Restoration of environments with radioactive residues. Papers and discussions. Proceedings of an international symposium

International Nuclear Information System (INIS)

2000-01-01

After the use of radioactive substances or the application of nuclear energy, radioactive residues may remain in the environment and may give rise to radiation exposure of people. Radioactive residues can originate from several sources. They may be remnants following the termination of a practice such as the decommissioning of a nuclear power plant. Occasionally, residues can derive from the accumulation of radionuclides from normal discharges to the environment of radioactive effluents from practices. Most commonly, they are the result of human activities that have been performed in the past without proper regard for the current international radiation protection requirements. They can also be the consequence of accidents that have released radioactive material to the environment. Radioactive residues are also generated by nature, e.g. in natural deposits of radioactive material found in the earth. Spring waters convey these materials. No matter what the cause of radioactive residues may be, there is the question of whether any restoration of the affected environment is required and, if so, to what extent it should be performed. The International Symposium on Restoration of Environments with Radioactive Residues was devoted to discussing these questions and to fostering the exchange of information on this subject. The Symposium explored five main topics: global overview of the problem; restoration principles and criteria; case studies of actual radiological assessments; a critical analysis of the case studies; and the role of public participation in the decision aiding and decision making processes. The Programme Committee of the Symposium accepted a number of contributed papers and posters for consideration at the Symposium, and these were published shortly before the Symposium. In early 2000, the IAEA released as Working Material a draft, unedited compilation of the present Proceedings Series publication. The present publication, which constitutes the record of

Characterization on incineration residue of radioactive solid wastes

International Nuclear Information System (INIS)

Katoh, Kiyoshi; Hirayama, Katsuyoshi; Kato, Akira.

1989-01-01

Characterization was carried out on incineration residue discharged from the radioactive solid waste incineration unit (capacity, 100 kg/h) in use at the Tokai Research Establishment of Japan Atomic Energy Research Institute (JAERI) to obtain basic data for investigating solidification methods of the residue. The characterized residue was taken from furnace and a primary ceramic filter of the incineration unit which incinerates combustible solid wastes generated at JAERI and the outside organizations. Items of characterization involve a particle size distribution, misplaced materials content, ignition loss, chemical composition and radioactivity of nuclides in the ash. As the results, the size of ash sampled from the furnace distributed a wide range, with about 35∼60 % of ash smaller than 5 mm and about 10∼25 % of massive one larger than 30 mm (max. size: ∼130 mm). The ignition loss was 2∼3 %. The chemical compositions of the ash were mainly SiO 2 , Fe 2 O 3 , CaO and Al 2 O 3 . The specific activities of the ash were about 0.4∼4 x 10 3 Bq/g, and principal contaminants were 60 Co and 137 Cs. (author)

Summary of the engineering assessment of radioactive sands and residues, Lowman Site, Lowman, Idaho

International Nuclear Information System (INIS)

1981-09-01

Ford, Bacon and Davis Utah Inc. has reevaluated the Lowman site in order to revise the December 1977 engineering assessment of the problems resulting from the existence of radioactive sands and residues at Lowman, Idaho. This engineering assessment has included the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of radioactive sands and residues and radiation exposures of individuals and nearby populations, the investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas released from the 191,000 tons of radioactive sands, residues, and contaminated soils at the Lowman site constitutes the most significant environmental impact, although windblown radioactive sands and external gamma radiation also are factors

Radioactive consumer products

International Nuclear Information System (INIS)

Sato, Otomaru

1981-01-01

Present situation of utilizing the radioactive consumer products and exposure dose were reviewed with published data. Practically, consumer products are divided into three categories, (1) radioactive nuclides intentionally incorporated into radioluminous dye, ionization chambers for smoke detector, eliminator of static electricity, and glow lamp (2) natural radioactive nuclides contained in false teeth, porcelain, glass, and gas mantle (3) natural radioactive nuclides accumulated as industrial waste at the consumption of coal, petroleum, and natural gas or in fertilizer and materials for construction. (Nakanishi, T.)

Long-term residual radioactivity in an intermediate-energy proton linac

CERN Document Server

Blaha, J; Silari, M; Vollaire, J

2014-01-01

A new 160 MeV H−H− linear accelerator (LINAC4) is being installed at CERN to replace the present 50 MeV LINAC2 as proton injector of the PS Booster (PSB). During operation, the accelerator components will be activated by the beam itself and by the secondary radiation field. Detailed Monte Carlo simulations, for various beam energies and several decay times, were performed to predict the residual radioactivity in the main accelerator components and to estimate the residual dose rate inside the tunnel. The results of this study will facilitate future dismantling, handling and storage of the activated parts and consequently minimize the radiation dose to involved workers. The component activation was also compared with the exemption limits given in the current Swiss legislation and to the CERN design values, in order to make predictions for the future storage and disposal of radioactive waste. The airborne radioactivity induced by particles escaping the beam dump and the activation of the beam dump cooling w...

Inventory of sites used to develop residual radioactivity criteria

International Nuclear Information System (INIS)

Ronca-Battista, M.; Hardeman, J.C. Jr.

1986-01-01

The US Environmental Protection Agency (EPA), in conjunction with the National Conference of Radiation Control Program Directors (CRCPD), has compiled an inventory of never licensed or otherwise poorly documented sites that may be contaminated with radioactive materials. This effort is in support of the EPA's development of radiation protection criteria for residual radioactivity at decommissioned sites. The inventory will help to establish the range of circumstances for which criteria are needed, as well as the suitability of candidate criteria for actual situations. The information will also be used to develop model sites and facilities for analyzing technical and economic feasibility of residual radioactivity criteria and to assess costs and benefits of alternate criteria. Relevant information about each site, such as radionuclides, waste forms, and quantities present will be included in the inventory when such information is available. The CRCPD has requested that each State radiation control agency furnish the information for the inventory. The inventory supplements the relatively extensive documentation of sites regulated by Federal or State agencies with information on old or unlicensed sites, such as old waste storage sites or radium ore processing facilities

Status policy and criteria for the remediation of sites with radioactive residues in China

International Nuclear Information System (INIS)

Yamin, Z.

1999-01-01

This paper introduces the status policy and criteria for remediation of sites with radioactive residues in China. We deal with the sites in difference patterns according to their circumstances. For the sites related with the decommissioning of the nuclear fuel cycle facilities, the programs for environmental restoration must be reviewed and approved by the State Environmental Protection Administration (SEPA). And the radioactive waste resulting from these facilities should be collected and eventually disposed of at the regional disposal repositories built by the country. For the sites related with use of radionuclides in medicine, research and industry, as well as the small scale extraction and processing of materials containing natural radionuclides, the provincial environmental authority is responsible for approving the restoration projects. These radioactive wastes should finally be sent to the special radioactive waste repositories built by the provincial environmental authorities. So far 21 waste repositories have been built in some provinces. More then 10 sites with radioactive residues have been restored. The standards for general public dose limit and soil residual radionuclides content have been established. (author)

Methodology for determining acceptable residual radioactive contamination levels at decommissioned nuclear facilities/sites

International Nuclear Information System (INIS)

Watson, E.C.; Kennedy, W.E. Jr.; Hoenes, G.R.; Waite, D.A.

1979-01-01

The ultimate disposition of decommissioned nuclear facilities and their surrrounding sites depends upon the degree and type of residual contamination. Examination of existing guidelines and regulations has led to the conclusion that there is a need for a general method to derive residual radioactive contamination levels that are acceptable for public use of any decommissioned nuclear facility or site. This paper describes a methodology for determining acceptable residual radioactive contamination levels based on the concept of limiting the annual dose to members of the public. It is not the purpose of this paper to recommend or even propose dose limits for the exposure of the public to residual radioactive contamination left at decommissioned nuclear facilities or sites. Unrestricted release of facilities and/or land is based on the premise that the potential annual dose to any member of the public using this property from all possible exposure pathways will not exceed appropriate limits as may be defined by Federal regulatory agencies. For decommissioned land areas, consideration should be given to people living directly on previously contaminated areas, growing crops, grazing food animals and using well water. Mixtures of radionuclides in the residual contamination representative of fuel reprocessing plants, light water reactors and their respective sites are presented. These mixtures are then used to demonstrate the methodology. Example acceptable residual radioactive contamination levels, based on an assumed maximum annual dose of one millirem, are calculated for several selected times following shutdown of a facility. It is concluded that the methodology presented in this paper results in defensible acceptable residual contamination levels that are directly relatable to risk assessment with the proviso that an acceptable limit to the maximum annual dose will be established. (author)

Radioactive wastes and residues: government participation in a control policy

International Nuclear Information System (INIS)

Gelli, Guido

1993-01-01

This paper discusses the politic aspects of the State participation in inspection and control of the radioactive wastes residues with the supervise of Brazilian Nuclear Energy Commission (CNEN), by a national program

Conceptual framework and technical basis for clearance of materials with residual radioactivity

International Nuclear Information System (INIS)

Chen, S.Y.

1997-01-01

The primary impediment to the release of materials containing residual radioactivity from a controlled environment is the lack of a suitable framework within which release standards can be developed. Recently, the 'risk-based' approach has been proposed as an appropriate means of setting standards. The term 'clearance' has been introduced by the International Atomic Energy Commission as a regulatory process for releasing radioactive materials posing trivial risks. A 'trivial' risk level has been determined to be on the order of 10[sup -6] to 10[sup -7] annual risk to an exposed individual, and a population risk of no more than 0.1 annually. Under these strict constraints, exposure scenarios may account for processing, disposal, and product end-use of materials. This paper discusses these scenarios and also describes the technical basis for deriving release levels under the suggested risk (or dose) constraints

Summary of industrial impacts from recycled radioactive scrap metals

International Nuclear Information System (INIS)

Dehmel, J.-C.; Harrop, J.; MacKinney, J.A.

1995-01-01

During operation, decontamination, and dismantlement, nuclear facilities are generating significant quantities of radioactive scrap metal (RSM). Future decommissioning will generate even more RSM. The petroleum industry also generates RSM in the form of equipment contaminated with naturally occurring radioactivity. Finally, the accidental melting of radioactive sources in steel mills has generated smaller amounts of contaminated metals. Steel mills, smelters, and foundries could recycle these materials, which might then appear in finished products or as feedstocks used by other industries. If introduced in this manner, residual radioactivity can adversely affect the performance of certain products. Such products include computers and other devices that rely on integrated circuits. The most important effect of residual radioactivity on integrated circuits is a phenomenon known as 'single event upsets or soft errors.' Radioactivity can also adversely affect the performance of products such as photographic film and components designed to measure the presence of radioactivity. Radioactivity that raises background count-rates to higher levels could affect the performance of radiation monitoring systems and analytical equipment. Higher background count-rates would lead to reduced sensitivity and lower resolution in spectroscopic systems. The computer, photographic, and radiation measurement industries have taken steps to minimize the impact of residual radioactivity on their products. These steps include monitoring manufacturing processes, specifying material acceptance standards, and screening suppliers. As RSM is recycled, these steps may become more important and more costly. This paper characterizes potentially impacted industries and vulnerability and effects due to the presence of residual radioactivity. Finally, the paper describes practices used to limit the impact of residual radioactivity. (J.P.N.)

Cost of the radioactive residues of nuclear power

International Nuclear Information System (INIS)

1986-06-01

The calculation of cost for the management and final storage of spent nuclear fuel and radioactive waste is presented. The continuing Research and Development activities are judged to render simplified designs. The existing and planned systems and and plans are as follows: - transport system for radioactive residues - central intermediate storage of spent fuel, CLAB - processing of spent fuel - final storing of long-lived waste - final storing of reactor waste and decommissioning waste, SFR. The total future cost of the Swedish waste management is calculated to be 39 billion SEK from 1987 and 60 years onwards. 5.3 billion SEK have been spent up to the year 1986. (G.B.)

Analysis on the influence of forest soil characteristics on radioactive Cs infiltration and evaluation of residual radioactive Cs on surfaces.

Science.gov (United States)

Mori, Yoshitomo; Yoneda, Minoru; Shimada, Yoko; Fukutani, Satoshi; Ikegami, Maiko; Shimomura, Ryohei

2018-03-29

We investigated the depth profiles of radioactive Cs, ignition loss, and cation exchange capacity (CEC) in five types of forest soils sampled using scraper plates. We then simulated the monitored depth profiles in a compartment model, taking ignition loss as a parameter based on experimental results showing a positive correlation between ignition loss and the CEC. The calculated values were comparable with the monitored values, though some discrepancy was observed in the middle of the soil layer. Based on decontamination data on the surface dose rate and surface contamination concentration, we newly defined a surface residual index (SRI) to evaluate the residual radioactive Cs on surfaces. The SRI value tended to gradually decrease in forests and unpaved roads and was much smaller in forests and on unpaved roads than on paved roads. The radioactive Cs was assumed to have already infiltrated underground 18 months after the nuclear power plant accident, and the sinking was assumed to be ongoing. The SRI values measured on paved roads suggested that radioactive Cs remained on the surfaces, though a gradual infiltration was observed towards the end of the monitoring term. The SRI value is thought to be effective in grasping the rough condition of residual radioactive Cs quickly at sites of decontamination activity in the field. The SRI value may be serviceable for actual contamination works after further research is done to elucidate points such as the relation between the SRI and the infiltration of radioactive Cs in various types of objects.

Management of NORM Residues

International Nuclear Information System (INIS)

2013-06-01

The IAEA attaches great importance to the dissemination of information that can assist Member States in the development, implementation, maintenance and continuous improvement of systems, programmes and activities that support the nuclear fuel cycle and nuclear applications, and that address the legacy of past practices and accidents. However, radioactive residues are found not only in nuclear fuel cycle activities, but also in a range of other industrial activities, including: - Mining and milling of metalliferous and non-metallic ores; - Production of non-nuclear fuels, including coal, oil and gas; - Extraction and purification of water (e.g. in the generation of geothermal energy, as drinking and industrial process water; in paper and pulp manufacturing processes); - Production of industrial minerals, including phosphate, clay and building materials; - Use of radionuclides, such as thorium, for properties other than their radioactivity. Naturally occurring radioactive material (NORM) may lead to exposures at some stage of these processes and in the use or reuse of products, residues or wastes. Several IAEA publications address NORM issues with a special focus on some of the more relevant industrial operations. This publication attempts to provide guidance on managing residues arising from different NORM type industries, and on pertinent residue management strategies and technologies, to help Member States gain perspectives on the management of NORM residues

Long-term residual radioactivity in an intermediate-energy proton linac

Science.gov (United States)

Blaha, J.; La Torre, F. P.; Silari, M.; Vollaire, J.

2014-07-01

A new 160 MeV H- linear accelerator (LINAC4) is being installed at CERN to replace the present 50 MeV LINAC2 as proton injector of the PS Booster (PSB). During operation, the accelerator components will be activated by the beam itself and by the secondary radiation field. Detailed Monte Carlo simulations, for various beam energies and several decay times, were performed to predict the residual radioactivity in the main accelerator components and to estimate the residual dose rate inside the tunnel. The results of this study will facilitate future dismantling, handling and storage of the activated parts and consequently minimize the radiation dose to involved workers. The component activation was also compared with the exemption limits given in the current Swiss legislation and to the CERN design values, in order to make predictions for the future storage and disposal of radioactive waste. The airborne radioactivity induced by particles escaping the beam dump and the activation of the beam dump cooling water circuit were also quantified. The aim of this paper is to provide data of sufficiently general interest to be used for similar studies at other intermediate-energy proton accelerator facilities.

Long-term residual radioactivity in an intermediate-energy proton linac

International Nuclear Information System (INIS)

Blaha, J.; La Torre, F.P.; Silari, M.; Vollaire, J.

2014-01-01

A new 160 MeV H − linear accelerator (LINAC4) is being installed at CERN to replace the present 50 MeV LINAC2 as proton injector of the PS Booster (PSB). During operation, the accelerator components will be activated by the beam itself and by the secondary radiation field. Detailed Monte Carlo simulations, for various beam energies and several decay times, were performed to predict the residual radioactivity in the main accelerator components and to estimate the residual dose rate inside the tunnel. The results of this study will facilitate future dismantling, handling and storage of the activated parts and consequently minimize the radiation dose to involved workers. The component activation was also compared with the exemption limits given in the current Swiss legislation and to the CERN design values, in order to make predictions for the future storage and disposal of radioactive waste. The airborne radioactivity induced by particles escaping the beam dump and the activation of the beam dump cooling water circuit were also quantified. The aim of this paper is to provide data of sufficiently general interest to be used for similar studies at other intermediate-energy proton accelerator facilities

Residues of 14C-cyolane in cottonseed products

International Nuclear Information System (INIS)

Zayed, S.M.A.D.; Osman, A.Z.; Fakhr, I.M.I.; Bahig, M.E.

1981-01-01

The systemic insecticide cyolane [2-(0,0-diethylphosphoryl)-imino-1,3-dithiolane] was prepared from 14 C-ethanol, phosphorus oxychloride and 2-amino-1,3-dithiolane. Cotton plants were treated with two applications of the insecticide under conditions of local agricultural practice. 14 C-residues in the crude oil and cake of the harvested cotton seeds amounted to 1.63 and 0.014 mg/kg respectively. About 50% of the 14 C-activity present in the crude oil was found to be eliminated by simulated commercial processes used for refining of the oil. Alkali treatment and bleaching removed 16% and 25% of the radioactive residues respectively. Winterization of the bleached oil at 5-7 0 C for 3 days effected a further elimination of 13%. 14 C-residues in the cotton seed products and in the samples of the refined oil were characterized and the main constituents identified using chromatographic techniques. (author)

Some aspects of the technology improvement for heat reprocessing of the combustible radioactive wastes and ash residue conditioning

International Nuclear Information System (INIS)

Dmitriev, S.A.; Lifanov, F.A.; Knyazev, I.A.; Buravchenko, N.N.; Sobolev, I.A.; Mamaev, L.A.; Alekseev, A.N.; Simagina, O.S.

1991-01-01

The results of studies devoted to increasing the efficiency of thermal reprocessing (combustion) of organic low- and intermediate-level radioactive wastes are given. The new most efficient three-stage process including: 1) gasification and pyrolysis of an organic material with volatile product release, 2) coke residual combustion, ash and noncombustible materials melting, 3) combustion of volatile products of thermal decomposition is developed on the basis of the analysis of solid radioactive waste combustion schemes, mathematical simulation and laboratory studies. Experimental bed, in which these processes are realized, is created. The results obtained in it have allowed one to begin designing of the pilot-commercial plant with shaft furnace having the capacity up to 200 kg/h for solid wastes

Radioactivity in Dutch consumer products

CERN Document Server

Janssen, M P M

2002-01-01

This study took place within the framework of a general update of the average radiation dose for the Dutch population. It focuses on consumer products in which radionuclides have been intentionally incorporated and on radiation-emitting devices that can be supplied to members of the public without special surveillance. Eleven consumer products were studied in more detail. The radiation from these products determined 90% of the total collective dose due to consumer products in the Netherlands in 1988. Individual and collective doses are presented here for each product. The total collective dose has decreased from 130 personSv in 1988 to 4.6 personSv at present. This reduction was attributed to: a decrease in the number of radioactive products (gas mantles), lower estimates of the number of radioactive products present in the Netherlands thanks to new information (camera lenses, smoke detectors containing Ra-226), replacement of radioactive by non-radioactive products (gas mantles, dental protheses), and a lowe...

Residual radioactive material guidelines: Methodology and applications

International Nuclear Information System (INIS)

Yu, C.; Yuan, Y.C.; Zielen, A.J.; Wallo, A. III.

1989-01-01

A methodology to calculate residual radioactive material guidelines was developed for the US Department of Energy (DOE). This methodology is coded in a menu-driven computer program, RESRAD, which can be run on IBM or IBM-compatible microcomputers. Seven pathways of exposure are considered: external radiation, inhalation, and ingestion of plant foods, meat, milk, aquatic foods, and water. The RESRAD code has been applied to several DOE sites to calculate soil cleanup guidelines. This experience has shown that the computer code is easy to use and very user-friendly. 3 refs., 8 figs

Report on residual radioactive materials on public or acquired lands of the United States

Energy Technology Data Exchange (ETDEWEB)

None

1979-07-01

This report identifies sites located on public or acquired lands of the United States containing residual radioactive materials and other radioactive waste (excluding waste resulting from the production of electric energy) and was developed in accordance with the provisions of Section 114(b) of Public Law 95-604, "Uranium Mill Tailings Radiation Control Act of 1978," enacted on November 8, 1978. Additionally, the report specifies which Federal agency has jurisdiction over such sites and, where appropriate data were available, provides a description of the radiological status of each of the sites reported. For purpose of providing a timely report t o t h e Congress, a termination date of May 31, 1979 was established for the receipt, correlation, and analysis of the input data. As of this date, residual radioactive materials and other radioactive waste have been identified by six Federal agencies at 48 sites throughout the United States. Table 1 on page vi provides a summary listing of the number of sites under the jurisdiction of each of these reporting agencies. A cross listing in tabular form by affected state is presented in Table 2 on page viii. Of the 48 sites reported, 36 are located i n three western states - Colorado (27 sites), Wyoming (5 sites), and Utah (4 sites). Based upon t h e data submitted, the sites were categorized into three broad radiological status categories -- controlled, unstabilized, and risk to the public. At controlled sites, the residue is stabilized, access t o t h e site is controlled, the s i t e is well monitored, and does not currently constitute a risk to the public. At sites in the unstabilized category, a probability exists for the spread of contamination. Sites in the risk category contain residue which represents a long-term risk to the public under present conditions. Of the 48 reported sites,. 9 (approximately 19%) could be classified in the controlled category; 38 (approximately 79%) were in the unstabilized category and

Radioactivity in consumer products

Energy Technology Data Exchange (ETDEWEB)

Moghissi, A.A.; Paras, P.; Carter, M.W.; Barker, R.F. (eds.)

