)

Norris, S.

2016-01-01

The purpose of this paper is to summarise a number of pieces of work that have been undertaken by the Nuclear Decommissioning Authority (NDA) to better understand the challenges of managing radioactive graphite wastes, these have led to an updated strategic position on graphite waste management. The updated strategic position takes into consideration Government’s response to Recommendation 8 from the Committee on Radioactive Waste Management’s (CoRWM), and provides the current NDA strategic position alongside circumstances where this should be reviewed. Two studies that provided input to this position are: 1. Operational Graphite Management Strategy: Credible and Preferred Options (Gate A & B); 2. The Long-term Management of Reactor Core Graphite Waste: Credible Options (Gate A). The paper highlights the key findings from the following work that has been undertaken to better inform this position: • A review by the NDA Radioactive Waste Management Directorate (RWMD)1 of the current baseline for managing radioactive graphite in England and Wales of geological disposal. The review identified some areas for optimisation and provided clarification on some aspects of the baseline e.g. the assumed ‘footprint’ of graphite wastes for a future Geological Disposal Facility (GDF). • Investigations into suitability of near-surface disposal options for graphite wastes. This included a review of the Low Level Waste Repository (LLWR) Ltd's new Environmental Safety Case (ESC) to assess the potential for graphite disposal and a feasibility study into a near-surface disposal facility for Higher Activity Waste (HAW) graphite at the Hunterston A site. • Continued monitoring of potential future treatment options. • Detailed characterisation work under the NDA’s Direct Research Portfolio using computer modelling and sample analysis to better understand any limitations of the current inventory data for graphite wastes. • Graphite behaviour work under the NDA�

Immobilized low-activity waste site borehole 299-E17-21

International Nuclear Information System (INIS)

Reidel, S.P.; Reynolds, K.D.; Horton, D.G.

1998-08-01

The Tank Waste Remediation System (TWRS) is the group at the Hanford Site responsible for the safe underground storage of liquid waste from previous Hanford Site operations, the storage and disposal of immobilized tank waste, and closure of underground tanks. The current plan is to dispose of immobilized low-activity tank waste (ILAW) in new facilities in the southcentral part of 200-East Area and in four existing vaults along the east side of 200-East Area. Boreholes 299-E17-21, B8501, and B8502 were drilled at the southwest corner of the ILAW site in support of the Performance Assessment activities for the disposal options. This report summarizes the initial geologic findings, field tests conducted on those boreholes, and ongoing studies. One deep (480 feet) borehole and two shallow (50 feet) boreholes were drilled at the southwest corner of the ILAW site. The primary factor dictating the location of the boreholes was their characterization function with respect to developing the geohydrologic model for the site and satisfying associated Data Quality Objectives. The deep borehole was drilled to characterize subsurface conditions beneath the ILAW site, and two shallow boreholes were drilled to support an ongoing environmental tracer study. The tracer study will supply information to the Performance Assessment. All the boreholes provide data on the vadose zone and saturated zone in a previously uncharacterized area

Wastes from former mining and milling activities in Tajikistan

International Nuclear Information System (INIS)

Mirsaidov, U.M.

2012-01-01

This article is devoted to wastes from former mining and milling activities in Tajikistan. Currently, the serious radiological and ecological problems in Tajikistan are uranium mining and milling activities consequences overcoming which intensively developed during the soviet period. After the collapse of USSR, the uranic ores extraction in Tajikistan stopped due to deposit's output completion on the territory of the republic. Remediation of mining and milling activities' sites became the most urgent once all mines were closed.

Behavior of ruthenium, cesium and antimony in high temperature processes for waste conditioning

International Nuclear Information System (INIS)

Klein, M.; Weyers, C.; Goossens, W.R.A.

1985-01-01

The fission products and the actinides of high level radioactive liquid wastes can be immobilized by incorporation into a glass matrix prior to disposal. The behaviour of so-called semi-volatile products during the vitrification process has been studied by the C.E.N./S.C.K. in Mol since 1979 in the framework of a contract with DWK of Germany in support to the HAW technological program PAMELA. The experiments were performed on laboratory and semi-pilot scale using simulated LEWC solutions tagged with radioisotopes of three suspected volatile fission products, namely ruthenium, cesium and antimony. The releases of these semi-volatile compounds to the off-gases have been investigated for a liquid fed melter as a function of the operational conditions. The study of a wet purification system, comprising in series of a dust scrubber, a condensor, an ejector venturi and an NOsub(x) column, has shown that cesium appears to be the reference isotope for the volatile elements released from the melter. Ruthenium seems not to be a problem from the point of view of gas purification although local radiation problems caused by deposits on metal surfaces cannot be excluded. (Auth.)

Categorisation of waste streams arising from the operation of a low active waste incinerator and justification of discharge practices

International Nuclear Information System (INIS)

Richards, J.M.

1989-01-01

Waste streams arising from the low active waste incinerator at Harwell are described, and the radiological impact of each exposure pathway discussed. The waste streams to be considered are: (i) discharge of scrubber liquors after effluent treatment to the river Thames; (ii) disposal of incinerator ash; and (iii) discharge of airborne gaseous effluents to the atmosphere. Doses to the collective population and critical groups as a result of the operation of the incinerator are assessed and an attempt made to justify the incineration practice by consideration of the radiological impact and monetary costs associated with alternative disposal methods. (author)

Supplemental Immobilization of Hanford Low-Activity Waste: Cast Stone Screening Tests

Energy Technology Data Exchange (ETDEWEB)

Westsik, Joseph H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Piepel, Gregory F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lindberg, Michael J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Heasler, Patrick G. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Mercier, Theresa M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Russell, Renee L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Cozzi, Alex [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Daniel, William E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Eibling, Russell E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Hansen, E. K. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Reigel, Marissa M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Swanberg, David J. [Washington River Protection Solutions (WRPS), Aiken, SC (United States)

2013-09-30

More than 56 million gallons of radioactive and hazardous waste are stored in 177 underground storage tanks at the U.S. Department of Energy’s (DOE’s) Hanford Site in southeastern Washington State. The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the wastes and immobilize them in a glass waste form. The WTP includes a pretreatment facility to separate the wastes into a small volume of high-level waste (HLW) containing most of the radioactivity and a larger volume of low-activity waste (LAW) containing most of the nonradioactive chemicals. The HLW will be converted to glass in the HLW vitrification facility for ultimate disposal at an offsite federal repository. At least a portion (~35%) of the LAW will be converted to glass in the LAW vitrification facility and will be disposed of onsite at the Integrated Disposal Facility (IDF). The pretreatment and HLW vitrification facilities will have the capacity to treat and immobilize the wastes destined for each facility. However, a second LAW immobilization facility will be needed for the expected volume of LAW requiring immobilization. A cementitious waste form known as Cast Stone is being considered to provide the required additional LAW immobilization capacity. The Cast Stone waste form must be acceptable for disposal in the IDF. The Cast Stone waste form and immobilization process must be tested to demonstrate that the final Cast Stone waste form can comply with the waste acceptance criteria for the disposal facility and that the immobilization processes can be controlled to consistently provide an acceptable waste form product. Further, the waste form must be tested 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 risk assessment and performance assessment (PA) analyses of the long-term environmental impact of the waste disposal in the IDF

Direction in charge of the management of wastes. 1998 activity report

International Nuclear Information System (INIS)

1998-01-01

This document is the 1998 activity report of the direction in charge of the management of radioactive wastes (DGD) of the French atomic energy commission (CEA). The role of the DGD is the elimination of radioactive wastes, the management of spent fuels, the cleansing and dismantling of shut-down and decommissioned installations at the CEA. This report summarizes the highlights of the 1998 year: the cleansing plan of the CEA (current policy, plan scheme, quality assurance, financing, public relation); the radioactive wastes (general considerations, management of liquid and solid effluents, management of sealed sources, modernization of equipments and new projects, relations with the Andra, studies in progress); the spent fuels (general considerations, solutions, long-term storage); the dismantling of shut-down installations (general considerations about decommissioning, dismantling actions at the CEA, main works performed, dismantling actions in progress); the management of wastes at the CEA-direction for military applications (DAM); the cleansing of the CEA-Marcoule site; 1998 status of the management of wastes (appendix). (J.S.)

Aerobic composting of waste activated sludge: Kinetic analysis for microbiological reaction and oxygen consumption

International Nuclear Information System (INIS)

Yamada, Y.; Kawase, Y.

2006-01-01

In order to examine the optimal design and operating parameters, kinetics for microbiological reaction and oxygen consumption in composting of waste activated sludge were quantitatively examined. A series of experiments was conducted to discuss the optimal operating parameters for aerobic composting of waste activated sludge obtained from Kawagoe City Wastewater Treatment Plant (Saitama, Japan) using 4 and 20 L laboratory scale bioreactors. Aeration rate, compositions of compost mixture and height of compost pile were investigated as main design and operating parameters. The optimal aerobic composting of waste activated sludge was found at the aeration rate of 2.0 L/min/kg (initial composting mixture dry weight). A compost pile up to 0.5 m could be operated effectively. A simple model for composting of waste activated sludge in a composting reactor was developed by assuming that a solid phase of compost mixture is well mixed and the kinetics for microbiological reaction is represented by a Monod-type equation. The model predictions could fit the experimental data for decomposition of waste activated sludge with an average deviation of 2.14%. Oxygen consumption during composting was also examined using a simplified model in which the oxygen consumption was represented by a Monod-type equation and the axial distribution of oxygen concentration in the composting pile was described by a plug-flow model. The predictions could satisfactorily simulate the experiment results for the average maximum oxygen consumption rate during aerobic composting with an average deviation of 7.4%

ANDRA - National Radioactive Waste Management Agency. 2014 Activity report - Responsibility in action. Financial report 2014

International Nuclear Information System (INIS)

2015-01-01

Created in 1979 within the CEA, the National Radioactive Waste Management Agency (ANDRA) was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act: - a R and D mission to propose safe long-term solution for radioactive waste without current disposal system; this mission includes long-term storage, since the 2006 Planning Act, in order to propose interim solutions while final ones are being studied; - an industrial mission concerning, on one hand, waste acceptance criteria and control and, on the other hand, siting, construction, operation, closure and monitoring of repositories. This mission includes as well a public service mission in terms of i) collection of waste of the 'small-scale nuclear activities' producers or owners (including the so-called 'household' radioactive waste, i.e. waste owned by private individuals) and ii) clean-up and rehabilitation of orphan polluted sites; - an information mission, notably through the regular publication of the National Inventory of radioactive materials and waste. This mission includes as well an active policy of dialogue with stakeholders both at national and local level. This document is the activity and financial report of the Andra for the year 2014

ANDRA - National Radioactive Waste Management Agency. Activity report and sustainable development 2013. Financial report 2013

International Nuclear Information System (INIS)

2014-01-01

Created in 1979 within the CEA, the National Radioactive Waste Management Agency (ANDRA) was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act: - a R and D mission to propose safe long-term solution for radioactive waste without current disposal system; this mission includes long-term storage, since the 2006 Planning Act, in order to propose interim solutions while final ones are being studied; - an industrial mission concerning, on one hand, waste acceptance criteria and control and, on the other hand, siting, construction, operation, closure and monitoring of repositories. This mission includes as well a public service mission in terms of i) collection of waste of the 'small-scale nuclear activities' producers or owners (including the so-called 'household' radioactive waste, i.e. waste owned by private individuals) and ii) clean-up and rehabilitation of orphan polluted sites; - an information mission, notably through the regular publication of the National Inventory of radioactive materials and waste. This mission includes as well an active policy of dialogue with stakeholders both at national and local level. This document is the activity and Sustainable Development Report, with the financial report, of the Andra for the year 2013

Waste Treatment Technology Process Development Plan For Hanford Waste Treatment Plant Low Activity Waste Recycle

International Nuclear Information System (INIS)

McCabe, Daniel J.; Wilmarth, William R.; Nash, Charles A.