1978-08-01

Papers presented at the conference dealt with regulations and standards; general and biological risks; radioluminous materials; mining, agricultural, and construction materials containing radioactivity; and various products containing radioactive sources.

Measurements of the radioactivity of power plant by-products processed into construction materials

International Nuclear Information System (INIS)

Marcinkowski, S.A.; Dudelewski, H.A.

1992-01-01

The subject of the recycling of residual products comprising, inter alia, fly ash and slags accuring from the combustion of black and brown coal in modern coal dust boilers in the power industry has been topical for a number of years. Numerous discussions and articles in technical periodicals and the daily press have revolved around the problem of the radioactivity of construction materials or construction elements obtained from fly ash or slags of power plant. In Poland, this was a forbidden subject until the publication in 1980 by the Warsaw institute of construction technology of standard no. 234 entitled: 'Recommendations for establishing the natural radioactivity of products processed into construction materials'. (orig.) [de

Manual for implementing residual radioactivity guidelines

International Nuclear Information System (INIS)

Gilbert, T.L.; Eckerman, K.F.; Hansen, W.R.; Healy, J.W.; Kennedy, W.E.; Napier, B.A.; Solday, J.K.

1986-01-01

The US Department of Energy (DOE) has recently issued guidelines for residual radioactivity at Formerly Utilized Sites Remedial Action Program (FUSRAP) and remote Surplus Facilities Management Program (SFMP) sites. A manual for implementing these guidelines has been prepared jointly by four DOE laboratories (ANL, LANL, ORNL, and PNL) and is being issued as a supplement to the guidelines. The manual presents procedures and tables for deriving site-specific guidelines for levels of residual radionuclide concentrations in soil that must not be exceeded if a site is to be released for unrestricted use. Guidance for implementing DOE ALARA policy for remedial actions is also included. The concentration factor method is used in the pathway analysis for deriving soil guidelines. The analysis has been structured in a manner that explicitly identifies all of the factors involved. Tables are provided for dose-conversion factors and pathway factors from which environmental transport factors for each radionuclide and pathway may be calculated. The scenarios used for deriving the environmental transport factors and dose conversion factors, and the manner in which the information provided in the manual is used to derive site-specific soil guidelines will be presented

Synthesis and evaluation of radioactive and fluorescent residualizing labels for identifying sites of plasma protein catabolism

International Nuclear Information System (INIS)

Maxwell, J.L.; Baynes, J.W.; Thorpe, S.R.

1986-01-01

Inulin and lactose were each coupled to tyramine by reductive amination with NaBH 3 CN and the tyramine then labeled with 125 I. Dilactitol- 125 I-tyramine (DLT) and inulin- 125 I-tyramine (InTn) were coupled by reductive amination and cyanuric chloride, respectively, to asialofetuin (ASF), fetuin and rat serum albumin (RSA). Attachment of either label had no effect on the circulating half-lives of the proteins. Radioactivity from labeled ASF was recovered in rat liver (> 90%) by 1 h post-injection and remained in liver with half-lives of 2 and 6 days, respectively, for the DLT and InTn labels. Whole body recoveries of radioactivity from DLT- and InTn labels. Whole body recoveries of radioactivity from DLT- and InTn-labeled RSA were 5 and 6.5 days, respectively, again indicating that the larger glycoconjugate label residualized more efficiently in cells following protein degradation. (Lactitol) 2 -N-CH 2 -CH 2 -NH-fluroescein (DLF) was also coupled to ASF by reductive amination and recovered quantitatively in liver at 1 h post-injection. Native ASF was an effective competitor for clearance of DLF-ASF from the circulation. Fluorescent degradation products were retained in liver with a half-life of 1.2 days. Residualizing fluorescent labels should be useful for identification and sorting of cells active in the degradation of plasma proteins

Measurement of residual radioactivity in cooper exposed to high energy heavy ion beam

Energy Technology Data Exchange (ETDEWEB)

Kim, Eunjoo; Nakamura, Takashi [Tohoku Univ., Sendai (Japan). Cyclotron and Radioisotope Center; Uwamino, Yoshitomo; Ito, Sachiko; Fukumura, Akifumi

1999-03-01

The residual radioactivities produced by high energy heavy ions have been measured using the heavy ion beams of the Heavy Ion Medical Accelerator (HIMAC) at National Institute of Radiological Sciences. The spatial distribution of residual radioactivities in 3.5 cm, 5.5 cm and 10 cm thick copper targets of 10 cm x 10 cm size bombarded by 290 MeV/u, 400 MeV/u-{sup 12}C ion beams and 400 MeV/u-{sup 20}Ne ion beam, respectively, were obtained by measuring the gamma-ray activities of 0.5 mm thick copper foil inserted in the target with a high purity Ge detector after about 1 hour to 6 hours irradiation. (author)

Energies and media nr 28. Uranium mining exploitations and residues. Uranium mines in Niger. Depleted uranium as a by-product of enrichment

International Nuclear Information System (INIS)

2009-02-01

After some comments on recent events in the nuclear sector in different countries (USA, China, India, UK, Sweden, Italy and France), this publication addresses the issue of uranium mining exploitations and of their residues. It comments the radioactivity in mining areas, briefly discusses the issue of low doses, describes the uranium ore and its processing, indicates which are the various residues of the mining activity (sterile uncovered tailings, non exploitable mineralized rocks, ore and residue processing, residue radioactivity, mine closing down, witnesses on health in ancient mines). Some reflections are stated about uranium mines in Niger, and about depleted uranium as a by-product of the enrichment activity

Manual for implementing residual radioactive material guidelines using RESRAD, Version 5.0

Energy Technology Data Exchange (ETDEWEB)

Yu, C.; Zielen, A.J.; Cheng, J.J. [and others

1993-09-01

This manual presents information for implementing US Department of Energy (DOE) guidelines for residual radioactive material. It describes the analysis and models used to derive site-specific guidelines for allowable residual concentrations of radionuclides in soil and the design and use of the RESRAD computer code for calculating doses, risks, and guideline values. It also describes procedures for implementing DOE policy for reducing residual radioactivity to levels that are as low as reasonably achievable. Two new pathways, radon inhalation and soil ingestion, have been added to RESRAD. Twenty-seven new radionuclides have also been added, and the cutoff half-life for associated radionuclides has been reduced to six months. Other major improvements to the RESRAD code include the ability to run sensitivity analyses, the addition of graphical output, user-specified dose factors, updated databases, an improved groundwater transport model, optional input of a groundwater concentration and a solubility constant, special models for tritium and carbon-14, calculation of cancer incidence risk, and the use of a mouse with menus.

Manual for implementing residual radioactive material guidelines using RESRAD, Version 5.0

International Nuclear Information System (INIS)

Yu, C.; Zielen, A.J.; Cheng, J.J.

1993-09-01

This manual presents information for implementing US Department of Energy (DOE) guidelines for residual radioactive material. It describes the analysis and models used to derive site-specific guidelines for allowable residual concentrations of radionuclides in soil and the design and use of the RESRAD computer code for calculating doses, risks, and guideline values. It also describes procedures for implementing DOE policy for reducing residual radioactivity to levels that are as low as reasonably achievable. Two new pathways, radon inhalation and soil ingestion, have been added to RESRAD. Twenty-seven new radionuclides have also been added, and the cutoff half-life for associated radionuclides has been reduced to six months. Other major improvements to the RESRAD code include the ability to run sensitivity analyses, the addition of graphical output, user-specified dose factors, updated databases, an improved groundwater transport model, optional input of a groundwater concentration and a solubility constant, special models for tritium and carbon-14, calculation of cancer incidence risk, and the use of a mouse with menus

Derivation of uranium residual radioactive material guidelines for the former Alba Craft Laboratory site, Oxford, Ohio

International Nuclear Information System (INIS)

Nimmagadda, M.; Faillace, E.; Yu, C.

1994-01-01

Residual radioactive material guidelines for uranium were derived for the former Alba Craft Laboratory site in Oxford, Ohio. This site has been identified for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy (DOE). Single nuclide and total uranium guidelines were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of the former Alba Craft Laboratory site should not exceed a dose of 30 mrem/yr following remedial action for the current use and likely future use scenarios or a dose of 100 mrem/yr for less likely future use scenarios (Yu et al. 1993). The DOE residual radioactive material guideline computer code, RESRAD, which implements the methodology described in the DOE manual for implementing residual radioactive material guidelines, was used in this evaluation

Assessment of radioactive residues arising from radiolabel instability in a multiple dose tissue distribution study in rats

International Nuclear Information System (INIS)

Slatter, J.G.; Sams, J.P.; Easter, J.A.

2003-01-01

Our study objectives were to quantitatively determine the effect of radiolabel instability on terminal phase radioactive tissue residues in a multiple dose tissue distribution study, to quantitatively compare tissue residue artifacts (non drug-related radioactivity) from two chemically-distinct radiolabel locations, and to conduct a definitive multiple dose tissue distribution study using the better of the two radiolabeled compounds. We compared the excretion and tissue distribution in rats of [ 14 C]linezolid, radiolabeled in two different locations, after 7 consecutive once daily [ 14 C] oral doses. The radiolabels were in the acetamide (two carbon) and oxazolidinone (isolated carbon) functional groups. Terminal phase tissue residue and excretion data were compared to data from rats dosed orally with [ 14 C]sodium acetate. Drug-related radioactivity was excreted rapidly over 24 h. After a single dose, the acetamide and oxazolidinone radiolabel sites both gave 3% of dose as exhaled 14 CO 2 . After 7 daily [ 14 C] oral doses, terminal phase radioactive tissue residues were higher from the acetamide radiolabel, relative to the oxazolidinone radiolabel, and were primarily not drug-related. In the definitive tissue distribution study, low concentrations of drug-related radioactivity in skin and thyroid were observed. We conclude that although small amounts of radiolabel instability do not significantly affect single dose tissue radioactivity C max and area under the curve (AUC), artifacts arising from radiolabel instability can prolong the apparent terminal phase half life and complicate study data interpretation. When possible, it is always preferable to use a completely stable radiolabel site. (author)

Assessment of radioactive residues arising from radiolabel instability in a multiple dose tissue distribution study in rats

Energy Technology Data Exchange (ETDEWEB)

Slatter, J.G. [Pharmacia Corp., Peapack, NJ (United States); Sams, J.P.; Easter, J.A. [Pharmacia Corp., Kalamazoo, MI (United States)] [and others

2003-05-01

Our study objectives were to quantitatively determine the effect of radiolabel instability on terminal phase radioactive tissue residues in a multiple dose tissue distribution study, to quantitatively compare tissue residue artifacts (non drug-related radioactivity) from two chemically-distinct radiolabel locations, and to conduct a definitive multiple dose tissue distribution study using the better of the two radiolabeled compounds. We compared the excretion and tissue distribution in rats of [{sup 14}C]linezolid, radiolabeled in two different locations, after 7 consecutive once daily [{sup 14}C] oral doses. The radiolabels were in the acetamide (two carbon) and oxazolidinone (isolated carbon) functional groups. Terminal phase tissue residue and excretion data were compared to data from rats dosed orally with [{sup 14}C]sodium acetate. Drug-related radioactivity was excreted rapidly over 24 h. After a single dose, the acetamide and oxazolidinone radiolabel sites both gave 3% of dose as exhaled {sup 14}CO{sub 2}. After 7 daily [{sup 14}C] oral doses, terminal phase radioactive tissue residues were higher from the acetamide radiolabel, relative to the oxazolidinone radiolabel, and were primarily not drug-related. In the definitive tissue distribution study, low concentrations of drug-related radioactivity in skin and thyroid were observed. We conclude that although small amounts of radiolabel instability do not significantly affect single dose tissue radioactivity C{sub max} and area under the curve (AUC), artifacts arising from radiolabel instability can prolong the apparent terminal phase half life and complicate study data interpretation. When possible, it is always preferable to use a completely stable radiolabel site. (author)

Residual radioactive contamination at Maralinga and Emu, 1985

International Nuclear Information System (INIS)

Lokan, K.H.

1985-04-01

An account is provided of residual contamination at Maralinga and Emu, in South Australia, where the United Kingdom Atomic Weapons Research Establishment conducted nuclear weapons development trials between 1953 and 1963. Detailed information is presented about contamination levels at sites on the range where radioactive materials were dispersed. Some of these were associated with trials involving natural uranium or short-lived isotopes which are no longer present. There are four sites where plutonium-239 was dispersed in substantial quantities from minor trials and information is presented about its distribution. Much of this material has been diluted by mixing with local soil, but there is a significant quantity of material present in the form of contaminated fragments, particularly at Taranaki. A considerable quantity of uranium-235 is also present at Taranaki. An assessment is made of the radiological significance of the dispersed plutonium and it is concluded that the material represents a potential long term hazard while it remains in its present form. Residual radioactivity associated with all but one of the seven major trial sites involving nuclear explosions continues to decay in a predictable way and will in the worst case, fall below levels considered safe for continuous occupancy within about fifty years. One site, Tadje, contains significant concentrations of plutonium over a small area and onsidered to be an additional plutonium-contaminated locality. Measurements of beryllium concentrations in soil are presented

Radioactive waste solidification material

International Nuclear Information System (INIS)

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

1992-01-01

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

Derivation of guidelines for uranium residual radioactive material in soil at the New Brunswick Site, Middlesex County, New Jersey

International Nuclear Information System (INIS)

Dunning, D.; Kamboj, S.; Nimmagadda, M.; Yu, C.

1996-02-01

Residual radioactive material guidelines for uranium in soil were derived for the New Brunswick Site, located in Middlesex County, New Jersey. This site has been designated for remedial action under the Formerly Utilized Sites Remedial Action Program of the US Department of Energy (DOE). Residual radioactive material guidelines for individual radionuclides of concern and total uranium were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of the New Brunswick Site should not exceed a dose of 30 mrem/yr following remedial action for the current-use and likely future-use scenarios or a dose of 100 mrem/yr for less likely future-use scenarios. The DOE residual radioactive material guideline computer code, RESRAD, was used in this evaluation; RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines. The guidelines derived in this report are intended to apply to the remediation of these remaining residual radioactive materials at the site. The primary radionuclides of concern in these remaining materials are expected to be radium-226 and, to a lesser extent, natural uranium and thorium. The DOE has established generic cleanup guidelines for radium and thorium in soil; however, cleanup guidelines for other radionuclides must be derived on a site-specific basis

The IAEA's functions and policies on the restoration of environments with radioactive residues

International Nuclear Information System (INIS)

Gonzalez, A.J.

2000-01-01

A global regime for the regulation of radiation sources is being established by the international community. A general agreement has already been achieved in the current international radiation protection recommendations, which should be resolutely applied. Protection against radioactive residues delivering relatively low level radiation doses can be regulated within the framework provided by the growing international regime based on these recommendations and composed of international conventions, safety standards and provisions for the application of these standards. It is to be noted, however, that the international safety regime is not more than a provider of a decision aiding mechanism based mainly on a global scientific consensus on radiation protection. Its outcome can only serve as input to a final (usually wider) decision making process, which may take into account societal and other concerns at a national, or even local, level. Many situations involving radioactive residues arise in the human habitant and, therefore, the decision making process should involve the participation of all relevant stakeholders in that habitant, rather than radiation protection specialists alone. The combination of decision aiding regulations based on the international regime being catalyzed under the IAEA and a decision making process that takes account of local circumstances and stakeholders' interests should prevent the current problems in the regulation of radioactive residues and in the restoration of the affected environments

Method of reprocessing radioactive asphalt solidification products

International Nuclear Information System (INIS)

Nakaya, Iwao; Murakami, Tadashi; Miyake, Takafumi; Inagaki, Yuzo.

1986-01-01

Purpose: To obtain heat-stable solidification products and decrease the total volume thereof by modifying the solidified form by the reprocessing of existent radioactive asphalt solidification products. Method: Radioactive asphalt solidification products are heated into a fluidized state. Then, incombustible solvents such as perchloroethylene or trichloroethylene are added to a dissolving tank to gradually dissolve the radioactive asphalt solidification products. Thus, organic materials such as asphalts are transferred into the solvent layer, while inorganic materials containing radioactive materials remain as they are in the separation tank. Then, the inorganic materials containing the radioactive materials are taken out and then solidified, for example, by converting them into a rock or glass form. (Kawakami, Y.)

Consumer Products Containing Radioactive Materials

Science.gov (United States)

Fact Sheet Adopted: February 2010 Health Physics Society Specialists in Radiation Safety Consumer Products Containing Radioactive Materials Everything we encounter in our daily lives contains some radioactive material, ...

Residual radioactivity in the soil of the Semipalatinsk Nuclear Test Site in the former USSR.

Science.gov (United States)

Yamamoto, M; Tsukatani, T; Katayama, Y

1996-08-01

This paper deals with our efforts to survey residual radioactivity in the soil sampled at the Semipalatinsk Nuclear Test Site and at off-site areas in Kazakhstan. The soil was sampled at the hypocenter where the first Soviet nuclear explosion was carried out on 29 August 1949, and at the bank of the crater called "Bolapan," which was formed by an underground nuclear detonation on 15 January 1965 along the Shagan River. As a comparison, other soil was also sampled in the cities of Kurchatov and Almaty. These data have allowed a preliminary evaluation of the contemporary radioactive contamination of the land in and around the test site. At the first nuclear explosion site and at Bolapan, higher than background levels of 239,240Pu with weapons-grade plutonium were detected together with fission and activation products such as 137Cs, 60Co, 152Eu, and 154Eu.

Minimization of zirconium chlorinator residues

International Nuclear Information System (INIS)

Green, G.K.; Harbuck, D.D.

1995-01-01

Zirconium chlorinator residues contain an array of rare earths, scandium, unreacted coke, and radioactive thorium and radium. Because of the radioactivity, the residues must be disposed in special waste containment facilities. As these sites become more congested, and with stricter environmental regulations, disposal of large volumes of wastes may become more difficult. To reduce the mass of disposed material, the US Bureau of Mines (USBM) developed technology to recover rare earths, thorium and radium, and unreacted coke from these residues. This technology employs an HCl leach to solubilize over 99% of the scandium and thorium, and over 90% of the rare earths. The leach liquor is processed through several solvent extraction stages to selectively recover scandium, thorium, and rare earths. The leach residue is further leached with an organic acid to solubilize radium, thus allowing unreacted coke to be recycled to the chlorinator. The thorium and radium waste products, which comprise only 2.1% of the original residue mass, can then be sent to the radioactive waste facility

Radiological survey of the radioactive sands and residues at Lowman, Idaho

International Nuclear Information System (INIS)

Haywood, F.F.; Burden, J.E.; Ellis, B.S.; Loy, E.T.; Shinpaugh, W.H.

1980-08-01

No uranium ore milling was performed at the Lowman site, which is located approximately 0.8 km northeast of the town of Lowman, Idaho. Nevertheless, approximately 80,000 metric tons of radioactive sands and residues from upgrading of heavy minerals by physical processing methods remain on the site grounds. Measurements of external gamma radiation 1 m above the surface showed exposure rates up to 2.4 mR/hr on site, but the exposure rate off site quickly dropped to the background level in all directions. Analysis of surface soil and sediment samples for 226 Ra and 232 Th indicated a limited spread of radioactive material

Radiological dose assessment for residual radioactive material in soil at the clean slate sites 1, 2, and 3, Tonopah Test Range

International Nuclear Information System (INIS)

1997-06-01

A radiological dose assessment has been performed for Clean Slate Sites 1, 2, and 3 at the Tonopah Test Range, approximately 390 kilometers (240 miles) northwest of Las Vegas, Nevada. The assessment demonstrated that the calculated dose to hypothetical individuals who may reside or work on the Clean Slate sites, subsequent to remediation, does not exceed the limits established by the US Department of Energy for protection of members of the public and the environment. The sites became contaminated as a result of Project Roller Coaster experiments conducted in 1963 in support of the US Atomic Energy Commission (Shreve, 1964). Remediation of Clean Slate Sites 1, 2, and 3 is being performed to ensure that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works on a Clean Slate site should not exceed 100 millirems per year. The DOE residual radioactive material guideline (RESRAD) computer code was used to assess the dose. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines (Yu et al., 1993a). In May and June of 1963, experiments were conducted at Clean Slate Sites 1, 2, and 3 to study the effectiveness of earth-covered structures for reducing the dispersion of nuclear weapons material as a result of nonnuclear explosions. The experiments required the detonation of various simulated weapons using conventional chemical explosives (Shreve, 1964). The residual radioactive contamination in the surface soil consists of weapons grade plutonium, depleted uranium, and their radioactive decay products

Radiological dose assessment for residual radioactive material in soil at the clean slate sites 1, 2, and 3, Tonopah Test Range

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-06-01

A radiological dose assessment has been performed for Clean Slate Sites 1, 2, and 3 at the Tonopah Test Range, approximately 390 kilometers (240 miles) northwest of Las Vegas, Nevada. The assessment demonstrated that the calculated dose to hypothetical individuals who may reside or work on the Clean Slate sites, subsequent to remediation, does not exceed the limits established by the US Department of Energy for protection of members of the public and the environment. The sites became contaminated as a result of Project Roller Coaster experiments conducted in 1963 in support of the US Atomic Energy Commission (Shreve, 1964). Remediation of Clean Slate Sites 1, 2, and 3 is being performed to ensure that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works on a Clean Slate site should not exceed 100 millirems per year. The DOE residual radioactive material guideline (RESRAD) computer code was used to assess the dose. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines (Yu et al., 1993a). In May and June of 1963, experiments were conducted at Clean Slate Sites 1, 2, and 3 to study the effectiveness of earth-covered structures for reducing the dispersion of nuclear weapons material as a result of nonnuclear explosions. The experiments required the detonation of various simulated weapons using conventional chemical explosives (Shreve, 1964). The residual radioactive contamination in the surface soil consists of weapons grade plutonium, depleted uranium, and their radioactive decay products.