2013-01-01

The purpose of this Process Development Plan is to summarize the objectives and plans for the technology development activities for an alternative path for disposition of the recycle stream that will be generated in the Hanford Waste Treatment Plant Low Activity Waste (LAW) vitrification facility (LAW Recycle). This plan covers the first phase of the development activities. The baseline plan for disposition of this stream is to recycle it to the WTP Pretreatment Facility, where it will be concentrated by evaporation and returned to the LAW vitrification facility. Because this stream contains components that are volatile at melter temperatures and are also problematic for the glass waste form, they accumulate in the Recycle stream, exacerbating their impact on the number of LAW glass containers. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and reducing the halides in the Recycle is a key component of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, this stream does not have a proven disposition path, and resolving this gap becomes vitally important. This task seeks to examine the impact of potential future disposition of this stream in the Hanford tank farms, and to develop a process that will remove radionuclides from this stream and allow its diversion to another disposition path, greatly decreasing the LAW vitrification mission duration and quantity of glass waste. The origin of this LAW Recycle stream will be from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover or precipitates of scrubbed components (e.g. carbonates). The soluble

Waste Treatment Technology Process Development Plan For Hanford Waste Treatment Plant Low Activity Waste Recycle

Energy Technology Data Exchange (ETDEWEB)

McCabe, Daniel J.; Wilmarth, William R.; Nash, Charles A.

2013-08-29

The purpose of this Process Development Plan is to summarize the objectives and plans for the technology development activities for an alternative path for disposition of the recycle stream that will be generated in the Hanford Waste Treatment Plant Low Activity Waste (LAW) vitrification facility (LAW Recycle). This plan covers the first phase of the development activities. The baseline plan for disposition of this stream is to recycle it to the WTP Pretreatment Facility, where it will be concentrated by evaporation and returned to the LAW vitrification facility. Because this stream contains components that are volatile at melter temperatures and are also problematic for the glass waste form, they accumulate in the Recycle stream, exacerbating their impact on the number of LAW glass containers. Approximately 32% of the sodium in Supplemental LAW comes from glass formers used to make the extra glass to dilute the halides to acceptable concentrations in the LAW glass, and reducing the halides in the Recycle is a key component of this work. Additionally, under possible scenarios where the LAW vitrification facility commences operation prior to the WTP Pretreatment facility, this stream does not have a proven disposition path, and resolving this gap becomes vitally important. This task seeks to examine the impact of potential future disposition of this stream in the Hanford tank farms, and to develop a process that will remove radionuclides from this stream and allow its diversion to another disposition path, greatly decreasing the LAW vitrification mission duration and quantity of glass waste. The origin of this LAW Recycle stream will be from the Submerged Bed Scrubber (SBS) and the Wet Electrostatic Precipitator (WESP) from the LAW melter off-gas system. The stream is expected to be a dilute salt solution with near neutral pH, and will likely contain some insoluble solids from melter carryover or precipitates of scrubbed components (e.g. carbonates). The soluble

Radioactive Waste Management Program Activities in Croatia

International Nuclear Information System (INIS)

Matanic, R.

2000-01-01

The concept of radioactive waste management in Croatia comprises three major areas: management of low and intermediate level radioactive waste (LILRW), spent fuel management and decommissioning. All the work regarding radioactive waste management program is coordinated by Hazardous Waste Management Agency (APO) and Croatian Power Utility (HEP) in cooperation with other relevant institutions. Since the majority of work has been done in developing low and intermediate level radioactive waste management program, the paper will focus on this part of radioactive waste management, mainly on issues of site selection and characterization, repository design, safety assessment and public acceptance. A short description of national radioactive waste management infrastructure will also be presented. (author)

Laboratory optimization tests of technetium decontamination of Hanford Waste Treatment Plant low activity waste melter off-gas condensate simulant

Energy Technology Data Exchange (ETDEWEB)

Taylor-Pashow, Kathryn M.L. [Savannah River Site (SRS), Aiken, SC (United States); McCabe, Daniel J. [Savannah River Site (SRS), Aiken, SC (United States)

2015-11-01

The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility again. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable simplified operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of glass waste.

Participation of the ININ in the activities of radioactive waste management of the Laguna Verde Central

International Nuclear Information System (INIS)

Medrano L, M.; Rodriguez C, C.; Linares R, D.; Ramirez G, R.; Zarate M, N.

2006-01-01

From the beginning of the operation of the Laguna Verde Central (CLV) the National Institute of Nuclear Research (ININ) has come supporting the CLV in the activities of administration of the humid and dry radioactive waste generated by the operation of the two units of the CLV, from the elaboration of procedures to the temporary storage in site, the implementation of a program of minimization and segregation of dry solid wastes, until the classification of the lots of humid waste and bulk dry wastes. In this work the description of the management activities of radioactive wastes carried out by the ININ in the facilities of the CLV to the date is presented, as well as some actions that they are had drifted in the future near, among those that it stands out the determination of the total alpha activity in humid samples by means of scintillation analysis. (Author)

Report on the emergency response training and equipment activities through fiscal year 1992 for the transportation of transuranic waste to the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1992-11-01

The Waste Isolation Pilot Plant (WIPP) is a research and development facility with the mission of demonstrating the safe shipment, emplacement, and retrieval of radioactive transuranic (TRU) wastes resulting from the defense activities and programs of the United States. It is the only long-term storage facility constructed for TRU waste. This report provides the status on the Department of Energy (DOE) efforts as of September 30, 1992, regarding emergency response training provided to local, state, and tribal governments for waste shipments to the WIPP, as required by section 16(c)(1)(A) of the Waste Isolation Pilot Plant Land Withdrawal Act (Public Law 102-579). This is an update to the April 1992 report (DOE/WIPP 92003) which provided status through 1991. This report will be updated and issued annually. Because of a growing public awareness of transportation-activities involving nuclear materials, this report was prepared to provide a status of the DOE's activities in this regard, as well as the cooperative efforts between the DOE and state and tribal governments

Protocol for the quantification of greenhouse gas emissions from waste management activities

International Nuclear Information System (INIS)

2013-10-01

' document. The quantification of GHG emissions from waste management activities is a complex exercise. This Protocol is a living document which is going to evolve together with the improvement of calculation and measurement techniques. This Protocol is a tool for quantifying and reporting a greenhouse gas inventory from waste activities over a given time frame, typically a year. In this regard, the landfill methane emissions reported are only those estimated to be emitted in the given reporting year. The reported value does not include the future emissions resulting from the degradation of waste landfilled in and prior to the reporting year. Therefore, the reported landfill methane values based on this Protocol should not be used in the context of a comparison of greenhouse gas footprint of various waste technologies

Generation and management of solid waste resulting from tourist activities of the Porto de Galinhas - P

Directory of Open Access Journals (Sweden)

Jaqueline Guimarães Santos

2015-04-01

Full Text Available The significant solid waste generation, coupled with the lack of proper management of the waste generated, has been one of the issues of concern and conducting research on the part of scholars in the field. Tourism as an activity that positively impacts and negativity a given location, has emerged as an activity that can generate a lot of waste, especially in periods of high season, considering the increase of people moving to the tourist destinations. Accordingly, this study aims to analyze the generation and management of solid waste resulting from tourism in Porto de Galinhas, PE. We performed an exploratory, descriptive, qualitative study, conducted in the form of a case study in Porto de Galinhas, PE. The data collection was done interviews together social actors, as well as non-participant observation during data collection. The results showed that tourism activities in Porto de Galinhas result in a high amount of solid waste, and these are directed to inappropriate places. Although fate presents a combination of recyclable materials, RECYCLE, reuses this not a significant amount, given the proportion of waste generated.

Capability and limitation study of the DDT passive-active neutron waste assay instrument

International Nuclear Information System (INIS)

Nicholas, N.J.; Coop, K.L.; Estep, R.J.

1992-05-01

The differential-dieaway-technique passive-active neutron assay system is widely used by transuranic waste generators to certify their drummed waste for eventual shipment to the Waste Isolation Pilot Plant (WIPP). Stricter criteria being established for waste emplacement at the WIPP site has led to a renewed interest in improvements to and a better understanding of current nondestructive assay (NDA) techniques. Our study includes the effects of source position, extreme matrices, high neutron backgrounds, and source self-shielding to explore the system's capabilities and limitations and to establish a basis for comparison with other NDA systems. 11 refs

Biohydrogen production using waste activated sludge disintegrated by gamma irradiation

International Nuclear Information System (INIS)

Yin, Yanan; Wang, Jianlong

2015-01-01

Highlights: • The waste activated sludge could be disintegrated by gamma irradiation. • The disintegrated sludge could be used for biohydrogen production. • Combined alkali-irradiation treatment achieved the highest solubilization of sludge. - Abstract: The biohydrogen production using the disintegrated and dissolved sludge by gamma irradiation was studied. The experimental results showed that gamma irradiation and irradiation combined with alkali pretreatment could disintegrate and dissolve waste activated sludge for biohydrogen production. The alkali-irradiation treatment of the sludge at pH = 12 and 20 kGy achieved the highest disintegration and dissolution, i.e., it could destroy the cell walls and release organic matters (such as soluble COD, polysaccharides and protein) into the solution. The disintegrated sludge could be used as a low-cost substrate for biohydrogen production

Method and equipment for the treatment of low-activity wastes

International Nuclear Information System (INIS)

White, L.E.; Anderson, R.E.; Vander Wall, E.M.

1976-01-01

In nuclear power plants, large amounts of waste products of low activity occur. For simplifying the final storage, it seems reasonable to reduce this volume. It is suggested, therefore, to evaporate the liquids, to compress the remaining mass by sintering or melting, and to transform it into solid monolithic bodies. The solidification is said to be promoted by additives of plastics. A remote-controlled, fully automatical device is presented, containing a fluidized bed system, in which the volume of the waste substances is reduced to 10% of the initial volume. (UWI) [de

Artificial neural networks in the evaluation of the radioactive waste drums activity

International Nuclear Information System (INIS)

Potiens, J.R.A.J.; Hiromoto, G.

2006-01-01

The mathematical techniques are becoming more important to solve geometry and standard identification problems. The gamma spectrometry of radioactive waste drums would be a complex solution problem. The main difficulty is the detectors calibration for this geometry; the waste is not homogeneously distributed inside the drums, therefore there are many possible combinations between the activity and the position of these radionuclides inside the drums, making the preparation of calibration standards impracticable. This work describes the development of a methodology to estimate the activity of a 200 L radioactive waste drum, as well as a mapping of the waste distribution, using Artificial Neural Network. The neural network data set entry obtaining was based on the possible detection efficiency combination with 10 sources activities varying from 0 to 74 x 10 3 Bq. The set up consists of a 200 L drum divided in 5 layers. Ten detectors were positioned all the way through a parallel line to the drum axis, from 15 cm of its surface. The Cesium -137 radionuclide source was used. The 50 efficiency obtained values (10 detectors and 5 layers), combined with the 10 source intensities resulted in a 100,000 lines for 15 columns matrix, with all the possible combinations of source intensity and the Cs-137 position in the 5 layers of the drum. This archive was divided in 2 parts to compose the set of training: input and target files. The MatLab 7.0 module of neural networks was used for training. The net architecture has 10 neurons in the input layer, 18 in the hidden layer and 5 in the output layer. The training algorithm was the 'traincgb' and after 300 'epoch s' the medium square error was 0.00108172. This methodology allows knowing the detection positions answers in a heterogeneous distribution of radionuclides inside a 200 L waste drum; in consequence it is possible to estimate the total activity of the drum in the training neural network limits. The results accuracy depends

Data Packages for the Hanford Immobilized Low-Activity Tank Waste Performance Assessment: 2001 Version

International Nuclear Information System (INIS)

MANN, F.M.