Influence of residual oxygen-15-labeled carbon monoxide radioactivity on cerebral blood flow and oxygen extraction fraction in a dual-tracer autoradiographic method.

Science.gov (United States)

Iwanishi, Katsuhiro; Watabe, Hiroshi; Hayashi, Takuya; Miyake, Yoshinori; Minato, Kotaro; Iida, Hidehiro

2009-06-01

Cerebral blood flow (CBF), cerebral metabolic rate of oxygen (CMRO(2)), oxygen extraction fraction (OEF), and cerebral blood volume (CBV) are quantitatively measured with PET with (15)O gases. Kudomi et al. developed a dual tracer autoradiographic (DARG) protocol that enables the duration of a PET study to be shortened by sequentially administrating (15)O(2) and C(15)O(2) gases. In this protocol, before the sequential PET scan with (15)O(2) and C(15)O(2) gases ((15)O(2)-C(15)O(2) PET scan), a PET scan with C(15)O should be preceded to obtain CBV image. C(15)O has a high affinity for red blood cells and a very slow washout rate, and residual radioactivity from C(15)O might exist during a (15)O(2)-C(15)O(2) PET scan. As the current DARG method assumes no residual C(15)O radioactivity before scanning, we performed computer simulations to evaluate the influence of the residual C(15)O radioactivity on the accuracy of measured CBF and OEF values with DARG method and also proposed a subtraction technique to minimize the error due to the residual C(15)O radioactivity. In the simulation, normal and ischemic conditions were considered. The (15)O(2) and C(15)O(2) PET count curves with the residual C(15)O PET counts were generated by the arterial input function with the residual C(15)O radioactivity. The amounts of residual C(15)O radioactivity were varied by changing the interval between the C(15)O PET scan and (15)O(2)-C(15)O(2) PET scan, and the absolute inhaled radioactivity of the C(15)O gas. Using the simulated input functions and the PET counts, the CBF and OEF were computed by the DARG method. Furthermore, we evaluated a subtraction method that subtracts the influence of the C(15)O gas in the input function and PET counts. Our simulations revealed that the CBF and OEF values were underestimated by the residual C(15)O radioactivity. The magnitude of this underestimation depended on the amount of C(15)O radioactivity and the physiological conditions. This underestimation

Coal combustion ashes: A radioactive Waste?

International Nuclear Information System (INIS)

Michetti, F.P.; Tocci, M.

1992-01-01

The radioactive substances naturally hold in fossil fuels, such as Uranium and Thorium, after the combustion, are subjected to an increase of concentration in the residual combustion products as flying ashes or as firebox ashes. A significant percentage of the waste should be classified as radioactive waste, while the political strategies seems to be setted to declassify it as non-radioactive waste. (Author)

Evaluation and analysis of the residual radioactivity for the 15UD Pelletron accelerator facility

International Nuclear Information System (INIS)

Sonkawade, R. G.

2007-01-01

For the assessment of radiological impact of the accelerators, it will be better to have the documented information on activation of metal parts of the accelerator components. It is very much essential to get reliable data on these subjects. During acceleration of light ion, the residual radioactivity in the accelerator facility was found near the Analyzing Magnet, single slit, Beam Profile Monitors (BPM), Faraday Cups (FC), bellows, beginning of switching magnet bellows, at the target and the ladder. Study with HPGE detector gives an insight of the formation of the short or long lived radionuclides. The different targets used in the light ion experiment were also monitored and proper decommissioning and decontamination steps were followed. This paper presents the data of residual radioactivity in the 15UD Pelletron accelerator infrastructure. (author)

Costs related to radioactive residues from nuclear power

International Nuclear Information System (INIS)

1988-06-01

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

Derivation of uranium residual radioactive material guidelines for the Shpack site

International Nuclear Information System (INIS)

Cheng, J.J.; Yu, C.; Monette, F.; Jones, L.

1991-08-01

Residual radioactive material guidelines for uranium were derived for the Shpack site in Norton, Massachusetts. This site has been identified for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy (DOE). The uranium guidelines were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of the Shpack site should not exceed a dose of 100 mrem/yr following decontamination. The DOE residual radioactive material guideline computer code, RESRAD, which implements the methodology described in the DOE manual for implementing residual radioactive material guidelines, was used in this evaluation. Three potential scenarios were considered for the site; the scenarios vary with regard to time spent at the site, sources of water used, and sources of food consumed. The results of the evaluation indicate that the basic dose limit of 100 mrem/yr will not be exceeded for uranium (including uranium-234, uranium-235, and uranium-238) within 1000 years, provided that the soil concentration of combined uranium (uranium-234 and uranium-238) at the Shpack site does not exceed the following levels: 2500 pCi/g for Scenario A (recreationist: the expected scenario); 1100 pCi/g for Scenario B (industrial worker: a plausible scenario); and 53 pCi/g for Scenario C (resident farmer using a well water as the only water source: a possible but unlikely scenario). The uranium guidelines derived in this report apply to the combined activity concentration of uranium-234 and uranium-238 and were calculated on the basis of a dose of 100 mrem/yr. In setting the actual uranium guidelines for the Shpack site, DOE will apply the as low as reasonably achievable (ALARA) policy to the decision-making process, along with other factors, such as whether a particular scenario is reasonable and appropriate. 8 refs., 2 figs., 8 tabs

Derivation of residual radioactive material guidelines for the Laboratory for Energy-Related Health Research site

International Nuclear Information System (INIS)

Chapman, T.E.

1993-11-01

Residual radioactive material guidelines were derived for the Laboratory for Energy-Related Health Research (LEHR) Environmental Restoration (ER) site in Davis, California. The guideline derivation was based on a dose limit of 100 mrem/yr. The US Department of Energy (DOE) residual radioactive material guideline computer code was used in this evaluation. This code implements the methodology described in the DOE manual for implementing residual radioactive material guidelines. Three potential site utilization scenarios were considered with the assumption that following ER action, the site will be used without radiological restrictions. The defined scenarios vary with regard to use of the site, time spent at the site, and sources of food consumed. The results of the evaluation indicate that the basic dose limit of 100 mrem/yr will not be exceeded, provided that the soil concentrations of these radionuclides at the LEHR site do not exceed the scenario-specific values calculated by this study. Except for the extent of the contaminated zone (which is very conservative), assumptions used are as site-specific as possible, given available information. The derived guidelines are single- radionuclide guidelines and are linearly proportional to the dose limit used in the calculations. In setting the actual residual soil contamination guides for the LEHR site, DOE will apply the as low as reasonably achievable policy to the decision-making process, along with other factors such as whether a particular scenario is reasonable and appropriate, as well as using site-specific inputs to computer models based on data not yet fully determined

Study of the on line radioactive multicharged ion production

International Nuclear Information System (INIS)

Lecesne, N.

1997-01-01

This work is directly related to the SPIRAL project (Systeme de Production d'Ions Radioactifs Acceleres en Ligne) which will start at GANIL at the end of 1998. The aim of the thesis was to study the on line radioactive multicharged ion beam production stages, i.e. the production and diffusion of the radioactive nuclei in a thick target, their possible transfer up to an ECR ion source and their ionisation. Production cross sections of radioactive neutron rich nuclei, formed by fragmentation of a heavy ion beam in a thick target, were measured. An external target-ECR source system, dedicated to the radioactive noble gases production, and two internal target-ECR source systems, dedicated to the radioactive condensable element production, were built and tested on the SIRa tests bench (Separateur d'Ions Radioactifs). Different detection configurations were elaborated in order to identify the radioactive nuclei and estimate their production yields. Finally, a new method for measuring the overall efficiency of the separator was developed and allowed to study the diffusion properties of radioactive noble gases in various targets. (author)

ENTRIA 2014. Memorandum on the disposal of high-level radioactive residuals

International Nuclear Information System (INIS)

Roehlig, Klaus-Juergen; Walther, Clemens; Bach, Friedrich-Wilhelm

2014-01-01

The memorandum on the disposal of high-level radioactive residuals covers the following issues: description of the problem: a ''wicked problem'', risks and NIMBY, the site selection law, international boundary conditions; disposal strategy and types of facilities: safety and reversibility, long-term surface storage, deep storage; risk and safety; procedural justice and the site selection process; social innovations and the requirement of long-term institutions; conclusion - central stress fields.

Production of high intensity radioactive beams

International Nuclear Information System (INIS)

Nitschke, J.M.

1990-04-01

The production of radioactive nuclear beams world-wide is reviewed. The projectile fragmentation and the ISOL approaches are discussed in detail, and the luminosity parameter is used throughout to compare different production methods. In the ISOL approach a thin and a thick target option are distinguished. The role of storage rings in radioactive beam research is evaluated. It is concluded that radioactive beams produced by the projectile fragmentation and the ISOL methods have complementary characteristics and can serve to answer different scientific questions. The decision which kind of facility to build has to depend on the significance and breadth of these questions. Finally a facility for producing a high intensity radioactive beams near the Coulomb barrier is proposed, with an expected luminosity of ∼10 39 cm -2 s -1 , which would yield radioactive beams in excess of 10 11 s -1 . 9 refs., 3 figs., 7 tabs

Method of producing solidification product of radioactive waste

International Nuclear Information System (INIS)

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

1989-01-01

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

Radioactivity of Consumer Products

Science.gov (United States)

Peterson, David; Jokisch, Derek; Fulmer, Philip

2006-11-01

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

Old radioactive waste storage sites

International Nuclear Information System (INIS)

2008-01-01

After a recall of the regulatory context for the management of old sites used for the storage of radioactive wastes with respect with their activity, the concerned products, the disposal or storage type, this document describes AREVA's involvement in the radioactive waste management process in France. Then, for the different kinds of sites (currently operated sites having radioactive waste storage, storage sites for uranium mineral processing residues), it indicates their location and name, their regulatory status and their control authority, the reference documents. It briefly presents the investigation on the long term impact of uranium mineral processing residues on health and environment, evokes some aspects of public information transparency, and presents the activities of an expertise group on old uranium mines. The examples of the sites of Bellezane (uranium mineral processing residues) and COMURHEX Malvesi (assessment of underground and surface water quality at the vicinity of this installation) are given in appendix

Optimization of heat-liberating batches for ash residue stabilization

International Nuclear Information System (INIS)

Karlina, O.K.; Varlackova, G.A.; Ojovan, M.I.; Tivansky, V.M.; Dmitriev, S.A.

1999-01-01

The ash residue obtained after incineration of solid radioactive waste is a dusting poly-dispersed powder like material that contains radioactive nuclides ( 137 Cs, 90 Sr, 239 Pu, hor ( ellipsis)). Specific radioactivity of the ash can be about 10 5 --10 7 Bq/kg. In order to dispose of the ash, residue shall be stabilized by producing a monolith material. The ash residue can be either vitrified or stabilized into a ceramic matrix. For this purpose the ash residue is mixed with fluxing agents followed by melting of obtained composition in the different type melters. As a rule this requires both significant energy consumption and complex melting equipment. A stabilization technology of ash residue was proposed recently by using heat liberating batches-compositions with redox properties. The ash residue is melted due to exothermic chemical reactions in the mixture with heat-liberating batch that occur with considerable release of heat. Stabilization method has three stages: (1) preparation of a mixture of heating batch and ash residue with or without glass forming batch (frit); (2) ignition and combustion of mixed composition; (3) cooling (quenching) of obtained vitreous material. Combustion of mixed composition occurs in the form of propagation of reacting wave. The heat released during exothermic chemical reactions provides melting of ash residue components and production of glass-like phase. The final product consists of a glass like matrix with embedded crystalline inclusions of infusible ash residue components

Radiological testing of products containing radioactivity

International Nuclear Information System (INIS)

Dixon, D.W.; Knight, A.

1980-01-01

Consumer products containing radioactive substances are tested by NRPB to determine how much radioactive material is likely to be released from a product if it is misused or accidentally damaged. Such testing is briefly described with particular reference to ionisation chamber smoke detectors, liquid crystal display watches illuminated with gaseous tritium light sources and anti-static brushes containing polonium-210 in the form of ceramic microspheres. (U.K.)

Residual radioactivity guidelines for the heavy water components test reactor at the Savannah River Site

International Nuclear Information System (INIS)

Owen, M.B. Smith, R.; McNeil, J.

1997-04-01

Guidelines were developed for acceptable levels of residual radioactivity in the Heavy Water Components Test Reactor (HWCTR) facility at the conclusion of its decommissioning. Using source terms developed from data generated in a detailed characterization study, the RESRAD and RASRAD-BUILD computer codes were used to calculate derived concentration guideline levels (DCGLs) for the radionuclides that will remain in the facility. The calculated DCGLs, when compared to existing concentrations of radionuclides measured during a 1996 characterization program, indicate that no decontamination of concrete surfaces will be necessary. Also, based on the results of the calculations, activated concrete in the reactor biological shield does not have to be removed, and imbedded radioactive piping in the facility can remain in place. Viewed in another way, the results of the calculations showed that the present inventory of residual radioactivity in the facility (not including that associated with the reactor vessel and steam generators) would produce less than one millirem per year above background to a hypothetical individual on the property. The residual radioactivity is estimated to be approximately 0.04 percent of the total inventory in the facility as of March, 1997. According to the results, the only radionuclides that would produce greater than 0.0.1-millirem per year are Am-241 (0.013 mrem/yr at 300 years), C-14 (0.022 mrem/yr at 1000 years) and U-238 (0.034 mrem/yr at 6000 years). Human exposure would occur only through the groundwater pathways, that is, from water drawn from, a well on the property. The maximum exposure would be approximately one percent of the 4 millirem per year ground water exposure limit established by the U.S. Environmental Protection Agency. 11 refs., 13 figs., 15 tabs

Manufacturing of concrete with residues from iron ore exploitation using the technology of radioactive waste cementation

Energy Technology Data Exchange (ETDEWEB)

Versieux, Juniara L.; Lameiras, Fernando S.; Tello, Cledola Cassia Oliveira de, E-mail: juniarani@gmail.com, E-mail: fsl@cdtn.br, E-mail: tellocc@cdtn.br [Centro de Desenvolvimento da Tecnologia Nucelar (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2015-07-01

Radioactive wastes from various segments of economy are immobilized by cementation, because of availability and widespread use in civil construction of cement. New cementitious materials are developed in CDTN using mining residues based on cementing techniques of radioactive wastes. Special procedures were developed to obtain concrete with the use of super plasticizers in which natural sand was totally replaced by mining residues. The motivation for this research is the exploration of banded iron formations (BIF) as iron ore in 'Quadrilatero Ferrifero' of Minas Gerais, where huge amounts of residues are generated with great concern about the environmental sustainability and safety of dams for residue storage. The exploitation of river sand causes many negative impacts, which leads to interest in its replacement by another raw material in mortar and concrete manufacturing. The use of BIF mining residues were studied for manufacturing of concrete pavers to contribute to reducing the impact caused by extraction of natural sand and use of mining residues. Previously developed procedures with total replacement of natural sand for mining residues were modified, including use of gravel to obtain pavers with improved properties. Four different mixtures were tested, in which the proportion of gravel and super plasticizer was varied. Monitored properties of pavers, among others, were compression resistance, water absorption, and void volume. With addition of gravel, the pavers had higher void index than those made only with mortar, and higher resistance to compression after 28 days of curing (an average of 18MPa of those made with mortar to 24MPa of those made with concrete). (author)

Manufacturing of concrete with residues from iron ore exploitation using the technology of radioactive waste cementation

International Nuclear Information System (INIS)

Versieux, Juniara L.; Lameiras, Fernando S.; Tello, Cledola Cassia Oliveira de

2015-01-01

Radioactive wastes from various segments of economy are immobilized by cementation, because of availability and widespread use in civil construction of cement. New cementitious materials are developed in CDTN using mining residues based on cementing techniques of radioactive wastes. Special procedures were developed to obtain concrete with the use of super plasticizers in which natural sand was totally replaced by mining residues. The motivation for this research is the exploration of banded iron formations (BIF) as iron ore in 'Quadrilatero Ferrifero' of Minas Gerais, where huge amounts of residues are generated with great concern about the environmental sustainability and safety of dams for residue storage. The exploitation of river sand causes many negative impacts, which leads to interest in its replacement by another raw material in mortar and concrete manufacturing. The use of BIF mining residues were studied for manufacturing of concrete pavers to contribute to reducing the impact caused by extraction of natural sand and use of mining residues. Previously developed procedures with total replacement of natural sand for mining residues were modified, including use of gravel to obtain pavers with improved properties. Four different mixtures were tested, in which the proportion of gravel and super plasticizer was varied. Monitored properties of pavers, among others, were compression resistance, water absorption, and void volume. With addition of gravel, the pavers had higher void index than those made only with mortar, and higher resistance to compression after 28 days of curing (an average of 18MPa of those made with mortar to 24MPa of those made with concrete). (author)

Residual radioactivity in the vicinity of formerly utilized MED/AEC sites

International Nuclear Information System (INIS)

Haywood, F.F.; Goldsmith, W.A.

1980-01-01

As demand for uranium and thorium was accelerated during the 1940's, services of chemical and metallurgical firms and major research facilities were contracted as needed by the Manhattan Engineer District (MED). A lack of documentation of the radiological status at the time contracts were terminated at these facilities led the Department of Energy (DOE), and its predecessor the Energy Research and Development Administration (ERDA), to develop a major radiological resurvey program to fill this information void. A combination of aerial and ground-level radiological monitoring teams were utilized to identify and assess off-site radioactivity. Results from comprehensive aerial surveys provide the approximate areal extent of elevated radiation levels on the ground. These aerial survey results led to two types of ground-level surveys: (1) gamma-ray scanning on foot or from a motorized vehicle (mobile lab based system) to pinpoint the location of residual radioactivity; and (2) compehensive radiological surveys to determine the amount and type of materials present on specific parcels of private and public property identified during the scanning. This type of investigation was initiated in 1978 and has been successful in identifying and assessing the potential radiation hazard from property on which materials bearing natural radioactivity have been found. This paper contains a description of the techniques used to find and evaluate radioactive material displaced outside the boundaries of a formerly utilized site

A survey of radioactive levels of agricultural products in Saitama prefecture

Energy Technology Data Exchange (ETDEWEB)

Motegi, Misako; Miyake, Sadaaki; Oosawa, Takashi; Nakazawa, Kiyoaki [Saitama Inst. of Public health, Saitama (Japan)

1997-09-01

Past atmospheric nuclear testing which have been conducted frequently, have caused environmental pollution due to the diffusion of radioactive substances into the atmosphere and from the radioactive fallout. The environmental pollution from nuclear testing into the atmosphere has resulted in the radioactive contamination in agricultural products and has continued for a long time. The radioactive contamination of agricultural products occurs through air, water and soil which were contaminated by radioactive fallout. In this paper, for the purpose of analyzing the extent of the radioactive contamination levels in the agricultural products of Saitama Prefecture, spinach, green soybeans, dried shiitake and welsh onion, were selected among products, as the amount of the harvest is abundant in all of Japan. Radioactivity concentration was investigated by gamma-ray spectrometry and radiochemical analysis. The radioactivity concentrations of artificial radioactive nuclides, cesium-137 ({sup 137}Cs) and strontium-90 ({sup 90}Sr), were detected in the range which is considered to be the result of radioactive fallout. Moreover, in order to examine the effect on radioactivity concentrations in agricultural products by culinary processing, the raw agricultural products were boiled, and their radioactivity concentrations were compared with the raw produce. The radioactivity concentrations in the boiled were lower than those in the raw produce. (author)

A survey of radioactive levels of agricultural products in Saitama prefecture

International Nuclear Information System (INIS)

Motegi, Misako; Miyake, Sadaaki; Oosawa, Takashi; Nakazawa, Kiyoaki

1997-01-01

Past atmospheric nuclear testing which have been conducted frequently, have caused environmental pollution due to the diffusion of radioactive substances into the atmosphere and from the radioactive fallout. The environmental pollution from nuclear testing into the atmosphere has resulted in the radioactive contamination in agricultural products and has continued for a long time. The radioactive contamination of agricultural products occurs through air, water and soil which were contaminated by radioactive fallout. In this paper, for the purpose of analyzing the extent of the radioactive contamination levels in the agricultural products of Saitama Prefecture, spinach, green soybeans, dried shiitake and welsh onion, were selected among products, as the amount of the harvest is abundant in all of Japan. Radioactivity concentration was investigated by gamma-ray spectrometry and radiochemical analysis. The radioactivity concentrations of artificial radioactive nuclides, cesium-137 ( 137 Cs) and strontium-90 ( 90 Sr), were detected in the range which is considered to be the result of radioactive fallout. Moreover, in order to examine the effect on radioactivity concentrations in agricultural products by culinary processing, the raw agricultural products were boiled, and their radioactivity concentrations were compared with the raw produce. The radioactivity concentrations in the boiled were lower than those in the raw produce. (author)

Western Canadian wood residue production and consumption trends

International Nuclear Information System (INIS)

McCloy, B.