2000-01-01

Data package supporting the 2001 Immobilized Low-Activity Waste Performance Analysis. Geology, hydrology, geochemistry, facility, waste form, and dosimetry data based on recent investigation are provided. Verification and benchmarking packages for selected software codes are provided

Comparison of soil heavy metal pollution caused by e-waste recycling activities and traditional industrial operations.

Science.gov (United States)

He, Kailing; Sun, Zehang; Hu, Yuanan; Zeng, Xiangying; Yu, Zhiqiang; Cheng, Hefa

2017-04-01

The traditional industrial operations are well recognized as an important source of heavy metal pollution, while that caused by the e-waste recycling activities, which have sprouted in some developing countries, is often overlooked. This study was carried out to compare the status of soil heavy metal pollution caused by the traditional industrial operations and the e-waste recycling activities in the Pearl River Delta, and assess whether greater attention should be paid to control the pollution arising from e-waste recycling activities. Both the total contents and the chemical fractionation of major heavy metals (As, Cr, Cd, Ni, Pb, Cu, and Zn) in 50 surface soil samples collected from the e-waste recycling areas and 20 soil samples from the traditional industrial zones were determined. The results show that the soils in the e-waste recycling areas were mainly polluted by Cu, Zn, As, and Cd, while Cu, Zn, As, Cd, and Pb were the major heavy metals in the soils from the traditional industrial zones. Statistical analyses consistently show that Cu, Cd, Pb, and Zn in the surface soils from both types of sites were contributed mostly by human activities, while As, Cr, and Ni in the soils were dominated by natural background. No clear distinction was found on the pollution characteristic of heavy metals in the surface soils between the e-waste recycling areas and traditional industrial zones. The potential ecological risk posed by heavy metals in the surface soils from both types of sites, which was dominated by that from Cd, ranged from low to moderate. Given the much shorter development history of e-waste recycling and its largely unregulated nature, significant efforts should be made to crack down on illegal e-waste recycling and strengthen pollution control for related activities.

Unravelling the protein preference of aquatic worms during waste activated sludge degradation

NARCIS (Netherlands)

de Valk, S.L.; Khadem, A.F.; van Lier, J.B.; de Kreuk, M.K.

2017-01-01

Worm predation (WP) by Tubifex tubifex was investigated using waste activated sludge (WAS) as the substrate. In order to better understand the sludge degradation mechanisms during WP, the activity of five common hydrolytic enzymes was determined and compared among the initial feed activated

Design requirements document for Project W-465, immobilized low-activity waste interim storage

International Nuclear Information System (INIS)

Burbank, D.A.

1998-01-01

The scope of this Design Requirements Document (DRD) is to identify the functions and associated requirements that must be performed to accept, transport, handle, and store immobilized low-activity waste (ILAW) produced by the privatized Tank Waste Remediation System (TWRS) treatment contractors. The functional and performance requirements in this document provide the basis for the conceptual design of the TWRS ILAW Interim Storage facility project and provides traceability from the program level requirements to the project design activity. Technical and programmatic risk associated with the TWRS planning basis are discussed in the Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The design requirements provided in this document will be augmented by additional detailed design data documented by the project

Solidification of highly active wastes

International Nuclear Information System (INIS)

Morris, J.B.

1984-11-01

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

DEVELOPMENT, QUALIFICATION, AND DISPOSAL OF AN ALTERNATIVE IMMOBILIZED LOW-ACTIVITY WASTE FORM AT THE HANFORD SITE

International Nuclear Information System (INIS)

Sams, T.L.; Edge, J.A.; Swanberg, D.J.; Robbins, R.A.

2011-01-01

Demonstrating that a waste form produced by a given immobilization process is chemically and physically durable as well as compliant with disposal facility acceptance criteria is critical to the success of a waste treatment program, and must be pursued in conjunction with the maturation of the waste processing technology. Testing of waste forms produced using differing scales of processing units and classes of feeds (simulants versus actual waste) is the crux of the waste form qualification process. Testing is typically focused on leachability of constituents of concern (COCs), as well as chemical and physical durability of the waste form. A principal challenge regarding testing immobilized low-activity waste (ILAW) forms is the absence of a standard test suite or set of mandatory parameters against which waste forms may be tested, compared, and qualified for acceptance in existing and proposed nuclear waste disposal sites at Hanford and across the Department of Energy (DOE) complex. A coherent and widely applicable compliance strategy to support characterization and disposal of new waste forms is essential to enhance and accelerate the remediation of DOE tank waste. This paper provides a background summary of important entities, regulations, and considerations for nuclear waste form qualification and disposal. Against this backdrop, this paper describes a strategy for meeting and demonstrating compliance with disposal requirements emphasizing the River Protection Project (RPP) Integrated Disposal Facility (IDF) at the Hanford Site and the fluidized bed steam reforming (FBSR) mineralized low-activity waste (LAW) product stream.

A Strategy for Maintenance of the Long-Term Performance Assessment of Immobilized Low-Activity Waste Glass

Energy Technology Data Exchange (ETDEWEB)

Ryan, Joseph V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Freedman, Vicky L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2016-09-28

Approximately 50 million gallons of high-level radioactive mixed waste has accumulated in 177 buried single- and double-shell tanks at the Hanford Site in southeastern Washington State as a result of the past production of nuclear materials, primarily for defense uses. The United States Department of Energy (DOE) is proceeding with plans to permanently dispose of this waste. Plans call for separating the tank waste into high-level waste (HLW) and low-activity waste (LAW) fractions, which will be vitrified at the Hanford Waste Treatment and Immobilization Plant (WTP). Principal radionuclides of concern in LAW are 99Tc, 129I, and U, while non-radioactive contaminants of concern are Cr and nitrate/nitrite. HLW glass will be sent off-site to an undetermined federal site for deep geological disposal while the much larger volume of immobilized low-activity waste will be placed in the on-site, near-surface Integrated Disposal Facility (IDF).

Chemical activation of tea waste and use for the removal of chromium (Vi) from aqueous solution

International Nuclear Information System (INIS)

Qureshi, K.; Bhatti, I.; Ansari, A.K.

2009-01-01

Tea waste is the residue left after the preparation of tea. At present the tea waste is regarded as a waste product having no use. In this study, tea waste is converted into an adsorbent. Tea waste is chemically activated with phosphoric acid at low temperature 450 degree C. This activated carbon is then utilized as an adsorbent for the removal of Chromium (VI) from aqueous solution. The various sorption parameters i.e pH, sorbent dose sorbate concentration, shaking time and shaking speed are first optimized. 75% of chromium from aqueous solution is effectively removed at pH 2. The best optimum conditions were obtained when 1 gm of sorbent was agitated at 100 rpm with 60 mg/l of sorbate for 50 minutes. Better results were obtained when low concentrations of sorbates were used. Hence tea waste could also be successfully used for the sorption of Chromium (VI), from industrial waste water. (author)

Study of scenarios of long term management of low-activity long-life wastes

International Nuclear Information System (INIS)

2012-01-01

This document reports the study of scenarios for the management of different low-activity long-life radioactive wastes with reference to different French legal texts. After a presentation of the legal and technical context, the report presents different existing and projected storages (description and safety principles for the Cires and Aube centres and for the Cigeo project of deep geological storage centre). It addresses the various aspects of radiferous and graphite waste management on a long term: inventory, parcel, waste peculiarities, management scenarios, assessment of storage in SCR. It also addresses the case of other wastes such as bituminous coated wastes, those presenting a reinforced natural radioactivity or residues of uranium conversion processing. The last part presents the main orientations for the project

Assessing Waste Water Treatment Plant Effluents For Thyroid Hormone Disrupting Activity

Science.gov (United States)

Much information has been coming to light on the estrogenic and androgenic activity of chemicals present in the waste water stream and in surface waters, but much less is known about the presence of chemicals with thyroid activity. To address this issue, we have utilized two ass...

The Japan Power Demonstration Reactor (JPDR) dismantling activities. Management of JPDR dismantling waste

International Nuclear Information System (INIS)

Abe, Masayoshi; Nakata, Susumu; Ito, Shinichi

1996-01-01

The management of wastes, both radioactive and non-radioactive, is one of the most important issues for a safe and reasonable dismantling operation of nuclear power plants. A large amount of radioactive wastes is arising from a reactor dismantling operation in a relatively short period time, ranging in a wide variety from very low level to relatively high level. Moreover non-radioactive waste is also in a huge amount. The dismantling operation of Japan Power Demonstration Reactor (JPDR) resulted in 24,440 tons of dismantling wastes, of which about 15% was radioactive and 85% non-radioactive. These wastes were managed successfully implementing a well developed management plan for JPDR dismantling waste. Research and development works for handling of JPDR dismantling wastes were performed, including fixation of loose contamination on surface, volume reduction and waste containers for on-site transportation and interim storage. The JPDR dismantling wastes generated were classified and categorized depending on their materials, characteristics and activity level. Approximately 2,100 tons of radioactive wastes were stored in the interim storage facilities on site using developed containers, and 1,670 tons of radioactive concrete waste were used for a safe demonstration test of a simple near-surface disposal for very low level waste. Other dismantling wastes such as steel and concrete which were categorized as non-radioactive were recycled and reused as useful resources. This paper describes the management of the JPDR dismantling wastes. (author)

ALKALI-ACTIVATED CEMENT MORTARS CONTAINING RECYCLED CLAY-BASED CONSTRUCTION AND DEMOLITION WASTE

Directory of Open Access Journals (Sweden)

F. Puertas

2015-09-01

Full Text Available The use of clay-based waste as an aggregate for concrete production is an amply studied procedure. Nonetheless, research on the use of this recycled aggregate to prepare alkaline cement mortars and concretes has yet to be forthcoming. The present study aimed to determine: the behaviour of this waste as a pozzolan in OPC systems, the mechanical strength in OPC, alkali-activated slag (AAS and fly ash (AAFA mortars and the effect of partial replacement of the slag and ash themselves with ground fractions of the waste. The pozzolanic behaviour of clay-based waste was confirmed. Replacing up to 20 % of siliceous aggregate with waste aggregate in OPC mortars induced a decline in 7 day strength (around 23 wt. %. The behaviour of waste aggregate in AAMs mortars, in turn, was observed to depend on the nature of the aluminosilicate and the replacement ratio used. When 20 % of siliceous aggregate was replaced by waste aggregate in AAS mortars, the 7 day strength values remained the same (40 MPa. In AAFA mortars, waste was found to effectively replace both the fly ash and the aggregate. The highest strength for AAFA mortars was observed when they were prepared with both a 50 % replacement ratio for the ash and a 20 % ratio for the aggregate.