2006-01-01

This presentation considered various trends in western Canadian wood residue production and consumption. Potential markets for wood residue products were also discussed. Trends were reviewed by province for the years 2000-2004. British Columbia (BC) is currently the largest producer of residue in the country, and also retains the largest surpluses of bark, sawdust and shavings. Wood residues in BC are used in pulp and plywood mill production, as well as in the creation of particleboard and MDF. Surplus mill wood residue production in the province has greatly increased due to the Mountain Pine Beetle (MPB) infestation, which has in turn spurred expansion of the BC interior sawmill industry. The infestation has also resulted in a glut of pulp chips. Current wood residue products in Alberta are mostly used in pulp mill combined heat and power (CHP) systems, as well as for wood pellet production and the creation of particleboard and MDF. It was noted that surplus residues are rapidly declining in the province. Saskatchewan's wood residue storage piles are estimated to contain 2,900,000 BDt, while Manitoba surpluses are relatively minor. It was suggested that high natural gas prices have increased the payback on wood energy systems to approximately 2 years. The value of wood residue is now greater than $100/BDt as a substitute for natural gas once the wood energy system has been fully depreciated. Sawmills may now wish to consider equipping themselves to sell wood residue products, as most sawmills only require 20 per cent of their residues for heating purposes. It was concluded that markets for hog fuel wood pellets should be developed in Canada and internationally. Future markets may also develop if natural gas currently used in pulp mill power boilers and lime kilns is replaced with wood residue energy systems. refs., tabs., figs

Review of the incineration of 500 tonnes of radio-active residues

International Nuclear Information System (INIS)

Rodier, J.; Seyfried, P.; Charbonneaux, M.

1969-01-01

During its first five years operation, the incinerator at the Marcoule Centre has burnt almost 500 tonnes of radio-active residues. Improvements in some of the details of the process have been made during this period; they concern the nature of the materials involved. The technical and radiological results for the installation are very favorable, and have made it possible to maintain a high charge factor.Although the overall economic results are not advantageous in the case of ungraded solid residues this method represents nevertheless the best available for eliminating oils, solvents, wood and dead animals. It can also be of use furthermore each time that a dilution in the atmosphere can advantageously be used as a method of disposing of certain radio elements such as tritium or carbon 14 in the form of gases or vapours. (author) [fr

The experimental study of residual radioactivity induced in electrostatic deflector

Directory of Open Access Journals (Sweden)

Xu Chong

2017-01-01

Full Text Available As one of the key components of Sector Focusing Cyclotron at the Institute of Modern Physics, Chinese Academy of Sciences, the electrostatic deflector can be activated by primary and secondary particles, because of a mismatch between the actual value and the design value of the emittance and emergence angle. In addition, it will be struck by more particles, since there is a stray magnetic field and outgas from the surface of the electrostatic deflector. The residual radioactivity in the electrostatic deflector has been studied in two aspects: specific activity and residual dose rate, based on the gamma-ray spectrometry and Fluke 451p ionization chamber, respectively. The specific activity of radionuclides in the main components and the dust on the enclosure have been investigated by using gamma-ray spectrometry. The residual dose rate around the electrostatic deflector has been obtained by Fluke 451p ionization chamber. The results of the study show that there is a non-negligible radiological risk to the staff. This result can be provided as guidance for making a maintenance schedule, so that the dose received by staff can be kept as low as reasonably achievable. Based on the results, advice for "hands-on" maintenance and decommissioning of the SFC have been provided.

Introducing radioactivity monitoring systems in the production of steel

International Nuclear Information System (INIS)

Sofilic, T.; Marjanovic, T.; Rastovcan-Mioc, A.

2005-01-01

Over the last twenty years, a significant number of cases of radioactive pollution has been recorded in metallurgical processes. However, it is not certain whether the pollution was caused by increased uncontrolled disposal of waste containing radionuclides or whether it was the result of increased radioactivity monitoring and control of metallic scrap. Many metal producers in the world have therefore implemented systematic monitoring of radioactivity in their production processes. Special attention was given to monitoring radioactivity in steel making processes, which is still the most applied construction material with an annual output of over billion tonnes all over the world. Drawing on the experience of the best known steel producers in Europe and world, Croatian steel mills find it necessary and justified to introduce radioactivity monitoring and control systems of radioactive elements in steel scrap, semi-finished and finished products. The aim of this paper is to point out the need to introduce the radioactivity monitoring and control in steel and steel-casting production, and to inform experts in Croatian steel mills and foundries about potential solutions and current systems. At the same time, we wanted to demonstrate how implementation of monitoring equipment can improve quality management and environmental management systems. This would render Croatian products competitive on the European market both in terms of physical and chemical properties and in terms of product quality certificates and radioactivity information. Since we lack our own standards and regulations to control both domestic and imported steel scrap, semi-finished products (crude steel, hot and cold rolled strip) and finished products, we need apply current international recommendations and guidelines, until we design our own monitoring system and adopt relevant legislation on the national level. This paper describes basic types of radioactivity monitoring and control systems, the most

Derivation of residual radioactive material guidelines for uranium in soil at the Former Associate Aircraft Tool and Manufacturing Company Site, Fairfield, Ohio

International Nuclear Information System (INIS)

Faillace, E.R.; Nimmagadda, M.; Yu, C.

1995-01-01

Residual radioactive material guidelines for uranium in soil were derived for the former Associate Aircraft Tool and Manufacturing Company site in Fairfield, Ohio. This site has been identified for remedial action under the U.S. Department of Energy's (DOE's) Formerly Utilized Sites Remedial Action Program (FUSRAP). Single-nuclide and total-uranium guidelines were derived on the basis of the requirement that, after remedial action, the 50-year committed effective dose equivalent to a hypothetical individual living or working in the immediate vicinity of the site should not exceed (1) 30 mrem/yr for the current-use and likely future-use scenarios or (2) 100 mrem/yr for less likely future-use scenarios. The DOE residual radioactive material (RESRAD) computer code, which implements the methodology described in the DOE manual for establishing residual radioactive material guidelines, was used in this evaluation

Immobilization of acid digestion residue

International Nuclear Information System (INIS)

Greenhalgh, W.O.; Allen, C.R.

1983-01-01

Acid digestion treatment of nuclear waste is similar to incineration processes and results in the bulk of the waste being reduced in volume and weight to some residual solids termed residue. The residue is composed of various dispersible solid materials and typically contains the resultant radioactivity from the waste. This report describes the immobilization of the residue in portland cement, borosilicate glass, and some other waste forms. Diagrams showing the cement and glass virtification parameters are included in the report as well as process steps and candidate waste product forms. Cement immobilization is simplest and probably least expensive; glass vitrification exhibits the best overall volume reduction ratio

The production of residual nuclides in Pb irradiated by 400 MeV/u carbon ions

Energy Technology Data Exchange (ETDEWEB)

Ge, H.L. [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Ma, F., E-mail: mf@impcas.ac.cn [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Zhang, X.Y.; Ju, Y.Q.; Zhang, H.B.; Chen, L.; Luo, P. [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Zhou, B. [Institute of High Energy Physics, Chinese Academy of Sciences, Beijing 100049 (China); Zhang, Y.B.; Li, J.Y.; Xu, J.K. [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China); Liang, T.J. [Institute of Physics, Chinese Academy of Sciences, Beijing 100190 (China); Wang, S.L. [Institute of High Energy Physics, Chinese Academy of Sciences, Beijing 100049 (China); Yang, Y.W.; Yang, L. [Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000 (China)

2014-10-15

The experiment was performed by irradiating a Pb foil with 400 MeV/u carbon beam at the HIRFL-CSR in Lanzhou, China. The experimental data was acquired by the off-line γ-spectroscopy method. 32 radioactive residual nuclides had been observed and their cross sections were determined. The measured results were compared with the results simulated by Monte Carlo code MCNPX2.7.0. The comparison shows that the simulated cross sections were underestimated for the fragments from A = 20 to 41 and A = 110 to 175. By fitting the measured and simulated cross sections to Rudstams semi-empirical formula, it was found that the charge distribution of products was asymmetric for the residual nuclides with a high mass number.

Carbaryl residues in maize products

International Nuclear Information System (INIS)

Zayed, S.M.A.D.; Mansour, S.A.; Mostafa, I.Y.; Hassan, A.

1976-01-01

The 14 C-labelled insecticide carbaryl was synthesized from [1- 14 C]-1-naphthol at a specific activity of 3.18mCig -1 . Maize plants were treated with the labelled insecticide under simulated conditions of agricultural practice. Mature plants were harvested and studied for distribution of total residues in untreated grains as popularly roasted and consumed, and in the corn oil and corn germ products. Total residues found under these conditions in the respective products were 0.2, 0.1, 0.45 and 0.16ppm. (author)

Radiation doses from residual radioactivity

International Nuclear Information System (INIS)

Okajima, Shunzo; Fujita, Shoichiro; Harley, John H.

1987-01-01

In this chapter available data and calculations for assessing the exposure of survivors of the Hiroshima and Nagasaki bombs and persons who entered the cities after the bombings have been presented. It appears that it is possible to produce firm estimates only for external radiation and, while the internal contribution for long-lived fission products appears small, there is no way to evaluate potential exposures to the short-lived fission products. The radiation exposure in the most highly contaminated fallout area of a few hectares at Nishiyama, Nagasaki, is estimated as 20 to 40 R when integrated from one hour to infinity using a decay exponent of -1.2. For the Hiroshima Koi-Takasu area, the corresponding exposure is estimated as 1 to 3 R. The falloff with distance for Nagasaki is not steep and an exposure of one-fifth of the maximum is spread over an area of perhaps 1000 ha. With the assumption stated above, the potential maximum exposures to external radiation from induced radioactivity at the hypocenter is estimated to be about 80 R fir Hiroshima and 30 to 40 R for Nagasaki with the assumptions stated above. These exposures fall off with both time and distance. The cumulative exposure would be about one-third as large after a day and only a few percent after a week. The falloff with distance is less striking, but can be estimated from the areas listed or from the curves shown in Gritzner and Woolson. Unlike the fallout, which exposed individuals in their living areas, exposures to induced activity came from reentry of individuals into the area around the hypocenter. As an example, an individual entering the Hiroshima hypocenter area after one day and working 10 or 20 hours a day for a week would have been exposed to about 10 R. If the person had been working at a distance of 500 m, the exposure would have been about 1 R and, at 1000 m, about 20 mR. The exposure described apply to the specified areas in the two cities. Application of these values to individuals

Development of simple and rapid radioactivity analysis for thorium series in the products containing naturally occurring radioactive materials (NORM)

Energy Technology Data Exchange (ETDEWEB)

Yoo, Jae Ryong; Park, Se Young; Yoon, Seok Won; Ha, Wi Ho [Korea Institute of Radiological and Medical Sciences, Seoul (Korea, Republic of); Lee, Jae Kook; Kim, Kwang Pyo [Kyung Hee University, Seoul (Korea, Republic of)

2016-05-15

It is necessary to analyze radioactivity of naturally occurring radioactive materials (NORM) in products to ensure radiological safety required by Natural Radiation Safety Management Act. The pretreatments for the existing analysis methods require high technology and time. Such destructive pretreatments including grinding and dissolution of samples make impossible to reuse products. We developed a rapid and simple procedure of radioactivity analysis for thorium series in the products containing NORM. The developed method requires non-destructive or minimized pretreatment. Radioactivity of the product without pretreatment is initially measured using gamma spectroscopy and then the measured radioactivity is adjusted by considering material composition, mass density, and geometrical shape of the product. The radioactivity adjustment can be made using scaling factors, which is derived by radiation transport Monte Carlo simulation. Necklace, bracelet, male health care product, and tile for health mat were selected as representative products for this study. The products are commonly used by the public and directly contacted with human body and thus resulting in high radiation exposure to the user. The scaling factors were derived using MCNPX code and the values ranged from 0.31 to 0.47. If radioactivity of the products is measured without pretreatment, the thorium series may be overestimated by up to 2.8 times. If scaling factors are applied, the difference in radioactivity estimates are reduced to 3-24%. The developed procedure in this study can be used for other products with various materials and shapes and thus ensuring radiological safety.

Process for reducing radioactive contamination in waste product gypsum

International Nuclear Information System (INIS)

Lange, P.H. Jr.

1979-01-01

A process is described for reducing the radioactive contamination in waste product gypsum in which waste product gypsum is reacted with a dilute sulfuric acid containing barium sulfate to form an acid slurry at an elevated temperature, the slurry is preferably cooled, the acid component is separated from the solid, and the resulting solid is separated into a fine fraction and a coarse fraction. The fine fraction predominates in barium sulfate and radioactive contamination. The coarse fraction predominates in a purified gypsum product of reduced radioactive contamination

Radioactive waste management in sealed sources laboratory production

International Nuclear Information System (INIS)

Carvalho, Gilberto

2001-01-01

The laboratory of sealed sources production, of Instituto de Pesquisas Energeticas e Nucleares, was created in 1983 and since then, has produced radioactive sources for industry and engineering in general, having specialization in assembly of radiation sources for non destructive testings, by gammagraphy, with Iridium-192, that represents 98% of the production of laboratory and 2% with the Cobalt-60, used in nuclear gages. The aim of this work, is to quantify and qualify the radioactive wastes generated annually, taking into account, the average of radioactive sources produced, that are approximately 220 sources per year

Radioactivity in consumer products : radiation safety and regulatory appraisal

International Nuclear Information System (INIS)

Murthy, B.K.S.; Venkataraman, G.; Subrahmanym, P.

1993-01-01

Use of radioactive materials in consumer products is in vogue almost since the discovery of radioactivity. There has been a rapid growth in the use of radioactive material in various consumer products such as Ionization Chamber Smoke Detectors (ICSD), Static eliminators, etc. In addition, there are certain manufacturing processes wherein the Naturally Occurring Radioactive Material (NORM) get incorporated in the consumer products. Certain phosphatic fertilizers, titanium dioxide pigments, phospho gypsum plaster boards are some examples in this category. The manufacture and use of these products result in radiation dose to the public apart from radiation exposure to the personnel involved in the manufacturing process. Appropriate radiation control measures have to be taken in the design, manufacture and use of consumer products to ensure that the radiation doses to the public and the population at large do not exceed the relevant limits. While appropriate regulatory controls and surveillance are established for manufacture and use of certain products, these are still to be recognised and established in respect of certain other processes and products. The current status of radiation safety and regulatory control and the lack of these in respect of some products are discussed in this paper. (author). 5 refs

Release process for non-real property containing residual radioactive material

International Nuclear Information System (INIS)

Ranek, N.L.; Chen, S.Y.; Kamboj, S.; Hensley, J.; Burns, D.; Fleming, R.; Warren, S.; Wallo, A.

1997-01-01

It is DOE's objective to operate its facilities and to conduct its activities so that radiation exposures to members of the public are maintained within acceptable limits and exposures to residual radioactive materials are controlled. To accomplish this, DOE has adopted Order DOE 5400.51 'Radiation Protection of the Public and the Environment', and will be promulgating IO CR Part 834 to codify and clarify the requirements of DOE 5400.5. Under both DOE 5400.5 and 10 CR Part 834, radioactively contaminated DOE property is prohibited from release unless specific actions have been completed prior to the release. This paper outlines a ten-step process that, if followed, will assist DOE Operations and contractor personnel in ensuring that the required actions established by Order DOE 5400.5 and 10 CR Part 834 have been appropriately completed prior to the release for reuse or recycle of non-real property (e.g., office furniture, computers, hand tools, machinery, vehicles and scrap metal). Following the process will assist in ensuring that radiological doses to the public from the released materials will meet applicable regulatory standards and be as low as reasonably achievable (ALARA)

Release procedures and disposal of radioactive residual substances at the Medical University Hanover (MHH)

International Nuclear Information System (INIS)

Scheller, F.; Behrendt, R.; Harke, H.

2005-01-01

The disposal of all radioactive residual packages of the MHH is regulated by the German radiation protection ordinance from 26 th July 2001; shown in appendix III, table 1, column 5: unrestricted release of solid materials and liquids. All radioactive waste packages are collected and handled by the central MHH department for radiation protection. They are sorted for type, nuclide and specific radioactivity. A few packages can directly be released as conventional waste after performing incoming measurements showing very low activity concentrations. Longer living radionuclides with specific activities above the release limits have to be delivered to the national waste disposal. For direct measurements of gamma-emitting radionuclides we use two in-situ-measuring units (ISOCS, Canberra) and a special release unit with 9 plastic scintillators in a fixed geometry (FR-9 PVT, MED Medizintechnik). Fluid beta-emitting radionuclides are measured by taking a fraction and using liquid scintillation counting (LSC). Solid beta-emitting radionuclides activity are calculated. (orig.)

Method of processing solidification product of radioactive waste

International Nuclear Information System (INIS)

Daime, Fumiyoshi.

1988-01-01

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

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

International Nuclear Information System (INIS)

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

1993-01-01

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

Method of treatment of radioactive silts and soils

International Nuclear Information System (INIS)

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

1997-01-01

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

Basic facts about the transport of packaged radioactive products

International Nuclear Information System (INIS)

1987-09-01

The pamphlet on the ''basic facts about the transport of packaged radioactive products'' was prepared by Amersham International for the Advisory Committee on the Safe Transport of Radioactive Material. Details of the regulations that apply to transport, the handling of radioactive materials and the precautions to be taken are all outlined, along with what should be done if a package of radioactive materials is damaged and how packages of radioactive materials can be recognised. (UK)

Radioactivity distribution in phosphate products, by-products, effluents, and wastes

International Nuclear Information System (INIS)

Guimond, R.J.; Windham, S.T.

1975-08-01

Phosphate rock throughout the world contains uranium in concentrations ranging from a few ppM to a few hundred ppM. In the United States, phosphate rock normally contains between 100 to 150 ppM uranium. Mining and processing of these ores redistributes much of the uranium daughters among the various products, by-products, and wastes. These materials are then widely dispersed throughout the environment. This redistribution may lead to increased exposure of the public to these naturally-occurring radionuclides. In determining the magnitude of the population exposure caused by this redistribution and in developing environmental standards and controls to prevent contamination of the biosphere from these naturally-occurring radionuclides it is necessary to determine the concentrations and total quantities of these radionuclides in the products, by-products, effluents and wastes of phosphate mining and manufacturing. Samples of phosphate ores, products, by-products, effluents, and wastes were obtained and analyzed for their radioactivity content. Quantities of radioactivity entering the environment through various products, by-products, effluents, and wastes were estimated

Total gamma activity measurements for determining the radioactivity of residual materials from nuclear power stations

International Nuclear Information System (INIS)

Auler, I.; Meyer, M.; Stickelmann, J.

1995-01-01

Large amounts of residual materials from retrofitting measures and from decommissioning of nuclear power stations shows such a weak level of radioactivity that they could be released after decision measurements. Expenses incurred with complex geometry cannot be taken with common methods. NIS developed a Release Measurement Facility (RMF) based on total gamma activity measurements especially for these kind of residual materials. The RMF has been applied for decision measurements in different nuclear power plants. Altogether about 2,000 Mg of various types of materials have been measured up to now. More than 90 % of these materials could be released 0 without any restriction after decision measurements

Radioactive ion beam production by the ISOL method for SPIRAL

International Nuclear Information System (INIS)

Landre-Pellemoine, Frederique

2001-01-01

This work is directly related to the SPIRAL project (Systeme de Production d'Ions Radioactifs Acceleres en Lignes) of which the start up will begin in September 2001 at GANIL (Grand Accelerateur National d'Ions Lourds) in Caen. This thesis primarily concerns the development of radioactive ion production systems (target/ion source) by the thorough study of each production stage of the ISOL (Isotopic Separation On Line) method: target and/or projectile fragmentation production, diffusion out of target material, effusion into the ion source and finally the ionization of the radioactive atoms. A bibliographical research and thermal simulations allowed us to optimize materials and the shape of the production and diffusion targets. A first target was optimized and made reliable for the radioactive noble gases production (argon, neon...). A second target dedicated to the radioactive helium production was entirely designed and realised (from the specifications to the 'off line' and 'on line' tests). Finally, a third target source system was defined for singly-charged radioactive alkaline production. The intensities of secondary beams planned for SPIRAL are presented here. A detailed study of the diffusion effusion efficiency for these various targets showed that the use of a fine microstructure carbon (grain size of 1 μm) improved the diffusion and showed the importance of thickness of the lamella for the short lived isotope effusion. (author) [fr

Residual radioactive contamination from decommissioning: Technical basis for translating contamination levels to annual dose

International Nuclear Information System (INIS)

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

1990-01-01

This document describes the generic modeling of the total effective dose equivalent (TEDE) to an individual in a population from a unit concentration of residual radioactive contamination. Radioactive contamination inside buildings and soil contamination are considered. Unit concentration TEDE factors by radionuclide, exposure pathway, and exposure scenario are calculated. Reference radiation exposure scenarios are used to derive unit concentration TEDE factors for about 200 individual radionuclides and parent-daughter mixtures. For buildings, these unit concentration factors list the annual TEDE for volume and surface contamination situations. For soil, annual TEDE factors are presented for unit concentrations of radionuclides in soil during residential use of contaminated land and the TEDE per unit total inventory for potential use of drinking water from a ground-water source. Because of the generic treatment of potentially complex ground-water systems, the annual TEDE factors for drinking water for a given inventory may only indicate when additional site data or modeling sophistication are warranted. Descriptions are provided of the models, exposure pathways, exposure scenarios, parameter values, and assumptions used. An analysis of the potential annual TEDE resulting from reference mixtures of residual radionuclides is provided to demonstrate application of the TEDE factors. 62 refs., 5 figs., 66 tabs

Thermal decomposition of woody wastes contaminated with radioactive materials using externally-heated horizontal kiln

International Nuclear Information System (INIS)

Iwasaki, Toshiyuki; Kato, Shigeru; Yamasaki, Akihiro; Ito, Takuya; Suzuki, Seiichi; Kojima, Toshinori; Kodera, Yoichi; Hatta, Akimichi; Kikuzato, Masahiro

2015-01-01

Thermal decomposition experiments of woody wastes contaminated with radioactive materials were conducted using an externally-heated horizontal kiln in the work area for segregation of disaster wastes at Hirono Town, Futaba County, Fukushima Prefecture. Radioactivity was not detected in gaseous products of thermal decomposition at 923 K and 1123 K after passage through a trap filled with activated carbon. The contents of radioactive cesium ( 134 Cs and 137 Cs) were measured in the solid and liquid products of the thermal decomposition experiments and in the residues in the kiln after all of the experiments. Although a trace amount of radioactive cesium was found in the washing trap during the start-up period of operation at 923 K, most of the cesium remained in the char, including the residues in the kiln. These results suggest that most of the radioactive cesium is trapped in char particles and is not emitted in gaseous form. (author)

Cyclotrons for the production of radioactive beams

International Nuclear Information System (INIS)

Clark, D.J.