Supplement analysis of transuranic waste characterization and repackaging activities at the Idaho National Engineering Laboratory in support of the Waste Isolation Pilot Plant test program

International Nuclear Information System (INIS)

1991-03-01

This supplement analysis has been prepared to describe new information relevant to waste retrieval, handling, and characterization at the Idaho National Engineering Laboratory (INEL) and to evaluate the need for additional documentation to satisfy the National Environmental Policy Act (NEPA). The INEL proposes to characterize and repackage contact-handled transuranic waste to support the Waste Isolation Pilot Plant (WIPP) Test Phase. Waste retrieval, handling and processing activities in support of test phase activities at the WIPP were addressed in the Supplemental Environmental Impact Statement (SEIS) for the WIPP. To ensure that test-phase wastes are properly characterized and packaged, waste containers would be retrieved, nondestructively examined, and transported from the Radioactive Waste Management Complex (RWMC) to the Hot-Fuel Examination Facility for headspace gas analysis, visual inspections to verify content code, and waste acceptance criteria compliance, then repackaging into WIPP experimental test bins or returned to drums. Following repackaging the characterized wastes would be returned to the RWMC. Waste characterization would help DOE determine WIPP compliance with US Environmental Protection Agency regulations governing disposal of transuranic waste and hazardous waste. Additionally, this program supports onsite compliance with Resource Conservation and Recovery Act (RCRA) requirements, compliance with the terms of the No-Migration Variance at WIPP, and provides data to support future waste shipments to WIPP. This analysis will help DOE determine whether there have been substantial changes made to the proposed action at the INEL, or if preparation of a supplement to the WIPP Final Environmental Impact Statement (DOE, 1980) and SEIS (DOE, 1990a) is required. This analysis is based on current information and includes details not available to the SEIS

Characterization of Old Nuclear Waste Packages Coupling Photon Activation Analysis and Complementary Non-Destructive Techniques

International Nuclear Information System (INIS)

Carrel, Frederick; Coulon, Romain; Laine, Frederic; Normand, Stephane; Sari, Adrien; Charbonnier, Bruno; Salmon, Corine

2013-06-01

Radiological characterization of nuclear waste packages is an industrial issue in order to select the best mode of storage. The characterization becomes crucial particularly for waste packages produced at the beginning of the French nuclear industry. For the latter, available information is often incomplete and some key parameters are sometimes missing (content of the package, alpha-activity, fissile mass...) In this case, the use of non-destructive methods, both passive and active, is an appropriate solution to characterize nuclear waste packages and to obtain all the information of interest. In this article, we present the results of a complete characterization carried out on the TE 1060 block, which is a nuclear waste package produced during the 1960's in Saclay. This characterization is part of the DEMSAC (Dismantling of Saclay's facilities) project (ICPE part). It has been carried out in the SAPHIR facility, located in Saclay and housing a linear electron accelerator. This work enables to show the great interest of active methods (photon activation analysis and high-energy imaging) as soon as passive techniques encounter severe limitations. (authors)

Adsorption decontamination of radioactive waste solvent by activated alumina and bauxites

International Nuclear Information System (INIS)

Hassan, N.M.; Marra, J.C.; Kyser, E.A.

1994-01-01

An adsorption process utilizing activated alumina and activated bauxite adsorbents was evaluated as a function of operating parameters for the removal of low level radioactive contaminants from organic waste solvent generated in the fuel reprocessing facilities and support operations at Savannah River Site. The waste solvent, 30% volume tributyl phosphate in n-paraffin diluent, was degraded due to hydrolysis and radiolysis reactions of tributyl phosphate and n-paraffin diluent, producing fission product binding degradation impurities. The process, which has the potential for removing these activity-binding degradation impurities from the solvent, was operated downflow through glass columns packed with activated alumina and activated bauxite adsorbents. Experimental breakthrough curves were obtained under various operating temperatures and flow rates. The results show that the adsorption capacity of the activated alumina was in the order 10 4 dpm/g and the capacity of the activated bauxite was 10 5 dpm/g. The performance of the adsorption process was evaluated in terms of dynamic parameters (i.e. adsorption capacity, the height and the efficiency of adsorption zone) in such a way as to maximize the adsorption capacity and to minimize the height of the mass transfer or adsorption zone

Techniques for sampling nuclear waste tank contents and in situ measurement of activity

International Nuclear Information System (INIS)

Lawrence, R.C.

1978-04-01

A study was conducted to develop suitable sampling equipment and techniques for characterizing the mechanical properties of nuclear wastes; identifying effective means of measuring radiation levels, temperatures, and neutron fluxes in situ in wastes; and developing a waste core sampler. A portable, stainless steel probe was developed which is placed in the tank through a riser. This probe is built for the insertion of instrumentation that can measure the contents of the tank at any level and take temperature, radiation, and neutron activation readings with reliable accuracy. A simple and reliable instrument for the in situ extraction of waste materials ranging from liquid to concrete-like substances was also developed. This portable, stainless steel waste core sampler can remove up to one liter of radioactive waste from tanks for transportation to hot cell laboratories for analysis of hardness, chemical form, and isotopic content. A cask for transporting the waste samples from the tanks to the laboratory under radiation-protected conditions was also fabricated. This cask was designed with a ''boot'' or inner-seal liner to contain any radioactive wastes that might remain on the outside of the waste core sampling device

Characterization of low and medium active wastes

International Nuclear Information System (INIS)

Saas, A.

1993-01-01

For several years now, research on raw or packaged waste characterization has been carried out in France. Qualitative or quantitative analysis are given of radionuclides present in already packaged waste (including badly packaged waste) or in unpackaged waste; as far as possible, evaluation of the main physico-mechanical and confinement characteristics

Hospitalar radioactive waste of low activity, a daily practice

Energy Technology Data Exchange (ETDEWEB)

Rezio, M.T.; Vieira, M.R. [Instituto Portugues de Oncologia de Francisco Gentil - CROL, Lisboa (Portugal)

2006-07-01

Introduction According to the law we should have a specific area for storing and treating waste. That area should have special containers for temporary storage in order to assure the radioactive decay for all the radioactive waste, biological contaminated or non biological and in solid or liquid form. According with that law the limits established for discharge are: For solid waste, we must not discharge more than 370 MBq in a minimum volume of 0,1 m{sup 3} and is not allowed waste with activities higher than 3,7 kBq; For liquid waste discharges from the department to the public sewer, the average concentrations calculated taking into account the water flow of the sewer system that serves the installation, should be the following:The annual medium concentration must not exceed 3 times the reference concentration (C.R.) for that nuclide; The monthly medium concentration must not exceed 15 times the reference concentration (C.R.); The daily medium concentration must not exceed 60 times the reference concentration (C.R.); The reference concentration (C.R.), expressed in Bq.m{sup -3}, should be calculated taking into account the relevant incorporation per ingestion. The calculation of C.R. in liquid waste should have into account the following: For the general public the effective dose E achieved, per ingestion by an individual in the group of age g is determined according to the following formula(1):E= {sigma}{sub i} h(g){sub j,ing} X J{sub j,ing}, where h(g){sub j,ing} is the committed effective dose per unit-intake for the ingested radionuclide j (Sv/Bq) by an individual in the group of age g; J{sub j,ing} is the relevant intake via ingestion of the radionuclide j (Bq). The effective dose E achieved by an individual in the group of age g should not be higher than 0,1 mSv/year. If the average water volume ingested by an individual adult is 800 l, the value J{sub j,ing}, calculated by the formula (1) should be referred to 1000 l, in order to obtain the C.R., for the

Nondestructive assay of TRU waste using gamma-ray active and passive computed tomography

International Nuclear Information System (INIS)

Roberson, G.P.; Decman, D.; Martz, H.; Keto, E.R.; Johansson, E.M.

1995-01-01

The authors have developed an active and passive computed tomography (A and PCT) scanner for assaying radioactive waste drums. Here they describe the hardware components of their system and the software used for data acquisition, gamma-ray spectroscopy analysis, and image reconstruction. They have measured the performance of the system using ''mock'' waste drums and calibrated radioactive sources. They also describe the results of measurements using this system to assay a real TRU waste drum with relatively low Pu content. The results are compared with X-ray NDE studies of the same TRU waste drum as well as assay results from segmented gamma scanner (SGS) measurements

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.)

Quarterly Progress Report Research And Development Activities Waste Fixation Program October Through December 1976

International Nuclear Information System (INIS)

McElroy, J. L.

1977-01-01

Research and development activities of the Waste Fixation Program for October through December 1976 are described in this report. The objective of this program is to develop processes to convert high-level radioactive liquid waste (HLLW) to solid forms that are demonstrated to be physically, chemically, and radiolytically stable and inert. The scope of this program encompasses plans to make available a flexible advancing technology for the solidification of radioactive waste. Early technology will produce borosilicate glass by in-can melting and continuous electric melters. Multibarrier waste forms will be developed for future application

LLNL/YMP Waste Container Fabrication and Closure Project; GFY technical activity summary

Energy Technology Data Exchange (ETDEWEB)

NONE

1990-10-01

The Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM) Program is studying Yucca Mountain, Nevada as a suitable site for the first US high-level nuclear waste repository. Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing and developing the waste package for the permanent storage of high-level nuclear waste. This report is a summary of the technical activities for the LLNL/YMP Nuclear Waste Disposal Container Fabrication and Closure Development Project. Candidate welding closure processes were identified in the Phase 1 report. This report discusses Phase 2. Phase 2 of this effort involved laboratory studies to determine the optimum fabrication and closure processes. Because of budget limitations, LLNL narrowed the materials for evaluation in Phase 2 from the original six to four: Alloy 825, CDA 715, CDA 102 (or CDA 122) and CDA 952. Phase 2 studies focused on evaluation of candidate material in conjunction with fabrication and closure processes.

Potential US/Canadian cooperative activities in geological disposal of radioactive waste

International Nuclear Information System (INIS)

Duguid, J.O.

1980-03-01

A joint review meeting between the US and Canada was held on June 19 and 20, 1979 to discuss waste isolation activities in crystalline rocks. The review meeting served the purposes of an initial information transfer and as a mechanism to stimulate thinking for a workshop on US/Canadian cooperative programs which was held on June 21, 1979. The workshop participants divided into working groups to discuss areas of potential cooperation: the Administrative Working Group established protocol for information exchange and cooperative activities; the Geotechnical Working Group selected activities in exploration, field testing, instrumentation and measurement technique development, monitoring, and quality assurance where cooperation would be of benefit to both countries; and the Assessment/Modeling Working Group discussed areas in model development and verification, engineered barriers, radiation effects, hydrologic properties of fractured rocks, waste form leaching, and sorption where cooperation would enhance both the US and Canadian programs

On the influence of matrix's heterogeneity on uncertainty of gamma-spectrometry at activity assay of radioactive waste

Directory of Open Access Journals (Sweden)

V. S. Prokopenko

2009-09-01

Full Text Available The influence of the waste matrix heterogeneity on the flux density value of initial gamma quanta at the transport of quanta in the matrix was considered. It is shown that the waste heterogeneity leads to the positive shift of the average flux density value comparing with corresponding value for homogeneous waste if average value of the attenuation factor in heterogeneous matrix is equal to the attenuation factor of homogeneous matrix. Due to this the activity assay of heterogeneous waste by a technique which was calibrated by using a homogeneous standard (surrogate container the measurement results will be positively shifted, or, in other words, conservative estimation of the waste activity will be obtained.

Acceptable knowledge summary report for combustible/noncombustible, metallic, and HEPA filter waste resulting from 238Pu fabrication activities

International Nuclear Information System (INIS)

Rogers, P.S.Z.; Foxx, C.L.

1998-01-01

All transuranic (TRU) waste must be sufficiently characterized and certified before it is shipped to the Waste Isolation Pilot Plant (WIPP). The US Environmental Protection Agency (EPA) allows use of acceptable knowledge (AK) for waste characterization. EPA uses the term AK in its guidance document and defines AK and provides guidelines on how acceptable knowledge should be obtained and documented. This AK package has been prepared in accordance with Acceptable Knowledge Documentation (TWCP-QP-1.1-021,R.2). This report covers acceptable knowledge information for five waste streams generated at TA-55 during operations to fabricate various heat sources using feedstock 238 Pu supplied by the Savannah River Site (SRS). The 238 Pu feedstock itself does not contain quantities of RCRA-regulated constituents above regulatory threshold limits, as known from process knowledge at SRS and as confirmed by chemical analysis. No RCRA-regulated chemicals were used during 238 Pu fabrication activities at TA-55, and all 238 Pu activities were physically separated from other plutonium processing activities. Most of the waste generated from the 238 Pu fabrication activities is thus nonmixed waste, including waste streams TA-55-43, 45, and 47. The exceptions are waste streams TA-55-44, which contains discarded lead-lined rubber gloves used in the gloveboxes that contained the 238 Pu material, and TA-55-46, which may contain pieces of discarded lead. These waste streams have been denoted as mixed because of the presence of the lead-containing material

Method to determine the activity concentration and total activity of radioactive waste; Metodo para determinar la concentracion de actividad y actividad total de desechos radiactivos

Energy Technology Data Exchange (ETDEWEB)

Angeles C, A

2001-02-15

A characteristic system of radioactive waste is described to determine the concentration of radionuclides activity and the total activity of bundles of radioactive waste. The system this integrated by three subsystems: - Elevator of drums. - Electromechanics. - Gamma spectroscopy. In the system it is analyzed waste of issuing gamma specifically, and this designed for materials of relative low density and it analyzes materials of cylindrical recipients.