1990-01-01

This paper describes the characteristics and design choices for modern cyclotrons. Cyclotrons can be used in 3 areas in the radioactive beam field: the production of high energy heavy ion beams for use in fragmentation, the spallation of targets with high energy protons, and the acceleration of radioactive beams from low energy to the MeV/u range. 16 refs., 6 figs

Study of extraterrestrial disposal of radioactive wastes. Part 3: Preliminary feasibility screening study of space disposal of the actinide radioactive wastes with 1 percent and 0.1 percent fission product contamination

Science.gov (United States)

Hyland, R. E.; Wohl, M. L.; Finnegan, P. M.

1973-01-01

A preliminary study was conducted of the feasibility of space disposal of the actinide class of radioactive waste material. This waste was assumed to contain 1 and 0.1 percent residual fission products, since it may not be feasible to completely separate the actinides. The actinides are a small fraction of the total waste but they remain radioactive much longer than the other wastes and must be isolated from human encounter for tens of thousands of years. Results indicate that space disposal is promising but more study is required, particularly in the area of safety. The minimum cost of space transportation would increase the consumer electric utility bill by the order of 1 percent for earth escape and 3 percent for solar escape. The waste package in this phase of the study was designed for normal operating conditions only; the design of next phase of the study will include provisions for accident safety. The number of shuttle launches per year required to dispose of all U.S. generated actinide waste with 0.1 percent residual fission products varies between 3 and 15 in 1985 and between 25 and 110 by 2000. The lower values assume earth escape (solar orbit) and the higher values are for escape from the solar system.

Evaluation of dose due to the liberation of the radioactive content present in systems of final disposal of radioactive residues

International Nuclear Information System (INIS)

Amado, V.; Lopez, F.

2006-01-01

The disposal systems of radioactive residuals well-known as repositories near to the surface, are used to dispose residuals that can contain high concentrations of radionuclides of period of short semi disintegration, which they would decay at levels radiologically insignificant in some few decades or in some centuries: and acceptably low concentrations of radionuclides of period of long semi disintegration. The dose that would receive the critic group due to these systems it could be increased by cause of discreet events that affect the foreseen retard time, or by the gradual degradation of the barriers. To this last case it contributes the presence of water, because it implies leaching and dissolution that can give place to radionuclide concentrations in the underground water greater to the prospective ones. The dosimetric evaluation is important because it offers useful objective information to decide if a given repository is adjusted to the purposes of its design and it fulfills the regulatory requirements. In this work a simplified evaluation of the dose that would receive the critic group due to the liberation of contained radionuclides in a hypothetical system of final disposition of radioactive residuals is presented. For it, they are considered representative values of the usually contained activities in this type of systems and they are carried out some approaches of the source term. The study is developed in two stages. In the first one, by means of the Radionuclide pollutant scattering pattern in phreatic aquifers (DRAF) it is considered the scattering of the pollutants in the phreatic aquifer, until the discharge point in the course of the nearest surface water. This model, developed originally in the regulatory branch of the National Commission of Argentine Atomic Energy (CNEA); it solves the transport equation of solutes in porous means in three dimensions, by the finite differences method having in account the soil retention and the radioactive

Presence of radioactivity in a sewage system: a proposal for radioactivity control

International Nuclear Information System (INIS)

Serradell, Vicente; Ballesteros, Luisa; Ortiz, Josefina

2008-01-01

Most hospitals use radioisotopes in diagnostics and to a lesser extent in therapy. The liquid residues thus generated are usually subjected to treatment before being discharged into the sewage system. Nevertheless, a certain amount of these residues escape from the treatment system and are poured directly into the sewer. In addition, other radioactive products used for research and industrial purposes may also be disposed of in the same way. The waste waters in many sewage systems can therefore be expected to be radiologically contaminated and the need for at least a basic control system in such situations seems obvious. When designing a procedure to measure radioactivity, certain conditions should be borne in mind: 1) The control program has to be simple and inexpensive; 2) Samples must be taken from the appropriate places; 3) Short life radionuclides will probably be present in significant amounts, so that specific recipes should be prepared; 4) Iodine is also frequently present. Special precautions should be taken to keep it in solution. In recent years, the Environmental Radioactivity Laboratory of the Universidad Politecnica de Valencia (Spain) has carried out a series of tests on the Valencia city sewage system and sewage treatment plant in order to design a permanent program to control radioactive contamination of the city's sewage system. This paper presents a proposal which we believe can provide the answer to this problem. (author)

Plan 2010. Costs starting in 2012 for the radioactive residual products from nuclear power. Basis for fees and guarantees during the period 2012-2014

Energy Technology Data Exchange (ETDEWEB)

2010-12-15

According to the current regulatory framework, it is the responsibility of the holder of a licence to own or operate a nuclear power reactor to prepare a calculation of the costs for all measures that are needed for the management and disposal of spent nuclear fuel that has been used in the reactors and other radioactive waste products and to decommission and dismantle the reactor plants. The regulatory framework comprises the Act (2006:647) and the Ordinance (2008:715) on Financial Measures for the Management of Residual Products from Nuclear Activities (hereinafter referred to as the Financing Act and the Financing Ordinance, respectively). This cost calculation shall be submitted periodically to the Government or the authority designated by the Government. SKB's owners have assigned SKB the task of preparing such a cost calculation jointly for the licensees of the Swedish nuclear power plants. The present report, which is the twenty-eighth annual plan report, gives an updated compilation of these costs. As in previous years' reports, the costs are shown for two cases. The first case concerns the system as a whole, including management and disposal of radioactive operational waste plus certain waste deriving from other facilities than those belonging to SKB's owners. This case has been based on a scenario concerning reactor operation that is based on the nuclear power plant owners' current planning. The second case concerns the system with the restrictions that follow from the regulatory framework, which stipulates the time for operation of the reactors that is supposed to serve as a basis for fees. The report is divided into three parts: Chapter 1 provides background information regarding the Financing Act and SKB's calculation model. Chapter 2 provides information on the underlying calculation, which is based on current plans for reactor operation and SKB's activities. Chapter 3 presents the cost estimates required by the Financing

Plan 2010. Costs starting in 2012 for the radioactive residual products from nuclear power. Basis for fees and guarantees during the period 2012-2014

International Nuclear Information System (INIS)

2010-12-01

According to the current regulatory framework, it is the responsibility of the holder of a licence to own or operate a nuclear power reactor to prepare a calculation of the costs for all measures that are needed for the management and disposal of spent nuclear fuel that has been used in the reactors and other radioactive waste products and to decommission and dismantle the reactor plants. The regulatory framework comprises the Act (2006:647) and the Ordinance (2008:715) on Financial Measures for the Management of Residual Products from Nuclear Activities (hereinafter referred to as the Financing Act and the Financing Ordinance, respectively). This cost calculation shall be submitted periodically to the Government or the authority designated by the Government. SKB's owners have assigned SKB the task of preparing such a cost calculation jointly for the licensees of the Swedish nuclear power plants. The present report, which is the twenty-eighth annual plan report, gives an updated compilation of these costs. As in previous years' reports, the costs are shown for two cases. The first case concerns the system as a whole, including management and disposal of radioactive operational waste plus certain waste deriving from other facilities than those belonging to SKB's owners. This case has been based on a scenario concerning reactor operation that is based on the nuclear power plant owners' current planning. The second case concerns the system with the restrictions that follow from the regulatory framework, which stipulates the time for operation of the reactors that is supposed to serve as a basis for fees. The report is divided into three parts: Chapter 1 provides background information regarding the Financing Act and SKB's calculation model. Chapter 2 provides information on the underlying calculation, which is based on current plans for reactor operation and SKB's activities. Chapter 3 presents the cost estimates required by the Financing Act that are the primary

Map of calculated radioactivity of fission product, (4)

International Nuclear Information System (INIS)

Takeda, Tsuneo

1978-07-01

The overall radioactivities of fission products depending on irradiation time and cooling time were calculated for 18 different neutron fluxes, which are presented in contour maps and tables. Irradiation condition etc. are the followings: neutron flux (n sub(th)) 1 x 10 12 - 6.8 x 10 14 n/cm 2 /sec, uranium quantity 1 mole (6 x 10 23 atoms, ca. 271 g UO 2 ), U-235 enrichment 2.7%, irradiation time 60. - 6 x 10 7 sec (1 min - 1.9 y), cooling time 0. and 60. - 6 x 10 7 sec (1 min - 1.9 y). The enrichment value represents those for LWRs. To calculate the overall radioactivities, 595 fission product nuclides were introduced. Overall radioactivities calculations were made for 68,000 combinations of irradiation time, cooling time and neutron flux. The many complex decay chains of fission products were treated with CODAC-No.6 computer code. (author)

Residual radioactivity in the soil of the Semipalatinsk Nuclear Test Site in the former USSR

International Nuclear Information System (INIS)

Yamamoto, Masayoshi; Tsukatani, Tsuneo; Katayama, Yukio

1996-01-01

This paper deals with our efforts to survey residual readioactivity in the soil sampled at teh Semipalatinsk Nuclear Test Site and at off-site areas in Kazakhstan. The soil sampled at the hypocenter where the first Soviet nuclear explosion was carried out on 29 August 1949, and at the bank of the crater called open-quotes Bolapan,close quotes which was formed by an underground nuclear detonation on 15 January 1965 along the Shagan River. As a comparison, other soil was also sampled in the cities of Kurchatov and Almaty. These data have allowed a preliminary evaluation of the contemporary radioactive contamination of the land in and around the test site. At the first nuclear explosion site and at Bolapan, higher than background levels of 239,240 Pu with weapons-grade plutonium were detected together with fission and activation products such as 137 Cs, 60 Co, 152 Eu, and 154 Eu. 20 refs., 3 figs., 5 tabs

Demonstration of a computer model for residual radioactive material guidelines, RESRAD

International Nuclear Information System (INIS)

Yu, C.; Yuan, Y.C.; Zielen, A.J.; Wallo, A. III

1989-01-01

A computer model was developed to calculate residual radioactive material guidelines for the US Department of Energy (DOE). This model, called RESRAD, can be run on IBM or IBM-compatible microcomputer. Seven potential exposure pathways from contaminated soil are analyzed, including external radiation exposure and internal radiation exposure from inhalation and food digestion. The RESRAD code has been applied to several DOE sites to derive soil cleanup guidelines. The experience gained indicates that a comprehensive set of site-specific hydrogeologic and geochemical input parameters must be used for a realistic pathway analysis. The RESRAD code is a useful tool; it is easy to run and very user-friendly. 6 refs., 12 figs

Radioactive sealed sources production process for industrial radiography

International Nuclear Information System (INIS)

Santos, Paulo de S.; Ngunga, Daniel M.G.; Camara, Julio R.; Vasquez, Pablo A.S.

2017-01-01

providing products and services to the private and governmental Brazilian users of industrial radiography and nucleonic control systems. Radioactive sealed sources are commonly used in nondestructive tests as radiography to make inspections and verify the internal structure and integrity of materials and in nucleonic gauges to control level, density, viscosity, etc. in on-line industrial processes. One of the most important activities carried out by this laboratory is related to the inspection of source projectors devices used in industrial radiography and its constituent parts as well as remote handle control assembly drive cable and guide tube systems. The laboratory also provide for the users iridium-192, cobalt-60 and selenium-75 sealed sources and performs quality control tests replacing spent or contaminated radiative sources. All discard of radioactive source is treated as radioactive waste. Additionally, administrative and commercial processes and protocols for exportation and transport of radioactive material are developed by specialized departments. In this work are presented the mean processes and procedures used by the Sealed Source Production Laboratory such as the arrival of the radioactive material to the laboratory and the source projectors, mechanical inspections, source loading, source leaking tests, etc. (author)

Radioactive sealed sources production process for industrial radiography

Energy Technology Data Exchange (ETDEWEB)

Santos, Paulo de S.; Ngunga, Daniel M.G.; Camara, Julio R.; Vasquez, Pablo A.S., E-mail: psantos@ipen.br, E-mail: hobeddaniel@gmail.com, E-mail: jrcamara@ipen.br, E-mail: pavsalva@ipen.br [Instituto de Pesquisas Energética s e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

2017-07-01

providing products and services to the private and governmental Brazilian users of industrial radiography and nucleonic control systems. Radioactive sealed sources are commonly used in nondestructive tests as radiography to make inspections and verify the internal structure and integrity of materials and in nucleonic gauges to control level, density, viscosity, etc. in on-line industrial processes. One of the most important activities carried out by this laboratory is related to the inspection of source projectors devices used in industrial radiography and its constituent parts as well as remote handle control assembly drive cable and guide tube systems. The laboratory also provide for the users iridium-192, cobalt-60 and selenium-75 sealed sources and performs quality control tests replacing spent or contaminated radiative sources. All discard of radioactive source is treated as radioactive waste. Additionally, administrative and commercial processes and protocols for exportation and transport of radioactive material are developed by specialized departments. In this work are presented the mean processes and procedures used by the Sealed Source Production Laboratory such as the arrival of the radioactive material to the laboratory and the source projectors, mechanical inspections, source loading, source leaking tests, etc. (author)

A mechanism for corrosion product deposition on the carbon steel piping in the residual heat removal system of BWRs

International Nuclear Information System (INIS)

Aizawa, Motohiro; Chiba, Yoshinori; Hosokawa, Hideyuki; Ohsumi, Katsumi; Uchida, Shunsuke; Ishizawa, Noboru

2002-01-01

The dose rate of the residual heat removal (RHR) piping has been considered to be caused by accumulation of insoluble (crud) radioactive corrosion products on carbon steel surfaces. Soft shutdown procedures (i.e., plant shutdown with moderate coolant temperature reduction rate) used to be applied to reduce crud radioactivity release from the fuel surface, but these are no longer used because of the need for shorter plant shutdown times. In order to apply other suitable countermeasures to reduce RHR dose rate, assessment of plant data, experiments on deposition of crud and ion species on carbon steel, and mass balance evaluation of radioactive corrosion products based on plant and laboratory data were carried out and the following findings were made. (1) Deposits of ion species on carbon steel surfaces of the RHR piping was much more numerous than for crud. (2) Ion species accumulation behavior on RHR piping, which is temperature dependent, can be evaluated with the calculation model used for the dehydration reaction of corrosion products generated during the wet lay-up period. (3) Deposition amounts could be reduced to 1/2.5 when the starting RHR system operation temperature was lowered from 155degC to 120degC. (author)

Volume of baseline data on radioactivity in drinking water, ground water, waste water, sewage sludge, residues and wastes of the annual report 1988 'Environmental radioactivity and radiation exposure'

International Nuclear Information System (INIS)

Abelmann, S.; Buenger, T.; Fusban, H.U.; Ruehle, H.; Viertel, H.; Gans, I.

1991-01-01

This WaBoLu volume is a shortened version of the annual report by the Federal Ministry of the Environment, Nature Protection and Reactor Safety 'Environmental radioactivity and radiation exposure' and gives an overview of the data on radioactivity in drinking water, ground water, waste water, sewage sludge, residues and wastes, compiled for the area of the Federal Republic of Germany in 1988 by the Institute of Water, Soil and Air Hygiene (WaBoLu) of the Federal Health Office. (BBR) With 22 figs., 15 tabs [de

Radioactivity in New Zealand meat products

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-07-01

Full text: New Zealand has no nuclear power programme of radioactive waste disposal programme. The only artificial radioactivity detectable in the New Zealand environment is global fallout from nuclear weapons tests conducted mainly in the northern hemisphere before 1964. This fallout in New Zealand is currently at its lowest level since environmental monitoring began in 1960. The total beta activity deposited in rain during 1985, for example, averaged 76 MBQ/km{sup 2}, with most of that being due to naturally occurring radionuclides, principally lead-210/Bismuth-210. Levels of artificial radioactivity in New Zealand dairy products reflect this very low deposition rate. During 1985, for example, Strontium-90 and Caesium-137 levels in cow's milk averaged 0.035 BG/GCA and 0.27BQ/QK respectively. Those levels were similar to, or less than, levels reported in northern hemisphere countries during 1985. No change in environmental contamination levels has been recorded in New Zealand during 1985. The very low deposition rate and milk contamination levels indicate that fallout contamination levels generally are insignificant in New Zealand and monitoring of other foodstuffs such as meat products is not warranted. (author)

Radioactivity in New Zealand meat products

International Nuclear Information System (INIS)

1986-01-01

Full text: New Zealand has no nuclear power programme of radioactive waste disposal programme. The only artificial radioactivity detectable in the New Zealand environment is global fallout from nuclear weapons tests conducted mainly in the northern hemisphere before 1964. This fallout in New Zealand is currently at its lowest level since environmental monitoring began in 1960. The total beta activity deposited in rain during 1985, for example, averaged 76 MBQ/km 2 , with most of that being due to naturally occurring radionuclides, principally lead-210/Bismuth-210. Levels of artificial radioactivity in New Zealand dairy products reflect this very low deposition rate. During 1985, for example, Strontium-90 and Caesium-137 levels in cow's milk averaged 0.035 BG/GCA and 0.27BQ/QK respectively. Those levels were similar to, or less than, levels reported in northern hemisphere countries during 1985. No change in environmental contamination levels has been recorded in New Zealand during 1985. The very low deposition rate and milk contamination levels indicate that fallout contamination levels generally are insignificant in New Zealand and monitoring of other foodstuffs such as meat products is not warranted. (author)

SU-E-T-534: Level of Residual Radioactivity of Activated Parts of a Decommissioned Cyclotron

International Nuclear Information System (INIS)

Choi, HHF; Leung, TM; Chiu, TL; Yang, B; Wu, PM; Cheung, KY; Yu, SK

2015-01-01

Purpose: CTI cyclotron RDS-111 was used at the Hong Kong Sanatorium and Hospital (HKSH) to produce radiopharmaceuticals and radioactive tracers for diagnostic scans between 1999 and 2007. During the operation, some machine components became radioactive by activation. For the safety of staff, decommissioning took place in 2009, two years after the cyclotron had stopped operation. This study investigates the residual radioactivity and radionuclides found in different cyclotron components in 2014 in compliance with the local regulations in Hong Kong for transfer of radioactive waste. Methods: A representative sample of each part was counted using a high-purity germanium detector (manufacturer: ORTECT) for at least four hours. GammaVision, a multichannel analyzer software, was used to identify the radionuclides found in the cyclotron components, as well as the associated activities. A standard library and a Mariscotti peak search algorithm were used to identify the present radionuclides. Only radionuclides with half-life greater than 180 days were considered. Results: Among the components, the Havar target foil has the highest specific activity ((4.6±0.6)×10 2 Bq/g), with Co-60 being the most prominent ((3.8±0.5)×10 2 Bq/g). The total activity of the target foil, however, is still low due to its small mass of 0.04 g. Radioisotopes Mn-54 (46±6 Bq/g), Na-22 (6.8±0.8 Bq/g), Co-57 (7.3±0.9 Bq/g), and Fe-59 (6.0±0.9 Bq/g) have also been detected in the target foil. The target window holder and the vacuum window register a specific activity of 88.3±0.6 Bq/g and 48.6±0.1 Bq/g, respectively. Other components, such as the collimator, the target tube, the valve body and the beamline, are also found with trace amounts of radionuclides. Conclusion: Even seven years after the cyclotron had stopped operation, some components still exhibited residual radioactivity from activation exceeding the IAEA clearance levels. Special consideration for radiological protection may need

Standard Guide for Unrestricted Disposition of Bulk Materials Containing Residual Amounts of Radioactivity

CERN Document Server

American Society for Testing and Materials. Philadelphia

2009-01-01

1.1 This guide covers the techniques for obtaining approval for release of materials encountered in decontamination and decommissioning (D&D) from restricted use. This would be addressed in the decommissioning plan (E 1281). It applies to materials that do not meet any of the requirements for regulatory control because of radioactivity content. Fig. 1 shows the logic diagram for determining the materials that could be considered for release. Materials that negotiate this logic tree are referred to as “candidate for release based on dose.” 1.2 The objective of this guide is to provide a methodology for distinguishing between material that must be carefully isolated to prevent human contact from that that can be recycled or otherwise disposed of. It applies to material in which the radioactivity is dispersed more or less uniformly throughout the volume of the material (termed residual in bulk form) as opposed to surface contaminated objects. 1.3 Surface contaminated objects are materials externally co...

Recovery of Residual LiCl-KCl Eutectic Salts in Radioactive Rare Earth Precipitates

International Nuclear Information System (INIS)

Eun, Hee Chul; Yang, Hee Chul; Kim, In Tae; Lee, Han Soo; Cho, Yung Zun

2010-01-01

For the pyrochemical process of spent nuclear fuels, recovery of LiCl-KCl eutectic salts is needed to reduce radioactive waste volume and to recycle resource materials. This paper is about recovery of residual LiCl-KCl eutectic salts in radioactive rare earth precipitates (rare earth oxychlorides or oxides) by using a vacuum distillation process. In the vacuum distillation test apparatus, the salts in the rare earth precipitates were vaporized and were separated effectively. The separated salts were deposited in three positions of the vacuum distillation test apparatus or were collected in the filter and it is difficult to recover them. To resolve the problem, a vacuum distillation and condensation system, which is subjected to the force of a temperature gradient at a reduced pressure, was developed. In a preliminary test of the vacuum distillation/condensation recovery system, it was confirmed that it was possible to condense the vaporized salts only in the salt collector and to recover the condensed salts from the salt collector easily

Formulation of morning product using food residues

Directory of Open Access Journals (Sweden)

Maria do Rosário de Fátima Padilha

2017-09-01

Full Text Available In Brazil, there is resistance of the population to the use of stalks, leaves, peels and seeds of vegetables and fruits, leading to trash important parts of the food in good physiological conditions and with the presence of potential nutrients. In this research, a morning product was elaborated using green and dry coconut residue, jerimum and melon seed, crystallized sicilian lemon peel, cashew nut, common rapadura sweet and ginger. The bacteriological tests proved the hygienic-sanitary quality of the product, therefore suitable for consumption, that is, according to RDC 12/2001. It was also observed that the dehydration of all the residues reached the legal levels and accepted by ANVISA that limits in 25% the water content in the dehydrated foods. As for the centesimal composition, it was observed that the elaborated product with residues and other ingredients had a good content of macro nutrients. A use of the type of waste as a new food proposal constitutes an alternative to avoid and reduce: the serious environmental problem caused by the large residual volume generated, and the inadequate places in which they are stored or deposited, aggravating the scenario of food-borne pollutants.

Fate of 14C-allylalcohol herbicide in soils and crop residues

International Nuclear Information System (INIS)

Scheunert, I.; Vockel, D.; Klein, W.; Korte, F.

1981-01-01

Residue disappearance and leaching of 14 C-allylalcohol from different soils were studied in laboratory experiments. Additionally, the uptake of residues by lettuce and carrots was investigated in the greenhouse. In laboratory experiments, residue disappearance and leaching from soils was correlated negatively to the organic matter content. In greenhouse experiments with a sandy loam soil at an application rate normally used in practice, an average of 12.5% of the applied radioactivity was recovered after an eight day interval between application and sowing. Furthermore, an average of 8% (sum in soil and plants) of the applied radioactivity was recovered after lettuce or carrot growing. Uptake of residues was higher by carrots than by lettuce, and higher by lettuce roots than by lettuce tops. No bioaccumulation was observed. The residues in soils and plants were, to a high percent-age, unextractable and, to a smaller extent, fully water-soluble products. Unchanged allylalcohol could not be detected by the analytical methods used

Impact of Corn Residue Removal on Crop and Soil Productivity

Science.gov (United States)

Johnson, J. M.; Wilhelm, W. W.; Hatfield, J. L.; Voorhees, W. B.; Linden, D.

2003-12-01

Over-reliance on imported fuels, increasing atmospheric levels of greenhouses and sustaining food production for a growing population are three of the most important problems facing society in the mid-term. The US Department of Energy and private enterprise are developing technology necessary to use high cellulose feedstock, such as crop residues, for ethanol production. Based on production levels, corn (Zea mays L.) residue has potential as a biofuel feedstock. Crop residues are a renewable and domestic fuel source, which can reduce the rate of fossil fuel use (both imported and domestic) and provide an additional farm commodity. Crop residues protect the soil from wind and water erosion, provide inputs to form soil organic matter (a critical component determining soil quality) and play a role in nutrient cycling. Crop residues impact radiation balance and energy fluxes and reduce evaporation. Therefore, the benefits of using crop residues as fuel, which removes crop residues from the field, must be balanced against negative environmental impacts (e.g. soil erosion), maintaining soil organic matter levels, and preserving or enhancing productivity. All ramifications of new management practices and crop uses must be explored and evaluated fully before an industry is established. There are limited numbers of long-term studies with soil and crop responses to residue removal that range from negative to negligible. The range of crop and soil responses to crop residue removal was attributed to interactions with climate, management and soil type. Within limits, corn residue can be harvested for ethanol production to provide a renewable, domestic source of energy feedstock that reduces greenhouse gases. Removal rates must vary based on regional yield, climatic conditions and cultural practices. Agronomists are challenged to develop a protocol (tool) for recommending maximum permissible removal rates that ensure sustained soil productivity.

Decree of the 23-rd of June 2015 related to installations implementing radioactive materials, radioactive wastes or solid residues of uranium, thorium or radium ore submitted to authorization according to entry 1716, to entry 1735 and to entry 2797 of the nomenclature of classified installations

International Nuclear Information System (INIS)

Blanc, P.

2015-01-01

This decree defines general prescriptions applicable to installations implementing radioactive materials, to installations used as depository, warehousing or storage of radioactive materials under the form of solid residues of radium, thorium or uranium ore, as well as some processing products, and to installations used for the management of radioactive wastes in an industrial or commercial facility. The decree contains general arrangements about authorisation request, financial guarantees and conditions of exploitation. It addresses measures and arrangements for the management of installations, for the management of radioactive materials and wastes, for the prevention of atmospheric pollution, for the protection of water resources and aquatic media. It also contains general rules for waste management, specific rules for radioactive waste management. It addresses measures and arrangements regarding the prevention of technological risks, the monitoring of installations and of their impact. An appendix addresses the various aspects of the quality management system: organisation and personnel, risk identification and assessment, process management and exploitation monitoring, management of modifications, planning of emergency situation, return on experience, performance monitoring. A last appendix addresses the monitoring of underground waters

Device of capturing for radioactive corrosion products

International Nuclear Information System (INIS)

Ohara, Atsushi; Fukushima, Kimichika.

1984-01-01

Purpose: To increase the area of contact between the capturing materials for the radioactive corrosion products contained in the coolants and the coolants by producing stirred turbulent flows in the coolant flow channel of LMFBR type reactors. Constitution: Constituent materials for the nuclear fuel elements or the reactor core structures are activated under the neutron irradiation, corroded and transferred into the coolants. While capturing devices made of pure metal nickel are used for the elimination of the corrosion products, since the coolants form laminar flows due to the viscosity thereof near the surface of the capturing materials, the probability that the corrosion products in the coolants flowing through the middle portion of the channel contact the capturing materials is reduced. In this invention, rotating rolls and flow channels in which the balls are rotated are disposed at the upstream of the capturing device to forcively disturb the flow of the liquid sodium, whereby the radioactive corrosion products can effectively be captured. (Kamimura, M.)

Carbaryl residues in cottonseed products in the Philippines

International Nuclear Information System (INIS)

Pablo, F.E.

1981-01-01

Residues of carbaryl in cottonseed products were determined by spectrophotometry. Carbaryl residues in oil and cake were 0.83 and 0.04 mg/kg respectively. Parallel experiments with 14 C-carbaryl gave comparable results. 14 C-carbaryl residues in oil and cake were 0.42 and 0.15 mg/kg respectively. (author)

Precaution against radioactive contamination of steel products in Germany

International Nuclear Information System (INIS)

Ewers, E.; Schulz-Klemp, V.; Steffen, R.

1999-01-01

Regulations for handling of radioactive materials in Germany. Engagement of the Germany Iron and Steel Institute (VDEh) since the end of the eighties and measures taken. Level of radioactivity in uncontaminated steel products. Agreements between steel industry and scrap supplying industry as well as terms of delivery. Actual status of equipment for detection of radioactivity in the German steel plants. Demands of steel users for clean steel. (author)

PLANT PROTECTION PRODUCT RESIDUES IN AGRICULTURAL PRODUCTS OF SLOVENE ORIGIN FOUND IN 2008

Directory of Open Access Journals (Sweden)

Helena BAŠA ČESNIK

2012-01-01

Full Text Available In the year 2008, 166 apple, bean, carrot, cucumber, lettuce, pear, potato and spinach samples from Slovene producers were analysed for plant protection product residues. The samples were analysed for the presence of 158 different active compounds using three analytical methods. In two samples (1.2% exceeded maximum residue levels (MRLs were determined which is better than the results of the monitoring of pesticide residues in the products of plant origin in the 27 European Union, Member States (EU MS and 2 European Free Trade Association (EFTA States: Norway and Iceland in 2008 (2.2%. The most frequently found active substance in agricultural products was dithiocarbamates. Products which contained 4 or more active substances per sample were apples and pears.

Experimental and theoretical study of the yields of residual product nuclei produced in thin targets irradiated by 100-2600 MeV protons

CERN Document Server

Titarenko, Y E; Karpikhin, E I

2003-01-01

The objective of the project is measurements and computer simulations of independent and cumulative yields of residual product nuclei in thin targets relevant as target materials and structure materials for hybrid accelerator-driven systems coupled to high-energy proton accelerators. The yields of residual product nuclei are of great importance when estimating such basic radiation-technology characteristics of hybrid facility targets as the total target activity, target 'poisoning', buildup of long-lived nuclides that, in turn, are to be transmuted, product nuclide (Po) alpha-activity, content of low-pressure evaporated nuclides (Hg), content of chemically-active nuclides that spoil drastically the corrosion resistance of the facility structure materials, etc. In view of the above, radioactive product nuclide yields from targets and structure materials were determined by an experiment using the ITEP U-10 proton accelerator in 51 irradiation runs for different thin targets: sup 1 sup 8 sup 2 sup , sup 1 sup 8 ...

Derivation of residual radioactive material guidelines for 13 radionuclides present in Operable Unit IV at Brookhaven National Laboratory, Upton, New York

International Nuclear Information System (INIS)

Faillace, E.; Nimmagadda, M.; Yu, C.

1994-12-01

Residual radioactive material guidelines for 13 radionuclides (americium-241; cobalt-60; cesium-137; europium-152, -154, and -155; plutonium-238, -239, and -240; strontium-90; and uranium-234, -235, and -238) were derived for Operable Unit (OU) IV at Brookhaven National Laboratory. This site has been identified for remedial action under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980, as amended by the Superfund Amendments and Reauthorization Act of 1986. Single-nuclide guidelines were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of OU IV should not exceed a dose constraint of 30 mrem/yr following remedial action for the current use and plausible future use scenarios or a dose limit of 100 mrem/yr for plausible but less likely future use scenarios. The US Department of Energy (DOE) residual radioactive material guideline computer code, RESRAD, was used in this evaluation; RESRAD implements the methodology described in the DOE manual for determining residual radioactive material guidelines. Four potential scenarios were considered; each assumed that, for a period of 1,000 years following remedial action, the site would be used without radiological restrictions. The four scenarios varied with regard to the type of site use, time spent at the site, and sources of food consumed

Radiological impact on the workers, members of the public, and environment from the partial decommissioning of Pakistan Research Reactor-I and its associated radioactive residues.

Science.gov (United States)

Ali, A; Orfi, S D; Manzur, H; Aslam, M

2001-05-01

The Pakistan Research Reactor-I (PARR-I) is a swimming pool type research reactor originally designed and built for a thermal power of 5 MW using High Enriched Uranium (HEU) fuel. In 1990-1991 the reactor was redesigned, partially decommissioned and recommissioned to operate with Low Enriched Uranium (LEU) fuel at a thermal power of 10 MW. An essential requirement, construction and commissioning of a wet spent fuel storage bay and fabrication of an irradiated fuel transfer cask were completed before actual dismantling of the reactor core. During the partial decommissioning operations, radioactive waste generated included 600 m3 low-level liquid radioactive waste and 14 m3 of solid radioactive waste with an average specific activity of 4.52 Bq ml(-1) and 2.22 kBq g(-1), respectively. External radiation doses of the workers were determined using TLD (NG 6,7) and direct reading dosimeters. The maximum individual external radiation dose received by any worker during this practice was 5 mSv, which was 25% of the annual dose limit of 20 mSv. Detection and measurement of internal contamination was carried out using bioassay techniques. During the whole operation, not a single case of internal contamination was detected. The ambient radiation levels around waste seepage pits are periodically monitored using TLD (G-2 cards) and G. M. radiation survey meters. Underground migration of radioactivity is checked by analyzing seepage water samples taken from boreholes that have been dug at different locations in the vicinity of the radioactive residues. The monitoring around disposal sites containing radioactive residues has been continued during the last 9 y and will be continued in the future. So far, no rise in the environmental gamma radiation dose level and migration of underground radionuclides has been found in the vicinity of these disposal sites. Working personal during the decommissioning of PARR-I have been found to be radiologically safe. Adherence to the ALARA

Derivation of uranium residual radioactive material guidelines for the Elza Gate Site

International Nuclear Information System (INIS)

Cheng, J.J.; Yu, C.; Devgun, J.S.

1991-02-01

Residual radioactive material guidelines for uranium were derived for a large, homogeneously contaminated area at the Elza Gate Site in Oak Ridge, Tennessee. The derivation of the single-nuclide and total uranium guidelines was based on the requirement that the 50-year committed effective dose equivalent to hypothetical individual who lives or works in the immediate vicinity of the Elza Gate Site should not exceed a dose of 100 mrem/yr following decontamination. The DOE residual radioactive guideline computer code RESRAD was used in this evaluation. Four potential scenarios were considered for the site; the scenarios vary with regard to time spent at the site, sources of water used, and sources of food consumed. The results of the evaluation indicate that the basic dose limit of 100 mrem/yr will not be exceeded for uranium within 1000 years, provided that the soil concentration of uranium at the Elza Gate Site does not exceed the following levels: 1800 pCi/g for Scenario A (industrial worker: the expected scenario); 4000 pCi/g for Scenario B (recreationist: a plausible scenario); 470 pCi/g for Scenario C (resident farmer using pond water as the only water source: a possible but unlikely scenario); and 120 pCi/g for Scenario D (resident farmer using well water as the only water source: a possible but unlikely scenario). The uranium guideline applies to the total activity concentration of uranium isotopes in their natural activity concentration ratio of 1:1: 0.046. These guidelines are calculated on the basis of a dose of 100 mrem/yr. In setting the actual uranium guideline for the Elza Gate Site, the DOE will apply the as low as reasonably achievable (ALARA) policy to the decision-making process, along with other factors, such as determining whether a particular scenario is reasonable and appropriate. 10 refs., 3 figs., 7 tabs

Cellulosic ethanol production from agricultural residues in Nigeria

International Nuclear Information System (INIS)

Iye, Edward; Bilsborrow, Paul

2013-01-01

Nigeria′s Biofuels Policy introduced in 2007 mandates a 10% blend (E10) of bioethanol with gasoline. This study investigates the potential for the development of a cellulosic ethanol industry based on the availability of agricultural residues and models the number of commercial processing facilities that could be sited in the six Geo-political zones. The potential for cellulosic ethanol production from agricultural residues in Nigeria is 7556 km 3 per annum exceeding the mandate of 10% renewable fuel required and providing the potential for 12 large- and 11 medium-scale processing facilities based on the use of a single feedstock. Cassava and yam peelings provided in excess of 80% of the process residues available with enough feedstock to supply 10 large-scale facilities with a fairly even distribution across the zones. Sorghum straw, millet straw and maize stalks represented 75% of the potential resource available from field residues with the potential to supply 2 large- and 7 medium-scale processing facilities, all of which would be located in the north of the country. When a multi-feedstock approach is used, this provides the potential for either 29 large- or 58 medium-scale facilities based on outputs of 250 and 125 km 3 per annum respectively. - Highlights: • Nigeria′s Biofuels Policy mandates a 10% blend of bioethanol with gasoline. • Total bioethanol production from agricultural residues was 7556 km 3 per annum. • Process residues offer the greatest potential accounting for 62% of production. • Nigeria has the potential for 12 large- and 11 medium scale commercial. • The use of mixed feedstocks significantly increases the potential for production

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

International Nuclear Information System (INIS)

Koyama, Masashi; Yoshida, Takumasa.

1995-01-01

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

Radionuclides in Bayer process residues: previous analysis for radiological protection

International Nuclear Information System (INIS)

Cuccia, Valeria; Rocha, Zildete; Oliveira, Arno H. de

2011-01-01

Natural occurring radionuclides are present in many natural resources. Human activities may enhance concentrations of radionuclides and/or enhance potential of exposure to naturally occurring radioactive material (NORM). The industrial residues containing radionuclides have been receiving a considerable global attention, because of the large amounts of NORM containing wastes and the potential long term risks of long-lived radionuclides. Included in this global concern, this work focuses on the characterization of radioactivity in the main residues of Bayer process for alumina production: red mud and sand samples. Usually, the residues of Bayer process are named red mud, in their totality. However, in the industry where the samples were collected, there is an additional residues separation: sand and red mud. The analytical techniques used were gamma spectrometry (HPGe detector) and neutron activation analysis. The concentrations of radionuclides are higher in the red mud than in the sand. These solid residues present activities concentrations enhanced, when compared to bauxite. Further uses for the residues as building material must be more evaluated from the radiological point of view, due to its potential of radiological exposure enhancement, specially caused by radon emission. (author)

Use of radioactive glucosamine in the perfused rat liver to prepare α1-acid glycoprotein (orosomucoid) with 3H- or 14C-labelled sialic acid and N-acetylglucosamine residues

International Nuclear Information System (INIS)

Aronson, N.N. Jr.

1982-01-01

A method was developed whereby [1- 14 C]glucosamine was used in a perfused rat liver system to prepare over 2 mg of α 1 -acid glycoprotein with highly radioactive sialic acid and glucosamine residues. The liver secreted radioactive α 1 -acid glycoprotein over a 4-6 h period, and this glycoprotein was purified from the perfusate by chromatography on DEAE-cellulose at pH3.6. The sialic acid on the isolated glycoprotein had a specific radioactivity of 3.1 Ci/mol, whereas the glucosamine-specific radioactivity was 4.3 Ci/mole. The latter amino-sugar residues on the isolated protein were only 13-fold less radioactive than the initially added [1- 14 C]glucosamine. Orosomucoid with a specific radioactivity of 31.3 μCi/mg of protein was obtainable by using [6- 3 H]glucosamine. Many other radioactive glycoproteins were found to be secreted into the perfusate by the liver. Thus this experimental system should prove useful for obtaining other serum glycoproteins with highly radioactive sugar moieties. (author)

A guide for controlling consumer products containing radioactive substances

International Nuclear Information System (INIS)

1985-01-01

Consumer products are considered regardless of the purpose for which the radionuclide is added. For example, the purpose may be to make use of the ionising radiation emitted by the substance in the product itself (e.g. radioluminescent devices antistatic devices and ionisation chamber smoke detectors), or to make use of some other property of the material where the presence of radiation in the final product is merely adventitious (e.g. thorium gas mantles, ceramics with uranium glazes, and products containing radioactive tracers added to facilitate manufacturing and inspection processes). The Guide does not cover some products containing natural radioactive substances which have not been intentionally added, such as building materials. The Guide does not cover medicinal products and pharmaceuticals, nuclear powered cardiac pacemakers, or electronic equipment, such as television receivers, that emit X-rays. Unlike the 1970 Guide, this Guide does not consider those products, such as EXIT signs, containing gaseous tritium light sources, that would not be supplied directly to members of the public. The Guide is concerned mainly with the exposure arising from consumer products of those persons who are not subject to any regulatory controls for purposes of radiation protection in normal circumstances. Members of the public come under this heading, but not workers involved in the manufacture of consumer products. These workers will normally be subject to separate control. Radiological protection concepts and policy for the control of radioactive consumer products and licensing and post-licensing surveillance are developed

Capturing device for radioactive corrosion products

International Nuclear Information System (INIS)

Ono, Kiyoshi.

1987-01-01

Purpose: To render the flow channel area uniform for each of coolants over the entire capturing device and reduce the corrosion of capturing materials due to coolants. Constitution: Most of radioactivity caused by radioactive corrosion products are due to Mn-54 radioactive nuclides and it has been known that the nuclides are readily deposited to the surface of nickel material in sodium at high temperature. It is difficult in a conventional capturing device constituted by winding a nickel plate fabricated with protrusions in a multiple-coaxial configuration, that the flow channel area is reduced in a portion of the flow channel and it is difficult to make the flow of the coolants uniform. In view of the above, by winding a nickel plate having a plurality of protrusions at the surface formed integrally by way of an electrolytic process into a multiple-coaxial or spiral shape, those having high resistance to the coolant corrosion can be obtained. (Takahashi, M.)