Winery waste recycling through anaerobic co-digestion with waste activated sludge.

Science.gov (United States)

Da Ros, C; Cavinato, C; Pavan, P; Bolzonella, D

2014-11-01

In this study biogas and high quality digestate were recovered from winery waste (wine lees) through anaerobic co-digestion with waste activated sludge both in mesophilic and thermophilic conditions. The two conditions studied showed similar yields (0.40 m(3)/kgCODfed) but different biological process stability: in fact the mesophilic process was clearly more stable than the thermophilic one in terms of bioprocess parameters. The resulting digestates showed good characteristics for both the tested conditions: heavy metals, dioxins (PCDD/F), and dioxin like bi-phenyls (PCBs) were concentred in the effluent if compared with the influent because of the important reduction of the solid dry matter, but remained at levels acceptable for agricultural reuse. Pathogens in digestate decreased. Best reductions were observed in thermophilic condition, while at 37°C the concentration of Escherichia coli was at concentrations level as high as 1000 UFC/g. Dewatering properties of digestates were evaluated by means of the capillary suction time (CST) and specific resistance to filtration (SRF) tests and it was found that a good dewatering level was achievable only when high doses of polymer (more than 25 g per kg dry solids) were added to sludge. Copyright © 2014 Elsevier Ltd. All rights reserved.

Determination of alpha activity and fissile mass content in solid waste by systems using neutron interrogation

International Nuclear Information System (INIS)

Romeyer Dherbey, J.; Lacruche, G.; Berne, R.; Auge, J.; Martin Deidier, L.; Butez, M.

1990-01-01

The Quantitative control (determination of heavy nuclides and alpha activity) of alpha radioactive wastes is necessary, particularly to determine if the waste is in accordance with the surface storage limits. In order to reduce the uncertainty on the alpha activity resulting from unknown isotopic composition, inhomogeneity of heavy nuclides in the matrix, combination of several methods is necessary. In the paper we present the Cadarache development work in the NDA of solid waste using the Californium shuffler, 14 Mev neutron generator, and also passive techniques such as neutron emission measurement and gamma spectrometry. Experimental systems combining active and passive methods are presented (COSAC, BANCO, DANAIDE, PROMETHEE)

Initial Selection of Supplemental Treatment Technologies for Hanford's Low-Activity Tank Waste

International Nuclear Information System (INIS)

Raymond, Richard E.; Powell, Roger W.; Hamilton, Dennis W.; Kitchen, William A.; Mauss, Billie M.; Brouns, Thomas M.

2004-01-01

In 2002, the U.S. Department of Energy (DOE) documented a plan for accelerating cleanup of the Hanford Site, located in southeastern Washington State, by at least 35 years (DOE 2002). A key element of the accelerated cleanup plan was a strategic initiative for acceleration of the tank waste program and completion of ''tank waste treatment by 2028 by increasing the capacity of the planned Waste Treatment Plant (ETP) and using supplemental technologies for waste treatment and immobilization''. The plan identified specific technologies to be evaluated for supplemental treatment of as much as 70% of the low-activity waste (LAW). The objective was to complete required testing and evaluation that would ''...bring an appropriate combination of the above technologies to deployment to supplement LAW treatment and immobilization in the WTP to achieve the completion of tank waste treatment by 2028''. In concert with this acceleration plan, DOE, the U.S. Environmental Protection Agency, and the Washington State Department of Ecology have proposed to accelerate from 2012 to 2005 the Hanford Federal Facility Compliance Agreement (Tri-Party Agreement) milestone (M-62-08) associated with a final decision on treatment of the balance of tank waste that is beyond the capacity of the currently designed WTP

Development of Simulants to Support Mixing Tests for High Level Waste and Low Activity Waste

International Nuclear Information System (INIS)

EIBLING, RUSSELLE.

2004-01-01

The objectives of this study were to develop two different types of simulants to support vendor agitator design studies and mixing studies. The initial simulant development task was to develop rheologically-bounding physical simulants and the final portion was to develop a nominal chemical simulant which is designed to match, as closely as possible, the actual sludge from a tank. The physical simulants to be developed included a lower and upper rheologically bounded: pretreated low activity waste (LAW) physical simulant; LAW melter feed physical simulant; pretreated high level waste (HLW) physical simulant; HLW melter feed physical simulant. The nominal chemical simulant, hereafter referred to as the HLW Precipitated Hydroxide simulant, is designed to represent the chemical/physical composition of the actual washed and leached sludge sample. The objective was to produce a simulant which matches not only the chemical composition but also the physical properties of the actual waste sample. The HLW Precipitated Hydroxide simulant could then be used for mixing tests to validate mixing, homogeneity and representative sampling and transferring issues. The HLW Precipitated Hydroxide simulant may also be used for integrated nonradioactive testing of the WTP prior to radioactive operation

US DOE Initiated Performance Enhancements to the Hanford Waste Treatment and Immobilization Plant (WTP) Low-activity Waste Vitrification (LAW) System

International Nuclear Information System (INIS)

Hamel, William F.; Gerdes, Kurt D.; Holton, Langdon K.; Pegg, Ian L.; Bowen, Brad W.

2006-01-01

The U.S Department of Energy Office of River Protection (DOE-ORP) is constructing a Waste Treatment and Immobilization Plant (WTP) for the treatment and vitrification of underground tank wastes stored at the Hanford Site in Washington State. The WTP comprises four major facilities: a pretreatment facility to separate the tank waste into high level waste (HLW) and low-activity waste (LAW) process streams, a HLW vitrification facility to immobilize the HLW fraction; a LAW vitrification facility to immobilize the LAW fraction, and an analytical laboratory to support the operations of all four treatment facilities. DOE has established strategic objectives to optimize the performance of the WTP facilities and the LAW and HLW waste forms to reduce the overall schedule and cost for treatment and vitrification of the Hanford tank wastes. This strategy has been implemented by establishing performance expectations in the WTP contract for the facilities and waste forms. In addition, DOE, as owner-operator of the WTP facilities, continues to evaluate (1) the design, to determine the potential for performance above the requirements specified in the WTP contract; and (2) improvements in production of the LAW and HLW waste forms. This paper reports recent progress directed at improving production of the LAW waste form. DOE's initial assessment, which is based on the work reported in this paper, is that the capacity of the WTP LAW vitrification facility can be increased by a factor of 2 to 4 with a combination of revised glass formulations, modest increases in melter glass operating temperatures, and a second-generation LAW melter with a larger surface area. Implementing these improvements in the LAW waste immobilization capability can benefit the LAW treatment mission by reducing both processing time and cost

A mobile system for treating low-salinity low-activity liquid wastes

International Nuclear Information System (INIS)

Sobolev, I.A.; Timofeev, E.M.; Panteleev, V.I.; Karlin Yu.V.; Kropotov, V.N.; Slastennikov, Yu.T.; Chuikov, V.Yu.; Demkin, V.I.; Rozhkov, V.T.

1993-01-01

Radioactive wastes are produced not only in radiochemical production and nuclear power stations but also in numerous research institutes and industrial organizations. The specific activities of these wastes are low, and the volumes do not exceed a few dozen cubic meters a year at each individual organization, but processing such territorially distributed wastes is complicated. This particularly applies to liquid wastes, whose transportation involves a high risk of contamination if the sealing fails. As a rule, liquid wastes are solidified before transportation to a storage site. In some cases, that simplified approach leads to an unduly large consumption of solidifying materials, and particularly to an increase in volume, while storage is an expensive technique. A considerable volume reduction in the wastes to be stored is provided by processing the liquid wastes to concentrate the radionuclides in a small volume, with the main volume of treated water discharged to the drains. Two styles are possible: a stationary plant for processing wastes at each institution or a mobile one with a centralized service base, e.g., at the storage site. Mobile systems have been reported in world practice, although there is no detailed information on them. From the economic viewpoint, the second approach is preferable because it enables one to conduct such operations with fewer plants and fewer staff. That a mobile concept that was used at the Moscow Radon Cooperative in 1985 in processing liquid wastes at regional storage locations is summarized in this article. Research and development led in 1989 to the manufacture of a prototype mobile system mounted on an MAZ articulated vehicle, which included three basic modules: ultrafiltration, electrodialysis, and filtration ones. Each module is located on a separate framework and is connected to the others by reinforced rubber hoses

''Cold crucible'' vitrification projects for low and high active waste

International Nuclear Information System (INIS)

Roux, P.; Jouan, A.

1998-01-01

In continuity of the CEA HLW vitrification process experienced for more than 20 years in industrial operations in Cogema reprocessing plants (Marcoule and La Hague), CEA has developed an advanced extended performance cold crucible glass melter to address a wider range of waste like LLW, ILW and in particular waste with very corrosive species or requiring glass with higher elaboration temperature. In the cold crucible melter the bath of molten glass is directly heated by induction while the walls are cooled in order to freeze a protective glass layer. This technology subsequently allows high glass throughput while keeping the flexibility, the maintainability and low secondary waste generation related to a small metallic melter. Its recent use in the glass industry and the thousands of hours of pilot tests performed on inactive surrogates have demonstrated the maturity of this technology and its flexibility of use for processing most of the waste generated at nuclear facilities. SGN has therefore proposed this technology in Italy and Korea and in USA in the frame of the Hanford Privatization phase 1 A feasibility study. Main features of this study but also tests results with Hanford surrogates and active samples are discussed. (author)

Source segregation and food waste prevention activities in high-density households in a deprived urban area

International Nuclear Information System (INIS)

Rispo, A.; Williams, I.D.; Shaw, P.J.

2015-01-01

Highlights: • Study of waste management in economically and socially deprived high-density housing. • Food waste segregation, prevention and recycling activities investigated. • Study involved a waste audit and household survey of 1034 households. • Populations in such areas are “hard-to-reach”. • Exceptional efforts and additional resources are required to improve performance. - Abstract: A waste audit and a household questionnaire survey were conducted in high-density housing estates in one of the most economically and socially deprived areas of England (Haringey, London). Such areas are under-represented in published research. The study examined source segregation, potential participation in a food waste segregation scheme, and food waste prevention activities in five estates (1034 households). The results showed that: contamination of recyclables containers was low; ca. 28% of the mixed residual waste’s weight was recyclable; food waste comprised a small proportion of the waste from these residents, probably because of their relatively disadvantaged economic circumstances; and the recycling profile reflected an intermittent pattern of behaviour. Although the majority of respondents reported that they would participate in a food waste separation scheme, the response rate was low and many responses of “don’t know” were recorded. Municipalities committed to foster improved diversion from landfill need to recognise that there is no “quick and easy fix”, regardless of local or national aspirations. Lasting and sustained behaviour change requires time and the quality of service provision and associated infrastructure play a fundamental role in facilitating residents to participate effectively in waste management activities that maximise capture of source-segregated materials. Populations in deprived areas that reside in high-rise, high-density dwellings are “hard-to-reach” in terms of participation in recycling schemes and exceptional

Source segregation and food waste prevention activities in high-density households in a deprived urban area

Energy Technology Data Exchange (ETDEWEB)

Rispo, A.; Williams, I.D., E-mail: idw@soton.ac.uk; Shaw, P.J.