Radioactivity Measurement in the Detergent Products by Gamma Spectrometry

International Nuclear Information System (INIS)

Ksouri, Abir

2009-01-01

Our study focuses on the evaluation of the level of radioactivity in the detergents. We have determined the specific activities of gamma emitting radionuclides belonging to the natural families of uranium, thorium and potassium using gamma spectrometry. The activities of radionuclides ( 235 U, 238U , 226 Ra, 232 Th, 40K) and their descendants are below the minimum detectable activity for dishwasher products, soaps, bleaches and shampoos, whereas they are found to levels considered very low (between 0,2 and 13 Bq/kg on average) in the products washes linens. These values are always lower than those of raw materials, what is explained by the conservation of radioactive material throughout the manufacturing process. The effective dose due to external exposure estimated below the regulatory standard recommended (<1 mSv / year), allows us to show that detergent products are not contaminated by radioactivity, are healthy and do not have harmful radiological impact on the consumer.

Long-term management of the existing radioactive wastes and residues at the Niagara Falls Storage Site. Draft Environmental Impact Statement

International Nuclear Information System (INIS)

1984-08-01

The statement assesses and compares several alternatives for long-term management of the existing radioactive wastes and residues at the Niagara Falls Storage Site (NFSS), Lewiston, New York. The alternatives include: (1) no action (continued interim storage at NFSS within a diked and capped containment area), (2) long-term management at NFSS (improved containment, with or without modified form of the residues), (3) long-term management at other DOE sites (Hanford, Washington, or Oak Ridge, Tennessee), and (4) offsite management of the residues at Hanford or Oak Ridge and either leaving the wastes at NFSS or removing them for disposal in the ocean. In addition to alternatives analyzed in depth, several options are also considered, including: other modifications of residue form, modification of the basic conceptual designs, other containment design options, transportation routes, and transportation modes. The radiological health effects (primarily increased risk of cancer) associated with long-term management of the wastes and residues are expected to be smaller than the nonradiological risks of occupational and transportation-related injuries and deaths. During the action period, the risk is highest for workers if all wastes and residues are moved to Hanford. The risk is highest for the general public if the residues are moved to Hanford and the wastes are moved to the ocean. Dispersal of the slightly contaminated wastes in the ocean is not expected to result in any significant impacts on the ocean environment or pose any significant radiological risk to humans. For all alternatives, if controls ceased, there would be eventual dispersion of the radioactive materials to the environment. If it is assumed that all controls cease, predicted time for loss of covers over the buried materials ranges from several hundred years to more than two million years, depending on the use of the land surface

A study on the production of agricultural residues in Italy

Energy Technology Data Exchange (ETDEWEB)

Di Blasi, C.; Tanzi, V.; Lanzetta, M. [Universita degli Studi di Napoli Federico II, Dip di Ingegneria Chimica, Napoli (Italy)

1997-12-01

The Italian production of agricultural residues has been evaluated with a view to energy recovery through gasification. Two main categories of residues have been identified: the first, (A) is associated with the growing and collection of products with a nutritional value, whereas the second (B) includes the residues associated with the subsequent processing in order to obtain final products for commercialization. Category A, which comprises three further sub-categories: straw (A1); woody residues (A2); and stems and leaves (residues from vegetables, tobacco, sugar beet, (A3)), results in about 16.5 mt yr. The average amount of straw (A1) is 11 mt/yr, of which about 60% is waste to be eliminated. Woody residues (A2) (mainly pruning off-cuts from vineyards and olive groves) are about 3.5 mt/yr (85% unused). Category A3 amounts to about 2 mt/yr (90% unused). Straw is available mainly in the northern part of the country, whereas the other two sub-categories are widely distributed in central and southern regions. The yields of category B are estimated at 4 mt/yr, of which more than 3 mt/yr are waste products from grape and olive processing. Other residues, such as rice, sunflower and soya-bean husks (about 0.65 mt/yr), almond and nut shells and fruit stones (about 0.2 mt/yr), although not widely available on a national scale, can be significant on a local basis. The total amount of unused agricultural residues is about 14.5 mt/yr, which, if completely exploited through gasification, can contribute as much as 7-10% to the current national electricity needs. The regions of Veneto, Puglia, Friuli, Lombardia and Emilia Romagna appear to be good candidates for electricity production, given the significant surface concentration of unused residues (105-55 t km{sup 2}). (author)

Derivation of residual radioactive material guidelines for uranium in soil at the Middlesex Sampling Plant Site, Middlesex, New Jersey

International Nuclear Information System (INIS)

Dunning, D.E.

1995-02-01

Residual radioactive material guidelines for uranium in soil were derived for the Middlesex Sampling Plant (MSP) site in Middlesex, New Jersey. This site has been designated for remedial action under the Formerly Utilized Sites Remedial Action Program (FUSRAP) of the US Department of Energy. The site became contaminated from operations conducted in support of the Manhattan Engineer District (MED) and the Atomic Energy Commission (AEC) between 1943 and 1967. Activities conducted at the site included sampling, storage, and shipment of uranium, thorium, and beryllium ores and residues. Uranium guidelines for single radioisotopes and total uranium were derived on the basis of the requirement that the 50-year committed effective dose equivalent to a hypothetical individual living or working in the immediate vicinity of the MSP site should not exceed a dose of 30 mrem/yr following remedial action for the current-use and likely future-use scenarios or a dose of 100 mrem/yr for less likely future-use scenarios. The RESRAD computer code, which implements the methodology described in the DOE manual for establishing residual radioactive material guidelines, was used in this evaluation. Four scenarios were considered for the site. These scenarios vary regarding future land use at the site, sources of water used, and sources of food consumed

[The main directions of improving the system of state accounting and control of radioactive substances and radioactive waste products].

Science.gov (United States)

2012-01-01

This paper describes a modification of the basic directions of state accounting and control of radioactive substances and radioactive waste products, whose implementation will significantly improve the efficiency of its operation at the regional level. Selected areas are designed to improve accounting and control system for the submission of the enterprises established by the reporting forms, the quality of the information contained in them, as well as structures of information and process for collecting, analyzing and data processing concerning radioactive substances and waste products.

Method of solidifying radioactive waste

International Nuclear Information System (INIS)

Hasegawa, Akira; Mihara, Shigeru; Yamashita, Koji; Sauda, Kenzo.

1988-01-01

Purpose: To obtain satisfactory plastic solidification products rapidly and more conveniently from radioactive wastes. Method: liquid wastes contain, in addition to sodium sulfate as the main ingredient, nitrates hindering the polymerizing curing reactions and various other unknown ingredients, while spent resins contain residual cationic exchange groups hindering the polymerizing reaction. Generally, as the acid value of unsaturated liquid polyester resins is lower, the number of terminal alkyd resins is small, formation of nitrates is reduced and the polymerizing curing reaction is taken place more smoothly. In view of the above, radioactive wastes obtained by dry powderization or dehydration of radioactive liquid wastes or spent resins are polymerized with unsaturated liquid polyester resins with the acid value of less than 13 to obtain plastic solidification. Thus, if the radioactive wastes contain a great amount of polymerization hindering material such as NaNO 2 , they can be solidified rapidly and conveniently with no requirement for pre-treatment. (Kamimura, Y.)

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)

Radioactive beam production at the Bevalac

International Nuclear Information System (INIS)

Alonso, J.R.; Feinberg, B.; Kalnins, J.G.; Krebs, G.F.; McMahan, M.A.; Tanihata, I.

1989-10-01

At the Bevalac radioactive beams are routinely produced by the fragmentation process. The effectiveness of this process with respect to the secondary beam's emittance, intensity and energy spread depends critically on the nuclear reaction kinematics and the magnitude of the incident beam energy. When this beam energy significantly exceeds the energies of the nuclear reaction process, many of the qualities of the incident beam can be passed on to the secondary beam. Factors affecting secondary beam quality are discussed along with techniques for isolating and purifying a specific reaction product. The on-going radioactive beam program at the Bevalac is used as an example with applications, present performance and plans for the future. 6 refs., 6 figs., 1 tab

Surveillance of radioactivity in imported foods marketed in Aichi Prefecture

International Nuclear Information System (INIS)

Ohnuma, Shoko; Kosako, Maki; Tomita, Banichi

2002-01-01

To assess the effects of radioactive contamination by the Chernobyl nuclear plant accident, the authors examined imported foods marketed in Aichi Prefecture from 1988 to 1999 for residual radioactivity. The concentration of both 134 Cs and 137 Cs was determined with an NaI(Tl) detector in 940 samples, including cereals and processed cereals (23%), vegetables and processed vegetables (19%), fruits and processed fruits (17%), including wines (6%), cheese and dairy products (12%), drinking water (11%), confections (6%), and other foods (12%). The countries of origin were Italy (35%), France (2%), Germany (5%), Denmark (4%), the Netherlands (4%), other European Countries (21%), the United States (5%), and other Countries (5%). None of the imported foods tested contained a total residual 134 Cs and 137 Cs radioactivity exceeding 370 Bq/Kg, the preliminary limit set by the government, but 1.3% of the imported foods contained more than 5 Bq/Kg, the lower limit of detection. Both the numbers and rates of imported foods containing radioactivity have clearly been decreasing since the accident, but it was noteworthy that raspberry juice produced in the Netherlands in 1998, 12 years after the accident, contained the highest level of residual radioactivity in this survey (94 Bq/Kg). If it were processed to enriched juice and jam, its radioactivity might exceed the preliminary limit. Since processed and enriched fruits are not currently included among inspected foods, fruits in them whose radioactivity exceeds the limit can be marketed, and thus the present inspection system should be assessed. The preliminary radioactivity limit was determined based on the accident at the Chernobyl nuclear plant, and it will be necessary to set new preliminary limits if a new, unexpected nuclear accident occurs. This surveillance data is expected to served as reference data. (K.H.)

Safety aspects of targets for ADTT: Activity, volatile products, residual heat release

International Nuclear Information System (INIS)

Gai, E.V.; Ignatyuk, A.V.; Lunev, V.P.; Shubin, Yu.N.

1999-01-01

Safety aspects of heavy metal liquid targets for the accelerator driven systems connected with the activity accumulation and residual energy release due to the irradiation with high energy proton beam are discussed. The results obtained for the lead-bismuth target that are under construction in IPPE now in the frame of ISTC Project No. 559 are briefly presented. The calculations and the analysis of the accumulation of the spallation reaction products, activity and energy release at various moments after the accelerator shutdown are presented. The concentrations of the reaction products, the total and partial activities, the activities of volatile products are determined. The contributions of the short-lived nuclides important for the prediction of the facility behaviour in regimes with the accelerator beam trips. The calculations and analysis of the residual energy release due to different decay type have been performed. The conclusions are as follows. The obtained results showed that long lived radioactivity accumulates mainly due to primary nuclear reactions. Secondary reactions are responsible for the production of small number of long-lived isotopes Bi-207, Po-210 and some others, being generated by radiative capture of low energy neutrons. It is possible to make a conclusion that neutrons in the energy range 20 - 800 MeV and protons with energy above 100 MeV give main contribution to the total activity generation although these parts of spectra inside the target give comparatively small contribution to the total flux. The correct consideration of short-lived nuclides contribution is the main problem in the analysis of the target behaviour in the case of short accelerator shutdowns. They make the determining contribution to the both activity and the heat release at the first moments after the accelerator shutdown, creating the intermediate links and additional channels for the long-lived nuclides accumulation chains. The strong dependence of calculated

Characterization of residual oils for biodiesel production

Directory of Open Access Journals (Sweden)

Edmilson Antonio Canesin

2014-01-01

Conclusions: The obtained results suggesting that it is possible to take advantage of these residues for biodiesel production as the obtained products were approved according to the rules established by the National Association of Petroleum (ANP; the bovine samples were the exception regarding moisture and acidity.

Modelling of radioactive fallout in the vicinity of Chernobyl nuclear power plant accident

International Nuclear Information System (INIS)

Israel, Y.A.; Petrov, V.N.; Severov, D.A.

1988-03-01

Deposition of radioactive products escaping into the atmosphere for a long time from the Chernobylsk-4 reactor resulting in residual radioactive contamination of the region at a distance of up to 100 km from the nuclear power plant is considered. The suggested model may be used for estimation of the possible scope of nuclear danger in the regions of nuclear power plants and creation of conditions ensuring safety of the population at possible accidents. The following topics are developed: height of elevation and conditions of radionuclide transfer in the atmosphere; dynamics of release and dispersive composition of radioactive products; calculations of radiation levels at a close trace [fr

Radioactive environmental impact assessment for a production project of titanium dioxide by chlorination process

International Nuclear Information System (INIS)

Qiu Guohua

2010-01-01

Based on the analysis of shifting direction of radionuclide in production process and the environmental investigation and monitoring, the radioactive environmental impact from a production project of titanium dioxide by chlorination process has been analyzed and assessed. The result of radioactive environmental investigation shows that values of assessment factors are in the range of environmental radioactive background. The radioactive environmental sensitive spot has been delineated. The results of radioactive environmental prediction show that the additional doses to workers and residents are 0.59 mSv/a and 9.28 × 10-4 mSv/a respectively which are less than the annual dose limits of administration. The radioactive environmental impact of the production project of the titanium dioxide by chlorination process will meet the needs of national regulations and standards if radiation protection and environmental protection measures are implemented and radioactive environmental monitoring are strengthened. (author)

Derivation of cesium-137 residual radioactive material guidelines for the Peek Street site, Schenectady, New York

International Nuclear Information System (INIS)

Jones, L.; Nimmagadda, M.; Yu, C.

1992-01-01

Residual radioactive material guidelines for cesium-137 were derived for the Peek rk. The derivation was based on the requirement that the Street site in Schenectady, New York. The derivation was based on the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of the Peek Street site should not exceed a dose of 100 mrem/yr following remedial action. The US Department of Energy (DOE) residual radioactive material guideline computer code, RESRAD was used in this evaluation. Three potential scenarios were considered for the site on the assumption that for a period of 1,000 years following remedial action, the site wig be utilized without radiological restrictions. The scenarios vary with regard to use of the site, time spent at the site, and sources of food consumed. Results indicate that the basic dose limit of 100 mrem/yr will not be exceeded for cesium-137 within 1,000 years, provided that the soil concentration of cesium-137 at the Peek Street site does not exceed the following levels: 98 pCi/g for Scenario A (industrial worker: the expected scenario), 240 pCi/g for Scenario B (recreationist: a plausible scenario), and 34 pCi/g for Scenario C (resident farmer ingesting food produced in the decontaminated area: a plausible scenario)

Bioaccumulation and food chain transfer of corrosion products from radioactive stainless steel

International Nuclear Information System (INIS)

Young, J.S.

1986-07-01

Two sets of experiments were conducted to determine if corrosion products from radioactive Type 347 stainless steel could be biologically transferred from sediment through a marine food chain, and whether corrosion products dissolved in seawater could be bioaccumulated and then eliminated. Corrosion products containing 60 Co and 63 Ni from the radioactive stainless steel were introduced into marine sediments. Infaunal polychaete worms exposed to these sediments bioaccumulated the radionuclides. The feeding of these worms to shrimp and fish resulted in a trophic transfer of the radioactive products across a one-step food chain. The magnitude of the transfers are described in terms of transfer factors. Dissolved corrosion products as measured by the radionuclides were also bioaccumulated by shrimp and fish concentrating more than fish. Concentration factors were calculated

A product designed for final disposal of low and intermediate level radioactive wastes

International Nuclear Information System (INIS)

Baboescu, E.; Popescu, I. V.

2001-01-01

The product 'metallic barrel - concrete - low level radioactive wastes - 1' (ABBD - 1) was certified according to the company's standard SF ICN/1994, updated 1. The product ABBD -1 is produced according to the following certified technologies: - technology for processing and conditioning of low level radioactive solid wastes; - technology for processing and conditioning of waste ion exchangers from the TRIGA reactor; - technology for conditioning the β - γ radioactive compacts. The product is constituted of a protection shield, the concrete block - radioactive waste, securing high mechanical strength and a high degree of radionuclides retaining, thus ensuring the necessary condition for long time disposal and, finally, the metallic container fulfilling the National Standards of Nuclear Safety for Radioactive Materials Transportation. The metallic container is made of pickled slab, with a 220 l capacity, according to STAS 7683/88 standards. The main characteristics of the product 'ABBD - 1' are: - size: height, 915 ± 10 mm, diameter, 600 ± 5 mm; - mass, 300 - 600 kg; - maximum permissible activity, 6 x 10 9 Bq/ barrel (0.164 Ci/barrel); - equivalent dose rate for gamma radiation at barrel's wall, max. 1 mSv/h (200 mrem/h); - unfixed external contamination, 2 ; - compression strength of concrete block alone, > 5 x 10 6 N/m 2 ; - lixiviation rate, -3 cm/day; - the compact concrete block-radioactive waste is leak-proof and crack-free. The final product is transferred from INR Pitesti to National Repository for Radioactive Waste by railway and road transportation according to the provisions of the National Commission for Nuclear Activity Control as stipulated in the National Standards of Nuclear Safety of Radioactive Materials Transportation

Residual biomass resources for energy production. Extended abstract

International Nuclear Information System (INIS)

Prevot, G.

2010-06-01

This report covers the whole problematic of energy production from biomass residues in France except the production of biofuels. It is made of two parts. The first one gives an overview of the availability of residual biomass resources, The concept of residue (or waste) is placed in its economic and regulatory context (the major part of the resource cannot be considered as waste without any further potential use). The conditions of availability of the resource for each market segment are identified. The second part describes the conditions for the use of 5 different conversion options of these residues into energy. The logistics constraints for the procurement of the fuel and the intermediate operations to prepare it are briefly summarised. The objective was the identification of key issues in all relevant aspects, without giving too much emphasis to one of them at the expense of another one in order to avoid duplicating the frequent cases of facilities that do not meet environmental and economic targets because the designers of the system have not paid enough attention to a parameter of the system. (author)

Handling of Solid Residues

International Nuclear Information System (INIS)

Medina Bermudez, Clara Ines

1999-01-01

The topic of solid residues is specifically of great interest and concern for the authorities, institutions and community that identify in them a true threat against the human health and the atmosphere in the related with the aesthetic deterioration of the urban centers and of the natural landscape; in the proliferation of vectorial transmitters of illnesses and the effect on the biodiversity. Inside the wide spectrum of topics that they keep relationship with the environmental protection, the inadequate handling of solid residues and residues dangerous squatter an important line in the definition of political and practical environmentally sustainable. The industrial development and the population's growth have originated a continuous increase in the production of solid residues; of equal it forms, their composition day after day is more heterogeneous. The base for the good handling includes the appropriate intervention of the different stages of an integral administration of residues, which include the separation in the source, the gathering, the handling, the use, treatment, final disposition and the institutional organization of the administration. The topic of the dangerous residues generates more expectation. These residues understand from those of pathogen type that are generated in the establishments of health that of hospital attention, until those of combustible, inflammable type, explosive, radio-active, volatile, corrosive, reagent or toxic, associated to numerous industrial processes, common in our countries in development

Investigation on natural radioactive nuclide contents of rock products in Xi'an construction materials market

International Nuclear Information System (INIS)

Zhou Chunlin; Han Feng; Shang Aiguo; Li Tiantuo; Guo Huiping; Yie Lichao; Li Guifang

2001-01-01

The author reports the investigation results on natural radioactive nuclide contents of rock products from Xi'an construction materials market. The products were classified according to the national standard. The results show that natural radioactive nuclide contents in sampled rock products are in normal radioactive background levels. The radio-activity ranges of 238 U, 226 Ra, 232 Th and 40 K are 2.7 - 181.8, 0.92 - 271.0, 0.63 - 148.0, 1.8 - 1245 Bq·kg -1 , respectively. According to the national standard (JC 518-93), the application of some rock products must be limited

Phase II, Title I engineering assessment of radioactive sands and residues, Lowman Site, Lowman Idaho

Energy Technology Data Exchange (ETDEWEB)

1977-12-01

An engineering assessment was performed of the problems resulting from the existence of radioactive uranium sand residues at the Lowman, Idaho, site. Services normally include the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and other radium-contaminated materials, the evaluation of resulting investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas release from the 90,000 tons of sand residues at the Lowman site constitutes the most significant environmental impact, although external gamma radiation is also a factor. The two alternative actions presented are dike construction, fencing, and maintenance (Option I); and consolidation of the piles, addition of a 2-ft-thick stabilization cover, and on-site cleanup (Option II). Both options include remedial action at off-site structures. Cost estimates for the two options are $393,000 and $590,000.

Phase II, Title I engineering assessment of radioactive sands and residues, Lowman Site, Lowman Idaho

International Nuclear Information System (INIS)

1977-12-01

An engineering assessment was performed of the problems resulting from the existence of radioactive uranium sand residues at the Lowman, Idaho, site. Services normally include the preparation of topographic maps, the performance of core drillings and radiometric measurements sufficient to determine areas and volumes of tailings and other radium-contaminated materials, the evaluation of resulting investigations of site hydrology and meteorology, and the evaluation and costing of alternative corrective actions. Radon gas release from the 90,000 tons of sand residues at the Lowman site constitutes the most significant environmental impact, although external gamma radiation is also a factor. The two alternative actions presented are dike construction, fencing, and maintenance (Option I); and consolidation of the piles, addition of a 2-ft-thick stabilization cover, and on-site cleanup (Option II). Both options include remedial action at off-site structures. Cost estimates for the two options are $393,000 and $590,000

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

International Nuclear Information System (INIS)

Wan Rongsheng

2004-01-01

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

Radioactive sources production in the Boris Kidric Institute of nuclear sciences

International Nuclear Information System (INIS)

Radosavljevic, B.; Nemoda, Dj.; Memedovic, T.; Bircanin, LJ.