2015-10-15

Highlights: • Study of waste management in economically and socially deprived high-density housing. • Food waste segregation, prevention and recycling activities investigated. • Study involved a waste audit and household survey of 1034 households. • Populations in such areas are “hard-to-reach”. • Exceptional efforts and additional resources are required to improve performance. - Abstract: A waste audit and a household questionnaire survey were conducted in high-density housing estates in one of the most economically and socially deprived areas of England (Haringey, London). Such areas are under-represented in published research. The study examined source segregation, potential participation in a food waste segregation scheme, and food waste prevention activities in five estates (1034 households). The results showed that: contamination of recyclables containers was low; ca. 28% of the mixed residual waste’s weight was recyclable; food waste comprised a small proportion of the waste from these residents, probably because of their relatively disadvantaged economic circumstances; and the recycling profile reflected an intermittent pattern of behaviour. Although the majority of respondents reported that they would participate in a food waste separation scheme, the response rate was low and many responses of “don’t know” were recorded. Municipalities committed to foster improved diversion from landfill need to recognise that there is no “quick and easy fix”, regardless of local or national aspirations. Lasting and sustained behaviour change requires time and the quality of service provision and associated infrastructure play a fundamental role in facilitating residents to participate effectively in waste management activities that maximise capture of source-segregated materials. Populations in deprived areas that reside in high-rise, high-density dwellings are “hard-to-reach” in terms of participation in recycling schemes and exceptional

Briefing book on environmental and waste management activities

International Nuclear Information System (INIS)

Quayle, T.A.

1993-04-01

The purpose of the Briefing Book is to provide current information on Environmental Restoration and Waste Management Activities at the Hanford Site. Each edition updates the information in the previous edition by deleting those sections determined not to be of current interest and adding new topics to keep up to date with the changing requirements and issues. This edition covers the period from October 15, 1992 through April 15, 1993

The validation of waste assay systems during active test at Rokkasho Reprocessing Plant

International Nuclear Information System (INIS)

Tamura, Takayuki; Miura, Yasushi; Iwamoto, Tomonori

2007-01-01

In order to implement accurate material accountancy at Rokkasho Reprocessing Plant (RRP) as a large scale reprocessing plant, it is necessary to introduce accurate measurement systems not only for mainstream material, but also appropriate measurement systems for solid waste materials. In this sense, the generated wastes by the active test operation have been measured with the Non-Destructive Assay Systems, such as Rokkasho Hulls Measurement System (RHMS) and Waste Crate Assay System (WCAS) for accountancy. This paper describes the experience of the NDA operation and the evaluation results for accountancy. (author)

State-of-the-art dry active waste processing facility

International Nuclear Information System (INIS)

Hillmer, T.; Ingalsbe, H.; Alcorn, G.; Anderson, K.; Dahlen, D.

1989-01-01

Palo Verde Nuclear Generating Station (PVNGS) is operated by Arizona Public Service for a consortium of seven owners. The site consists of three identical single unit power plants. Each unit is a Combustion Engineering Series 80 pressurized water reactor (PWR) rated at 1270 Megawatts electric. The site is located 100 kilometers west of Phoenix, Arizona in the arid southwest desert region of the United States of America. Since the start up of Unit One in 1985, Palo Verde has aggressively pursued waste volume reduction. This includes a dry active waste (DAW) segregation program that locates and separates nonradioactive and reusable materials that have been mixed with the radioactive DAW. The DAW program is described in further detail in the paper

New insights into co-digestion of activated sludge and food waste: Biogas versus biofertilizer.

Science.gov (United States)

Ma, Yingqun; Yin, Yao; Liu, Yu

2017-10-01

This study explored two holistic approaches for co-digestion of activated sludge and food waste. In Approach 1, mixed activated sludge and food waste were first hydrolyzed with fungal mash, and produced hydrolysate without separation was directly subject to anaerobic digestion. In Approach 2, solid generated after hydrolysis of food waste by fungal mash was directly converted to biofertilizer, while separated liquid with high soluble COD concentration was further co-digested with activated sludge for biomethane production. Although the potential energy produced from Approach 1 was about 1.8-time higher than that from Approach 2, the total economic revenue generated from Approach 2 was about 1.9-fold of that from Approach 1 due to high market value of biofertilizer. It is expected that this study may lead to a paradigm shift in biosolid management towards environmental and economic sustainability. Copyright © 2017 Elsevier Ltd. All rights reserved.

Levels for the specific activity at disposing low-level contaminated municipal wastes

International Nuclear Information System (INIS)

Poschner, J.; Schaller, G.

1993-12-01

Using radioecological models, nuclide-specific ''basic values'' were established for the specific activity of radioactive contaminated waste. These basic values were determined in order to avoid dose equivalents of more than 10 μSv/a (de minimis concept) when disposing the waste in conventional waste deposits or burning it in incineration plants. The basic values vary within 16 orders of magnitude, ranging between 4.3E-02 Bq/g for Cm-250 and 2.2E+14 Bq/g for Po-212. About 82% of the basic values are between 1 Bq/g und 1000 Bq/g. The critical exposure for most of the radionuclides is that from direct radiation or inhalation at the slag-deposit. For 54% of the radionuclides the basic value for the specific activity of waste is lower at least by a factor of 10 than the 10 -4 -fold value per gram of the release limit (German Radiation Protection Ordinance). Appropriate nuclide-specific and dose-related limits were derived from these basic values. The respective limits are ranging between 1E-01 Bq/g and 1E+07 Bq/g. About 95% of the limits are between 1 Bq/g and 1000 Bq/g. (orig./HP) [de

Applicability of Activated Carbon to Treatment of Waste Containing Iodine-Labeled Compounds

International Nuclear Information System (INIS)

Gad, H.M.H.; El-Mouhty, N.R.A.; Aly, H.F.

2008-01-01

The applicability of activated carbon prepared from sawdust (SD) by one-step chemical activation process using H 3 PO 4 (H) to treatment of aqueous waste contaminated with iodine-labeled prolactin (I-PRL) has been investigated. Treatment processes were performed under the varying conditions; contact time, temperature, carbon type, carbon dosage, and different particle size of activated carbon (SDH). Effect of aqueous waste volume has been investigated to calculate the batch factor (V/M) and the distribution coefficient (K d ). The used activated carbon (SDH) was characterized by N 2 adsorption, FTIR, density, ph, point of zero charge ph p zc, moisture and ash content. Methylene blue (MB) and iodine number was calculated by adsorption from solution. In order to investigate the mechanism of sorption and potential rate controlling steps, pseudo first- and second-order equations, intra particle diffusion equation and the Elovich equation have been used to test experimental data. Kinetic analysis of the four models has been carried out for system variables in order to assess which model provides the best fit predicted data with experimental results. 7 M NaOH can be used for regeneration of spent SDH activated carbon with the efficiency of 99.6% and the regenerated carbon can be reused for five cycles effectively. The prospect of applying the SDH activated carbon prepared from agricultural by-product, sawdust, to treatment of aqueous waste contaminated with I-PRL appears promising and is considered highly applicable because of its high adsorption capacity, available at low cost, easily regenerated and reused

Prospective implementation of a software application for pre-disposal L/ILW waste management activities in Romania

International Nuclear Information System (INIS)

Fako, Raluca; Sociu, Florin; Stan, Camelia; Georgescu, Roxana; Barariu, Gheorghe

2013-01-01

Romania is actively engaged to update the Medium and Long Term National Strategy for Safe Management of Radioactive Waste and to approve the Road Map for Geological Repository Development. Considering relevant documents to be further updated, about 122,000 m 3 SL-LILW are to be disposed in a near surface facility that will have room, also, for quantities of VLLW. Planned date for commissioning is under revision. Taking into account that in this moment there are initiated several actions for the improvement of the technical capability for LILW treatment and conditioning, several steps for the possible use of SAFRAN software were considered. In view of specific data for Romanian radioactive waste inventory, authors are trying to highlight the expected limitations and unknown data related with the implementation of SAFRAN software for the foreseen pre-disposal waste management activities. There are challenges that have to be faced in the near future related with clear definition of the properties of each room, area and waste management activity. This work has the aim to address several LILW management issues in accordance with national and international regulatory framework for the assurance of nuclear safety. Also, authors intend to develop their institutional capability for the safety demonstration of the existent and future radioactive waste management facilities and activities. (authors)

Treatment of rod shaped intermediate active waste

International Nuclear Information System (INIS)

Graf, A.; Blase, F.; Dirks, F.; Valencia, L.

2002-01-01

The Central Decontamination Operation Department (HDB) of the Research Center Karlsruhe operates facilities for the disposal of radioactive waste. In general, their objective is to reduce the volume of the radioactive waste and to obtain waste products suitable for repository storage. One of the central facilities of the HDB is the intermediate level waste (ILW) scrapping facility which processes intermediate level waste. Since the ILW scrapping facility was not large enough to handle radioactive waste coming from the dismantling and operating of nuclear facilities, HDB expanded and built a larger hot cell. It contains a hydraulically driven metal cutter with a guiding channel and a high pressure compactor. A major task in the hot cell of the ILW scrapping facility is disposing of fuel boxes. These are cut in pieces and scrapped, which is a unique technique in Germany for fuel box disposal. HDB's experiences in disposing of radioactive waste in the ILW scrapping facility will described in detail, with special emphasis on the handling of rod shaped components. (author)

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.)

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

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

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

Adsorption of malachite green on groundnut shell waste based powdered activated carbon

International Nuclear Information System (INIS)

Malik, R.; Ramteke, D.S.; Wate, S.R.

2007-01-01

In the present technologically fast changing situation related to waste management practices, it is desirable that disposal of plant waste should be done in a scientific manner by keeping in view economic and pollution considerations. This is only possible when the plant waste has the potential to be used as raw material for some useful product. In the present study, groundnut shell, an agricultural waste, was used for the preparation of an adsorbent by chemical activation using ZnCl 2 under optimized conditions and its comparative characterisation was conducted with commercially available powdered activated carbon (CPAC) for its physical, chemical and adsorption properties. The groundnut shell based powdered activated carbon (GSPAC) has a higher surface area, iodine and methylene blue number compared to CPAC. Both of the carbons were used for the removal of malachite green dye from aqueous solution and the effect of various operating variables, viz. adsorbent dose (0.1-1 g l -1 ), contact time (5-120 min) and adsorbate concentrations (100-200 mg l -1 ) on the removal of dye, has been studied. The experimental results indicate that at a dose of 0.5 g l -1 and initial concentration of 100 mg l -1 , GSPAC showed 94.5% removal of the dye in 30 min equilibrium time, while CPAC removed 96% of the dye in 15 min. The experimental isotherm data were analyzed using the linearized forms of Freundlich, Langmuir and BET equations to determine maximum adsorptive capacities. The equilibrium data fit well to the Freundlich isotherm, although the BET isotherm also showed higher correlation for both of the carbons. The results of comparative adsorption capacity of both carbons indicate that groundnut shell can be used as a low-cost alternative to commercial powdered activated carbon in aqueous solution for dye removal

Evaluation of residual activity of solid waste generated in nuclear medicine services of Porto Alegre - Brazil

International Nuclear Information System (INIS)

Xavier, Ana M.; Alabarse, Frederico Gil; Magalhaes, Maisa Haiidamus; Guerrero, Jesus Salvador Perez

2008-01-01

An experimental programme to estimate, with a better degree of accuracy, the activity that remains adsorbed in flasks and syringes used in Nuclear Medicine Services for the administration of radionuclides to patients submitted to diagnostic or therapy was conducted under the coordination of the Radioactive Waste Division of the Brazilian Nuclear Energy Commission. The adopted recommendation in Brazil to allow an expedite solid waste management in nuclear medicine facilities, up to the present, is to consider that 2% of the initial activity remains adsorbed in the solid waste, which easily allows the calculation of the storage time to achieve regulatory clearance levels by decay. This research evaluates 17 different kinds of radio pharmaceuticals and three radioisotopes: 99m Tc, 67 Ga and 201 Tl. Results obtained by means of a weighting method to estimate the residual mass in flasks show that the ratio of the mass of the liquid that remains in the solid waste to the mass of the empty flask is constant. This suggests that the residual activity depends on the initial activity concentration of radiopharmaceutical contained in each flask, as assumed by the regulatory body. Additionally, results obtained by determining the remaining activity in flasks, shortly after the injection of its radionuclides contents in patients, indicate that an average value for the residual activity of the order of 10% of the initial activity contained in the flasks or syringes can be adopted instead of the previously assumed 2%. It is suggested that the more conservative average value obtained in the present work for the activity that remains in flasks and syringes, that is, 10% of the initial activity, could be adopted to determine the decay storage time before the release of solid waste in the urban conventional land fill disposal system. (author)

WATER ACTIVITY DATA ASSESSMENT TO BE USED IN HANFORD WASTE SOLUBILITY CALCULATIONS

Energy Technology Data Exchange (ETDEWEB)

DISSELKAMP RS

2011-01-06

The purpose of this report is to present and assess water activity versus ionic strength for six solutes:sodium nitrate, sodium nitrite, sodium chloride, sodium carbonate, sodium sulfate, and potassium nitrate. Water activity is given versus molality (e.g., ionic strength) and temperature. Water activity is used to estimate Hanford crystal hydrate solubility present in the waste.

WATER ACTIVITY DATA ASSESSMENT TO BE USED IN HANFORD WASTE SOLUBILITY CALCULATIONS

International Nuclear Information System (INIS)

Disselkamp, R.S.

2011-01-01

The purpose of this report is to present and assess water activity versus ionic strength for six solutes:sodium nitrate, sodium nitrite, sodium chloride, sodium carbonate, sodium sulfate, and potassium nitrate. Water activity is given versus molality (e.g., ionic strength) and temperature. Water activity is used to estimate Hanford crystal hydrate solubility present in the waste.

Waste management regulatory compliance issues related to D ampersand D activities at Oak Ridge National Laboratory (ORNL)

International Nuclear Information System (INIS)

Hitch, J.P.; Arnold, S.E.; Burwinkle, T.; Daugherty, D.

1994-01-01

The waste management activities at ORNL related to the decontamination and decommissioning (D ampersand D) of radioactively contaminated buildings are divided into four categories: Operational facilities, inactive or surplus facilities, future facilities planning, and D ampersand D activities. This paper only discusses regulatory issues related to inactive or surplus facilities. Additionally, rather than attempting to address all resulting waste streams and related regulations, this paper highlights only a few of the ORNL waste streams that present key regulatory issues

Microbial activity in argillite waste storage cells for the deep geological disposal of French bituminous medium activity long lived nuclear waste: Impact on redox reaction kinetics and potential

Science.gov (United States)

Albrecht, A.; Leone, L.; Charlet, L.

2009-04-01

Micro-organisms are ubiquitous and display remarkable capabilities to adapt and survive in the most extreme environmental conditions. It has been recognized that microorganisms can survive in nuclear waste disposal facilities if the required major (P, N, K) and trace elements, a carbon and energy source as well as water are present. The space constraint is of particular interest as it has been shown that bacteria do not prosper in compacted clay. An evaluation of the different types of French medium and high level waste, in a clay-rich host rock storage environment at a depth between 500 and 600 m, has shown that the bituminous waste is the most likely candidate to accommodate significant microbial activity. The waste consists of a mixture of bitumen (source of bio-available organic matter and H2 as a consequence of its degradation and radiolysis) and nitrates and sulphates kept in a stainless steel container. The assumption, that microbes only have an impact on reaction kinetics needs to be reassessed in the case where nitrates and sulphates are present since both are known not to react at low temperatures without bacterial catalysis. The additional impact of both oxy-anions and their reduced species on redox conditions, radionuclide speciation and mobility gives this evaluation their particular relevance. Storage architecture proposes four primary waste containers positioned into armoured cement over packs and placed with others into the waste storage cell itself composed of a cement mantle enforcing the argillite host rock, the latter being characterized by an excavation damaged zone constricted both in space and in time and a pristine part of 60 m thickness. Bacterial activity within the waste and within the pristine argillite is disregarded because of the low water activity (biofilms are within the interface zones. A major restriction for the initial development of microbial colonies is the high pH controlled by the cement solution. Archea are able to survive

Laboratory Optimization Tests of Technetium Decontamination of Hanford Waste Treatment Plant Direct Feed Low Activity Waste Melter Off-Gas Condensate Simulant

Energy Technology Data Exchange (ETDEWEB)

Taylor-Pashow, K. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2015-12-23

The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable less integrated operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also decrease the LAW vitrification mission duration and quantity of glass waste.

Research on transmutation and accelerator-driven systems at the Forschungszentrum Karlsruhe

International Nuclear Information System (INIS)

Knebel, J.U.; Heusener, G.

2000-01-01

Transmutation is considered a promising technology worldwide for significantly reducing the amount and, thereby, the long-term radiotoxicity of high active waste (HAW) produced by the operation of nuclear power plants such as light water reactors (LWR). The maximum reduction of radiotoxicity could be by a factor of about 100. Transmutation is thus an alternative to the direct deposition of large volumes of highly radioactive waste. Transmutation presents the possibility of closing the fuel cycle including the minor actinides. Plutonium, minor actinides and long-lived fission products can be transmuted in a so called Accelerator Driven Sub-critical System (ADS), which consists of an accelerator, a target module and a subcritical blanket. This paper describes the work performed at Forschungszentrum Karlsruhe which is critically evaluating an ADS mainly with respect to its potential for transmuting minor actinides, to its feasibility and to safety aspects. The work is being done in the area of core design, neutronics, safety, system analyses, materials and corrosion. (orig.) [de

ANDRA - National Radioactive Waste Management Agency. Activity report 2007. Management report - Financial statements at December 31, 2007

International Nuclear Information System (INIS)

2008-09-01

Created in 1979 within the CEA, the National Radioactive Waste Management Agency (ANDRA) was established by the December 1991 Waste Act as a public body in charge of the long-term management of all radioactive waste, under the supervision of the Ministry of Ecology, Energy, Sustainable Development and the Sea (formerly the Ministry of Industry and the Ministry of Environment), and the Ministry of Research. Its 3 basic missions were extended and their funding secured through the 2006 Planning Act: - a R and D mission to propose safe long-term solution for radioactive waste without current disposal system; this mission includes long-term storage, since the 2006 Planning Act, in order to propose interim solutions while final ones are being studied; - an industrial mission concerning, on one hand, waste acceptance criteria and control and, on the other hand, siting, construction, operation, closure and monitoring of repositories. This mission includes as well a public service mission in terms of i) collection of waste of the 'small-scale nuclear activities' producers or owners (including the so-called 'household' radioactive waste, i.e. waste owned by private individuals) and ii) clean-up and rehabilitation of orphan polluted sites; - an information mission, notably through the regular publication of the National Inventory of radioactive materials and waste. This mission includes as well an active policy of dialogue with stakeholders both at national and local level. This document is the activity report with the management and financial statements report of the Andra for the year 2007

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

International Nuclear Information System (INIS)

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

1993-02-01

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

Waste management, decommissioning and environmental restoration for Canada's nuclear activities: 'Current practices and future needs'

International Nuclear Information System (INIS)

2006-01-01

The Canadian Nuclear Society conference on Waste Management, Decommissioning and Environmental Restoration for Canada's Nuclear Activities was held on May 8-11, 2005 in Ottawa, Ontario, Canada. The objective of this Conference was to provide a forum for discussion and exchange of views on the technical, regulatory and social challenges and opportunities in radioactive waste management, nuclear facility decommissioning and environmental restoration activities in Canada. The Conference was organized into several plenary sessions and eight technical tracks: Low- and intermediate-level wastes; Uranium mining and milling wastes; Used nuclear fuel; Decommissioning; Environmental restoration; Policy, economics and social issues; Licensing and regulatory issues; and, Radioactive materials transportation. The three-day Conference involved waste management, decommissioning and environmental technology practitioners; delegates from industry, academia, and government agencies and regulators; consulting engineers; financial and legal experts; and other specialists working in the field. While the Conference had a primarily Canadian focus, about 10 per cent of the submissions received came from foreign and international organizations, which provided insights into how other countries are dealing with similar issues

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.)

Radioactive waste treatment

International Nuclear Information System (INIS)

Alter, U.

1988-01-01

For the Federal Government the safe disposal of waste from nuclear power plants constitutes the precondition for their further operation. The events in the year 1987 about the conditioning and transport of low activity waste and medium activity waste made it clear that it was necessary to intensify state control and to examine the structures in the field of waste disposal. A concept for the control of radioactive waste with negligible heat development (LAW) from nuclear installations is presented. (DG) [de

Molecular hydrogen: an energy source for bacterial activity in nuclear waste disposal

International Nuclear Information System (INIS)

Libert, M.; Esnault, L.

2010-01-01

Document available in extended abstract form only. Hydrogen is a common product of microbial metabolism, large number of bacteria are able to use it as energetic substrate in subsurface ecosystems. Moreover H 2 is known as one of the most energetic substrates for deep subsurface ecosystem. It could be produced in different ways mainly volcanic activity (basalts iron rich volcanic rocks) or natural radiolysis of water or even fermentation. The millimolar concentrations of H 2 observed in the ground waters are consistent with the activity of a large variety of hydrogen-oxidising bacteria as described in the following Table. Electron acceptors are identified as O 2 , CO 2 , NO 3 , SO 4 or Fe +++ . Aerobic, anaerobic, obligate and facultative autotrophs are included. Numerous of these bacteria are thermophilic bacteria. This bacterial activity leads to the production of methane, acetate, nitrogen, hydrogen sulphur or ferrous oxides. In anoxic environments, H 2 concentrations are governed by microbial metabolism. In most cases, H 2 producing microorganisms are thermodynamically controlled by the abundance of H 2 , and survive thanks to H 2 consumers, a metabolism called inter-species H 2 transfer. Metabolism of H 2 is catalysed by hydrogenase as cytoplasmic enzymes or membrane bound enzymes. Several situations of H 2 production will occur in nuclear waste repository: - Radiolysis of water. - Radiolysis of organic matter (such as bitumen, in case of B waste), H 2 production due to gamma radiolysis of bitumen is evaluated to 1 L H 2 /kg of bitumen /MGy. - Corrosion of metal containers (in deaerated solutions). Large amount of H 2 are predicted in some situations, and will select the development of hydrogen species. Then, aerobic hydrogen bacteria oxidising hydrogen could be found in basins containing irradiating waste, or during the oxic period of storage, denitrifying bacteria or sulfate reducing bacteria will develop near the bitumen waste. Groundwater of the Callovo

A passive-active neutron device for assaying remote-handled transuranic waste

International Nuclear Information System (INIS)

Estep, R.J.; Coop, K.L.; Deane, T.M.; Lujan, J.E.

1990-01-01

A combined passive-active neutron assay device was constructed for assaying remote-handled transuranic waste. A study of matrix and source position effects in active assays showed that a knowledge of the source position alone is not sufficient to correct for position-related errors in highly moderating or absorbing matrices. An alternate function for the active assay of solid fuel pellets was derived, although the efficacy of this approach remains to be established

The European Community's research and development activities on the management of radioactive waste from decommissioning

International Nuclear Information System (INIS)

Huber, B.

1984-01-01

The Commission of the European Communities is conducting an R and D programme on the decommissioning of nuclear power plants. The activities carried out within this framework that concern, in particular, management of the radioactive waste arising from the decommissioning are outlined. Characterization of the radioactivity inventory of nuclear power plants at the end of their useful life is of fundamental importance in this context. Research in this field comprises analyses of the trace elements in reactor materials which are relevant for the formation of long-lived radionuclides by neutron activation, as well as examinations of samples taken from activated and contaminated plant components. Most of the radioactive plant components are only surface contaminated. Highly efficient decontamination techniques are being developed with the objective of achieving conditions permitting unrestricted release of the material treated. Other activities concern the conditioning of steel and concrete waste for disposal, and the management of graphite waste from gas-cooled reactors. Large containers are being developed for transport and disposal of radioactive components. Finally, the methods of radiological evaluation and measurement are being studied which are required to decide whether material from the dismantling of nuclear power plants has to be disposed of as radioactive waste or not. (author)

PROMETHEE: An Alpha Low Level Waste Assay System Using Passive and Active Neutron Measurement Methods

International Nuclear Information System (INIS)

Passard, Christian; Mariani, Alain; Jallu, Fanny; Romeyer-Dherbey, Jacques; Recroix, Herve; Rodriguez, Michel; Loridon, Joel; Denis, Caroline; Toubon, Herve

2002-01-01

The development of a passive-active neutron assay system for alpha low level waste characterization at the French Atomic Energy Commission is discussed. Less than 50 Bq[α] (about 50 μg Pu) per gram of crude waste must be measured in 118-l 'European' drums in order to reach the requirements for incinerating wastes. Detection limits of about 0.12 mg of effective 239 Pu in total active neutron counting, and 0.08 mg of effective 239 Pu coincident active neutron counting, may currently be detected (empty cavity, measurement time of 15 min, neutron generator emission of 1.6 x 10 8 s -1 [4π]). The most limiting parameters in terms of performances are the matrix of the drum - its composition (H, Cl...), its density, and its heterogeneity degree - and the localization and self-shielding properties of the contaminant

Neutron Activation analysis of waste water; Analisis de aguas residuales mediante activacion neutronica

Energy Technology Data Exchange (ETDEWEB)

Hernandez H, V

1997-12-01

An instrumental neutron activation analysis for the simultaneous determination of chlorine, bromine, sodium, manganese, cobalt, copper, chromium, zinc, nickel, antimony and iron in waste water is described. They were determined in waste water samples under normal conditions by non-destructive neutron activation simultaneously using a suitable monostandard method. Standardized water samples were used and irradiated in polyethylene ampoules at a neutron flux of 10{sup 13} cm{sup -2} s{sup -1} for periods of 1 minute, 1 and 10 hours. A Ge hyperpure detector was used for your activity determination, with count times of 60, 180, 300 and 600 seconds. The obtained results show than the method can be utilized for the determination of this elements without realize anything previous treatment of the samples. (Author).

The Application of Active Sewage Sludge on the Vermicomposting of Agricultural Waste

Directory of Open Access Journals (Sweden)

seyyedeh maryam kharrazi

2015-11-01

Full Text Available In this experiment, active sewage sludge was inoculated in organic waste. The objective was to study its effect on nutrient dynamics during vermicomposting. Active sewage sludge, as a source of nitrogen fixing and phosphorous solubilizing bacteria, was added in four combinations to the vermicomposting substrate. Prior to inoculation with active sludge, the treatments were precomposted for 30 days and finally vermicomposted for 40 days. Results showed that inoculation of microorganisms in the substrate accompanied by earthworms’ activity enhances the organic waste biodegradation rate. Increasing sludge concentration from 0 to 6000 mg/l led to reduced Total Organic Carbon from 32.76 to 29.91%, Total Volatile Solids from 49.85 to 48/02%, and C/N ratio from 19.59 to 16.06 but increased Total Kjeldahl Nitrogen from 1.68 to 1.87%, nitrate from 1476.75 to 1699.60 mg/kg, Total Phosphorous from 1.66 to 1.77 g/kg, and Electrical Conductivity from 3.10 to 3.48 mS/cm. By increasing the concentration of sewage sludge, heavy metals content also increased significantly due to the enhanced organic matter biodegradation. Finally, the results showed that, among the treatments, the one with an active sewage sludge concentration of 6000 mg/l had more desirable effects on the final vermicompost quality. Based on the reproducibility of the process and the quality of the final products, this experimental procedure may be proposed for studies requiring a mass reduction in the initial composted waste mixtures.

Hanford Immobilized Low Activity Waste (ILAW) Performance Assessment 2001 Version [Formerly DOE/RL-97-69] [SEC 1 & 2

Energy Technology Data Exchange (ETDEWEB)

MANN, F.M.

2000-08-01

The Hanford Immobilized Low-Activity Waste Performance Assessment examines the long-term environmental and human health effects associated with the planned disposal of the vitrified low-activity fraction of waste presently contained in Hanford Site tanks. The tank waste is the byproduct of separating special nuclear materials from irradiated nuclear fuels over the past 50 years. This waste is stored in underground single- and double-shell tanks. The tank waste is to be retrieved, separated into low-activity and high-level fractions, and then immobilized by vitrification. The US. Department of Energy (DOE) plans to dispose of the low-activity fraction in the Hanford Site 200 East Area. The high-level fraction will be stored at the Hanford Site until a national repository is approved. This report provides the site-specific long-term environmental information needed by the DOE to modify the current Disposal Authorization Statement for the Hanford Site that would allow the following: construction of disposal trenches; and filling of these trenches with ILAW containers and filler material with the intent to dispose of the containers.

Volumetric activity of SRS mixed waste and comparison with SRS performance and commercial facility limits

International Nuclear Information System (INIS)

Ades, M.J.; Daugherty, B.A.; Cook, J.R.

1996-01-01

This paper discusses the comparative analysis performed to estimate the after-treatment volumetric activity of the radionuclides included in the Savannah River site (SRS) mixed-waste streams and its comparison with the following: (1) The performance evaluation (PE) limits established for each radionuclide for on-site disposal: These limits correspond to the permissible waste disposal limits that are the lowest limits evaluated for the most restrictive release scenarios that include the groundwater pathway, the atmospheric pathway, and the intruder scenarios. (2) The radiological performance assessment (PA) limits established for each radionuclide for disposal in the SRS disposal vaults that meet the requirements of Chap. III of the U.S. Department of Energy Order 5820.2A: The vaults considered are the low-activity waste (LAW) vaults, the intermediate-level non-tritium (ILNT) vaults. and the intermediate-level tritium (ILT) vaults. (3) The radioactive limits of a commercial mixed waste disposal facility

Radioactive Bench-scale Steam Reformer Demonstration of a Monolithic Steam Reformed Mineralized Waste Form for Hanford Waste Treatment Plant Secondary Waste - 12306

Energy Technology Data Exchange (ETDEWEB)

Evans, Brent; Olson, Arlin; Mason, J. Bradley; Ryan, Kevin [THOR Treatment Technologies, LLC - 106 Newberry St. SW, Aiken, SC 29801 (United States); Jantzen, Carol; Crawford, Charles [Savannah River Nuclear Solutions (SRNL), LLC, Aiken, SC 29808 (United States)

2012-07-01

Hanford currently has 212,000 m{sup 3} (56 million gallons) of highly radioactive mixed waste stored in the Hanford tank farm. This waste will be processed to produce both high-level and low-level activity fractions, both of which are to be vitrified. Supplemental treatment options have been under evaluation for treating portions of the low-activity waste, as well as the liquid secondary waste from the low-activity waste vitrification process. One technology under consideration has been the THOR{sup R} fluidized bed steam reforming process offered by THOR Treatment Technologies, LLC (TTT). As a follow-on effort to TTT's 2008 pilot plant FBSR non-radioactive demonstration for treating low-activity waste and waste treatment plant secondary waste, TTT, in conjunction with Savannah River National Laboratory, has completed a bench scale evaluation of this same technology on a chemically adjusted radioactive surrogate of Hanford's waste treatment plant secondary waste stream. This test generated a granular product that was subsequently formed into monoliths, using a geo-polymer as the binding agent, that were subjected to compressibility testing, the Product Consistency Test and other leachability tests, and chemical composition analyses. This testing has demonstrated that the mineralized waste form, produced by co-processing waste with kaolin clay using the TTT process, is as durable as low-activity waste glass. Testing has shown the resulting monolith waste form is durable, leach resistant, and chemically stable, and has the added benefit of capturing and retaining the majority of Tc-99, I-129, and other target species at high levels. (authors)

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

National Low-Level Waste Management Program final summary report of key activities and accomplishments for fiscal year 1997

International Nuclear Information System (INIS)

Rittenberg, R.B.

1998-03-01

The US Department of Energy (DOE) has responsibilities under the Low-Level Radioactive Waste Policy Amendments Act of 1985 to assist states and compacts in their siting and licensing efforts for low-level radioactive waste disposal facilities. The National Low-Level Waste Management Program (NLLWMP) is the element of the DOE that performs the key support activities under the Act. The NLLWMP's activities are driven by the needs of the states and compacts as they prepare to manage their low-level waste under the Act. Other work is added during the fiscal year as necessary to accommodate new requests brought on by status changes in states' and compacts' siting and licensing efforts. This report summarizes the activities and accomplishments of the NLLWMP during FY 1997

The IRIS Incinerator at Cea-Valduc assessment after more than one ton and a half of active waste incineration

International Nuclear Information System (INIS)

Chateauvieux, H.; Guiberteau, P.; Longuet, T.; Lemort, F.; Lannaud, J.; Lorich, M.; Medzadourian, M.

2000-01-01

During the operation of its facilities, the Valduc Research Center produces alpha-contaminated solid waste. An incineration facility has been built to treat the most contaminated combustible waste. The process selected for waste incineration is the IRIS process, which was developed by the CEA at the Marcoule Nuclear Research Center. The Valduc Center asked SGN to build the incineration facility. The facility was commissioned in late 1996, and inactive waste incineration campaigns were run during more than 2,500 hours in 1997-1998. Active commissioning of the facility was performed in March 1999. Since then five campaigns with active waste and a complete plutonium cleaning session have been carried out, the results of which are given in the paper. The Valduc incinerator is the first industrial active application of the IRIS process. (authors)

Where, when, how: the place of radioactive wastes in France. Andra, 1998 activity report

International Nuclear Information System (INIS)

1998-01-01

The 1998 activity report of the French national agency of radioactive wastes (Andra) presents successively: the role and missions of the Andra (history, status of radioactive wastes in France, surface storage and know-how, underground research laboratories, site selection and public information); the aspects of safety (inventory, identification and labelling of wastes, environmental policy, public relation, safety rules and reports, information storage); the scientific programs (collaborations, financing, site studies, rock mechanics and reversibility of storage, design of storage facilities, services); financial report. (J.S.)

The impact of anaerobic microorganisms activities in ruminant waste and coal

Science.gov (United States)

Harlia, Ellin; Hamdani, H.; Winantris, Kurnani, Tb. B. A.; Hidayati, Y. A.; Marlina, E. T.; Rahmah, K. N.; Arief, H.; Ridwan, R.; Joni, I. M.

2018-02-01

Ruminant (dairy cattle, beef cattle and buffalo) waste from intensive farming concentrated in highly populated areas when stacked and accumulated in certain heights and in anaerobic condition, may produce Green House Gases (GHGs) which lead to global warming. This condition is generated through fermentation by microorganism contained in livestock waste and biogenic activities on coal. The GHGs include CH4 (methane), CO2 (carbon dioxide) and N2O (nitrous oxide). The GHG emission should be early monitored to minimize greater problems. In the other hand, methane can be utilized as an environmental friendly energy after stored as biogas on digester. The aim of this research is to detect how much GHGs formed from ruminant waste and biogenic activities on coal, which can be utilized as an alternative energy. This research conducted as an explorative study utilizing dairy cattle feces, beef cattle feces, buffalo feces and three types of coal: lignite, bituminous and sub-bituminous, which is separately added into medium 98-5 made from mixture of agar medium and chemical components in powder and crystal form diluted with distilled water and rumen liquid, with six repetitions. Each sample was stored into 250 mL anaerobic digester, observed weekly for period of 4 weeks, analyzed by Gas Chromatography (GC-A14). The result showed that GHGs: CH4, CO2 and N2O were found in all samples. Anticipation of GHGs formation to avoid air pollution is by utilizing livestock waste and coal in aerobic condition or in anaerobic condition through digester.

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