1978-01-01

Since 1960, in the Laboratory for radioisotopes production of the Institute isotopes were produced for industrial, medical and research purposes. From the beginning, this activity was developed in two directions: 1. sealed sources, for industrial radiography, teletherapy Cobalt, later for lightning arresters, level meters, densitometers etc., 2. radioactive sources that need chemical treatment for different applications in industry and research. This paper lists the types of radioactive sources and methods for production [sr

Review on Sources and Handling Method of Pesticide Residues in Animal Products

Directory of Open Access Journals (Sweden)

Indraningsih

2006-06-01

Full Text Available Field studies and literature search showed that some pesticide residues either organochlorines (OC or organophosphates (OP were detected in animal products (meat and milk . Pesticide residues in meat collected from West Java were detected at the level of 0 .8 ppb lindane and 62 ppb diazinon . While in meat from Lampung was detected at the level of 7 ppb lindane . 2 .7 heptachlor, 0 .8 endosulfan and 0 .5 ppb aldrin . Furthermore, pesticide residues were also detected in the milk collected from West, Central and East Java . The levels of lindane were 2,3 ; 15,9 ; 0,2 ppb ; heptachlor 8 ; 0 .4 and 0,05 ppb; diazinon 8 ; 0 and 1,8 ppb; CPM 0,4 ; 0,8 and 0 ppb ; endosulfan 0,1 ; 0,04 and 0,05 ppb for West, Central and East Java, respectively . The source of pesticide contamination in animal products is generally originated from feed materials, fodders . contaminated soils and water around the farm areas . Minimalization approach of pesticide residues in animal products could be conducted integratedly, such as through chemical process, biodegradation using microorganisms . Organic farming system is recognised as an alternative that may be applied to minimise contamination on agricultural land, eventually reducing pesticide residues in the agricultural products . Feeding with organic agricultural by-products with low pesticide residues appears to reduce pesticide residues in animal products . In order to eliminate pesticide contamination in soil, it has to be conducted progressively by implementing sustainable organic farming .

Radioactive waste products 2002 (RADWAP 2002). Proceedings

International Nuclear Information System (INIS)

Odoj, R.; Baier, J.; Brennecke, P.; Kuehn, K.

2003-01-01

The 4 th International Seminar on Radioactive Waste Products was organised by the Forschungszentrum Juelich in co-operation with the Bundesamt fuer Strahlenschutz and the European Commission. On behalf of the Bundesamt, I would like to welcome all participants of this scientific-technical meeting. I very much appreciate the participation not only of numerous German scientists, engineers and technicians as well as governmental and industrial representatives, but would particularly express my gratitude for the participation of many colleagues from abroad. Radioactive waste management and disposal is a worldwide issue and international co-operation to support national programmes is therefore much appreciated. The international organisations provide, among other things, guidance to member countries on safe, economic and environmentally acceptable solutions for radioactive waste disposal. On a national basis respective programmes are developed, modified or successfully realized. Nevertheless, the challenge of radioactive waste management and disposal is no longer a scientific and technical exclusivity. The importance of ethical and social aspects, the dialogue with the public and transparency in decision-making processes increase more and more. Thus, when addressing safety-related key questions one needs to be as open as possible on scientific-technical aspects and to consider the involvement of the public requiring a clear, open-minded and transparent communication. (orig.)

Dose estimation from residual and fallout radioactivity, 1

International Nuclear Information System (INIS)

Takeshita, Kenji

1975-01-01

External dose rates and cumulative doses for early entrants from areal surveys and simulated experiments are reviewed. The average cumulative doses to infinity at the hypocenters were 101 rad in Hiroshima and 32 rad in Nagasaki, with a variation of about 60 percent. Radioactive fallout areas nearly matched the ''black rain'' areas in Nagasaki and in Hiroshima. Radioactivity in the fallout areas was affected by radioactive decay and by the leaching and dissipation by rains. Considering these factors, the cumulative dose to infinity in the fallout area of Hiroshima was estimated to be 13 rad, excluding internal radiation doses from inhaled and ingested radionuclides. Attempts to estimate radiation dose from internally deposited radionuclides are also described. (auth.)

Transfer of radioactive contamination from milk to commercial dairy products

International Nuclear Information System (INIS)

Wilson, L.G.; Sutton, P.M.

1988-01-01

The fate of radioactive contamination resulting from fallout from the Chernobyl accident was studied during milk processing. A range of commercial dairy products was produced on a pilot-laboratory scale and the radiocaesium contents were measured by high-resolution gamma spectrometry. The results show that the radiocaesium partitioned with the water phase and therefore butter, cream and cheese had relatively low levels of radioactivity. Ion exchange demineralization was effective in removing radiocaesium from whey. Ultrafiltration of whey resulted in a reduction of radioactivity relative to retentate solids. (author)

BEES AS BIOINDICATORS TO GUARANTEE HEALTHY PRODUCTS FOR THE CONSUMER

Directory of Open Access Journals (Sweden)

B. Brusa

2011-04-01

Full Text Available Many investigators have employed honeybees or honeybee products as tools for assessing environmental pollution in industrial areas. The pollution in northwest Italy by insecticides used in crop protection, heavy metals and radioactivity has been investigated utilizing, as a bioindicator: honeybees, bee honey, wax, pollen produced in this area. Honeybees and honeybee products samples collected from 6 apiaries located in this area were analyzed for neonicotinoids residues with LC/MS method, pesticides organochlorines and organophosphates by GCECD and GC-NPD methods, PCB using GC-MS, radioactivity on 137Cs by g spectrometer and heavy metals with atomic spectroscopy. The results show: 19 honeybee samples were positive on neonicotinoids (clothianidin residues (total of 78 samples, no one sample was positive on pesticides organochlorines and organophosphates residues (total of 32 honeybee samples, the radioactivity levels were always below the instrumental limit determination, at last the heavy metal content (Pb, Cd, Cr on 21 honey samples was favorable. This study indicates that in agricultural areas with developed apiculture, useful information about the occurrence and the distribution of pesticide residues due to crop protection treatments can be derived from the analysis of randomly collected honeybee products samples, used as bioindicators.

Waste vinegar residue as substrate for phytase production.

Science.gov (United States)

Wang, Zhi-Hong; Dong, Xiao-Fang; Zhang, Guo-Qing; Tong, Jian-Ming; Zhang, Qi; Xu, Shang-Zhong

2011-12-01

Waste vinegar residue, the by-product of vinegar processing, was used as substrate for phytase production from Aspergillus ficuum NTG-23 in solid-state fermentation to investigate the potential for the efficient re-utilization or recycling of waste vinegar residue. Statistical designs were applied in the processing of phytase production. First, a Plackett-Burman (PB) design was used to evaluate eleven parameters: glucose, starch, wheat bran, (NH(4))(2)SO(4), NH(4)NO(3), tryptone, soybean meal, MgSO(4)·7H(2)O, CaCl(2)·7H(2)O, FeSO(4)·7H(2)O, incubation time. The PB experiments showed that there were three significant factors: glucose, soybean meal and incubation time. The closest values to the optimum point were then derived by steepest ascent path. Finally, a mathematical model was created and validated to explain the behavioural process after these three significant factors were optimized using response surface methodology (RSM). The best phytase activity was attained using the following conditions: glucose (7.2%), soybean meal (5.1%), and incubation time (271 h). The phytase activity was 7.34-fold higher due to optimization by PB design, steepest ascent path design and RSM. The phytase activity was enhanced 0.26-fold in comparison with the results by the second step of steepest ascent path design. The results indicate that with waste vinegar residue as a substrate higher production of phytase from Aspergillus ficuum NTG-23 could be obtained through an optimization process and that this method might be applied to an integrated system for recycling of the waste vinegar residue.

Map of calculated radioactivity of fission product, 3

International Nuclear Information System (INIS)

Takeda, Tsuneo

1977-02-01

In this work, the radioactivities of fission products were calculated and summarized in contour maps and tables depending on irradiation and cooling times. The irradiation condition and other parameters used for the present calculation are shown in the followings. Neutron flux (N sub(th)): 3x10 13 n/sec/cm 2 Atom number of uranium: 1 mole (6x10 23 , ca. 271 gUO 2 ) Enrichment of U-235: 2.7% Range of irradiation time: 60-6x10 7 sec (ca. 1.9 y) Range of cooling time: 60-6x10 7 sec (ca. 1.9 y). Values of the neutron flux and the enrichment treated here are representative for common LWRs. The maps and tables of 560 nuclides are divided and compiled into the following three volumes. Vol. I: Maps of radioactivity of overall total, element total and each nuclide (Ni - Zr), Vol. II: Maps of radioactivity of each nuclide (Nb - Sb), Vol. III: Maps of radioactivity of each nuclide (Te - Tm). (auth.)

Map of calculated radioactivity of fission product, (1)

International Nuclear Information System (INIS)

Takeda, Tsuneo

1977-02-01

In this work, the radioactivities of fission products were calculated and summarized in contour maps and tables depending on irradiation and cooling times. The irradiation condition and other parameters used for the present calculation are shown in the followings. Neutron flux (N sub(th)): 3x10 13 n/sec/cm 2 Atom number of uranium: 1 mole (6x10 23 , ca. 271 gUO 2 ) Enrichment of U-235: 2.7% Range of irradiation time: 60-6x10 7 sec (ca. 1.9 y) Range of cooling time: 60-6x10 7 sec (ca. 1.9 y). Values of the neutron flux and the enrichment treated here are representative for common LWRs. The maps and tables of 560 nuclides are divided and compiled into the following three volumes. Vol. I Maps of radioactivity of overall total, element total and each nuclide (Ni - Zr) Vol. II Maps of radioactivity of each nuclide (Nb - Sb) Vol. III Maps of radioactivity of each nuclide (Te - Tm) (auth.)

Map of calculated radioactivity of fission product, 2

International Nuclear Information System (INIS)

Takeda, Tsuneo

1977-02-01

In this work, the radioactivities of fission products were calculated and summarized in contour maps and tables depending on irradiation and cooling times. The irradiation condition and other parameters used for the present calculation are shown in the followings. Neutron flux (N sub(th)): 3x10 13 n/sec/cm 2 Atom number of uranium: 1 mole (6x10 23 , ca. 271 gUO 2 ) Enrichment of U-235: 2.7% Range of irradiation time: 60-6x10 7 sec (ca. 1.9 y) Range of cooling time: 60-6x10 7 sec (ca. 1.9 y). Values of the neutron flux and the enrichment treated here are representative for common LWRs. The maps and tables of 560 nuclides are divided and compiled into the following three volumes. Vol. I: Maps of radioactivity of overall total, element total and each nuclide (Ni - Zr), Vol. II: Maps of radioactivity of each nuclide (Nb - Sb), Vol. III: Maps of radioactivity of each nuclide (Te - Tm). (auth.)

Treatment of Radioactive Waste Generated from the Production of Molybdenum-99 Radioisotope

International Nuclear Information System (INIS)

Aisyah; Herlan Martono

2007-01-01

The 99 Mo is produced as the parent radionuclide for 99m Tc radioisotope which is used as medical radiodiagnostic for certain disease. In Indonesia 99 Mo is produced by irradiating target of high enriched U in the reactor. The characteristics of radioactive waste from the production of 99 Mo depend on the U enrichment of the target and the irradiation time. The characteristic of the radioactive waste can be directly determined by laboratory analysis or by ORIGEN 2 code. Producing 99 Mo from high enriched uranium target will produce radioactive waste containing 235 U, 238 U and fission product, while from low enriched uranium target will produce radioactive waste containing large amount of 239 Pu. Plutonium-239 is a long half life actinide that need to be separated from the fission product due to a different treatment is required. The fission product, after it is allowed to decay then needs to be categorized as low or medium level waste, while 239 Pu are categorized as transuranic waste. The disposal of low and medium level waste are stored in near surface disposal, while the disposal of transuranic waste is stored in a geologic formation. (author)

On the role of the residual stress state in product manufacturing

NARCIS (Netherlands)

Zijlstra, G.; Groen, M.; Post, J.; Ocelik, V.; de Hosson, J.Th.M.

2016-01-01

This paper concentrates on the effect of the residual stress state during product manufacturing of AISI 420 steel on the final shape of the product. The work includes Finite Element (FE) calculations of the distribution of the residual stresses after metal forming and a heat treatment. The evolution

ENTRIA 2014. Memorandum on the disposal of high-level radioactive residuals; ENTRIA 2014. Memorandum zur Entsorgung hochradioaktiver Reststoffe

Energy Technology Data Exchange (ETDEWEB)

Roehlig, Klaus-Juergen; Walther, Clemens; Bach, Friedrich-Wilhelm [Niedersaechsische Technische Hochschule, Braunschweig, Clausthal-Zellerfeld, Hannover (Germany); and others

2014-04-30

The memorandum on the disposal of high-level radioactive residuals covers the following issues: description of the problem: a ''wicked problem'', risks and NIMBY, the site selection law, international boundary conditions; disposal strategy and types of facilities: safety and reversibility, long-term surface storage, deep storage; risk and safety; procedural justice and the site selection process; social innovations and the requirement of long-term institutions; conclusion - central stress fields.

Regulatory requirements for the use of consumer products containing radioactive substances

International Nuclear Information System (INIS)

Mason, G.C.; Paynter, R.A.; Schmitt-Hannig, A.; Sztanyik, L.B.

1996-01-01

In almost 100 years since the discovery of radioactivity, the properties of radioactive materials have been exploited in products such as clocks and watches incorporating luminous paint which are freely available to members of the public. Over time, regulatory authorities have felt it necessary to apply some degree of control to the supply and use of such products in order to protect public health. In many areas of radiation protection, national authorities take note of international recommendations when developing national standards, but the existing detailed guidance of the International Atomic Energy Agency (IAEA) for consumer products is incomplete and out of date. Recently, a thorough revision of the International Basic Safety Standards (BSS) has occurred, which has prompted a review and revision of the related guidance published by the IAEA. A draft Guide on Regulatory Requirements for the Use of Consumer Products Containing Radioactive Substances has now been completed and is currently under review within the IAEA's system for development of documents in its Safety Series of publications. (author)

Survey of product quality control of radioactive waste

International Nuclear Information System (INIS)

Warnecke, E.

1989-01-01

The PTB has developed basic procedures with regard to deriving final storage conditions and product quality control. After this, requirements for radioactive waste are derived via safety analysers, in which information about the radioactive waste, the geological overall situation of the site and the layout of the final storage mine, in particular, are included as basic data. The final storage conditions are only determined with the awarding of the planning decision. Compliance with them can be proved by random sample tests on waste containers or via a qualification and inspection of the conditioning process. (DG) [de

Radioactivity transfer to animal products

International Nuclear Information System (INIS)

Coughtrey, P.J.

1990-01-01

Information on the behaviour of strontium, caesium, ruthenium, plutonium and americium in a range of domestic animals is reviewed to form a basis for the specification of time-dependent mathematical models describing uptake, distribution and retention in various domestic animals. Transfer factors relating concentration in animal product to daily radioactivity intake are derived after 100 d continuous intake and at equilibrium. These transfer factors are compared with the available published literature and used as a basis for the derivation of feedingstuff conversion factors relating limiting concentrations in animal feedingstuffs to limiting concentrations in human foodstuffs for application to animals receiving commercial feedingstuffs after a nuclear accident. Recommended transfer factors for animal products in conditions of continuous discharge and models for application to field conditions after a nuclear accident are also presented. Transfer of caesium to animal products is more effective than that for the other elements considered here. Transfer to meat of lamb, fattening pig, and chickens is generally more effective than that for other animals and other products

Natural radioactivity in the production of titanium dioxide pigment: a study of the Laporte Plant and environment behaviour of radionuclides at Bunbury, Western Australia

International Nuclear Information System (INIS)

Cooper, M.B.; Statham, J.R.; Williams, G.A.

1981-10-01

A study of radioactivity levels in samples collected at a titanium dioxide plant at Bunbury in Western Australia is described. The radioactivities of the principal radionuclides present in the ilmenite feed ( 226 Ra, 228 Ra, and 228 Th) are followed throughout the pigment production process. It is found that approximately 67 MBq/day of activity due to each of 228 Ra and 228 Th enters the plant (equivalent to 17.8 kg of thorium), and approximately 14 MBq/day of activity due to 226 Ra. Essentially all of this radioactivity leaves the plant in the form of acidic effluent, which is pumped to disposal lagoons and allowed to neutralise and drain away. A preliminary study of possible environmental effects of radioactivity in the effluent is presented. It was established that in the presence of high sulphate ion concentrations in both the plant feed liquor and the effluent, thorium remains in solution whereas radium, which forms an insoluble sulphate compound, tends to coprecipitate and is found in solid residues throughout the process

Agro-residues as Alternative for Xylanase Production by Filamentous Fungi

Directory of Open Access Journals (Sweden)

Adriana Knob

2014-07-01

Full Text Available Agro-industrial wastes are the most abundant renewable resource on earth and are available in large quantities. However, the disposal of these wastes presents an increasing environmental problem. Recently, there has been a great interest in the exploitation of these wastes as low-cost raw materials for the production of value-added compounds as microbial enzymes by submerged or solid-state fermentation systems. This review focuses on alternatives for xylanase production using agro-residues as substrates. In recent years, the interest in xylanase, which plays an important role in the breakdown of xylan, has markedly increased due to its wide variety of biotechnological applications. Among several agro-industrial residues that have been intensively investigated, many, such as wheat bran, wheat straw, and sugarcane bagasse, are suitable and result in high yields of xylanase, leading to low production costs. In addition, many relatively unexplored residues, such as oil palm wastes, sorghum straw, and coffee by-products, are some of the most promising substrates for xylanase production, requiring further assessment.

Production of radioactive nuclides in inverse reaction kinematics

International Nuclear Information System (INIS)

Traykov, E.; Rogachevskiy, A.; Bosswell, M.; Dammalapati, U.; Dendooven, P.; Dermois, O.C.; Jungmann, K.; Onderwater, C.J.G.; Sohani, M.; Willmann, L.; Wilschut, H.W.; Young, A.R.

2007-01-01

Efficient production of short-lived radioactive isotopes in inverse reaction kinematics is an important technique for various applications. It is particularly relevant when the isotope of interest is only a few nucleons away from a stable isotope. In this article production via charge exchange and stripping reactions in combination with a magnetic separator is explored. The relation between the separator transmission efficiency, the production yield, and the choice of beam energy is discussed. The results of some exploratory experiments will be presented

Machine for compacting solid residues

International Nuclear Information System (INIS)

Herzog, J.

1981-11-01

Machine for compacting solid residues, particularly bulky radioactive residues, constituted of a horizontally actuated punch and a fixed compression anvil, in which the residues are first compacted horizontally and then vertically. Its salient characteristic is that the punch and the compression anvil have embossments on the compression side and interpenetrating plates in the compression position [fr

Recycling crop residues for use in recirculating hydroponic crop production

Science.gov (United States)

Mackowiak, C. L.; Garland, J. L.; Sager, J. C.

1996-01-01

As part of bioregenerative life support feasibility testing by NASA, crop residues are being used to resupply elemental nutrients to recirculating hydroponic crop production systems. Methods for recovering nutrients from crop residues have evolved from water soaking (leaching) to rapid aerobic bioreactor processing. Leaching residues recovered the majority of elements but it also recovered significant amounts of soluble organics. The high organic content of leachates was detrimental to plant growth. Aerobic bioreactor processing reduced the organic content ten-fold, which reduced or eliminated phytotoxic effects. Wheat and potato production studies were successful using effluents from reactors having with 8- to 1-day retention times. Aerobic bioreactor effluents supplied at least half of the crops elemental mass needs in these studies. Descriptions of leachate and effluent mineral content, biomass productivity, microbial activity, and nutrient budgets for potato and wheat are presented.

Latest developments at GANIL for stable and radioactive ion beam production

International Nuclear Information System (INIS)

Jardin, P.; Barue, C.; Bajeat, O.; Canet, C.; Clement, E.; Cornell, J. C.; Delahaye, P.; Dubois, M.; Dupuis, M.; Flambard, J. L.; Fraanberg, H.; Frigot, R.; Leboucher, C.; Lecesne, N.; Lecomte, P.; Leherissier, P.; Lemagnen, F.; Leroy, R.; Maunoury, L.; Mery, A.

2010-01-01

In the frame of the SPIRAL II (Systeme de Production d'Ions Radioactifs Acceleres en Ligne Partie II) project, several developments of stable and radioactive ion production systems have been started up. In parallel, GANIL has the ambition to preserve the existing stable and radioactive beams and also to increase its range by offering new ones. In order to identify the best directions for this development, a new group called GANISOL has been formed. Its preliminary conclusions and the latest developments at GANIL are presented.

Determination of radioactivity in petroleum products and wastes

International Nuclear Information System (INIS)

Hrichi, Hajer

2009-01-01

At this end engineering study, we determined the activities of gamma- emitting radionuclides belonging to the families of 238 U, 235 U, 232 Th and 40K in the petroleum products and wastes of the refinery S.T.I.R. The activities of radionuclides which exceed that of crude oil prove that it's a technologically enhanced natural radioactivity since several chemical products were injected during the refining process. (Author)

Utilization of corn residues for production of the polysaccharide schizophyllan

Science.gov (United States)

Abundant corn residues include fiber from wet milling operations and distillers' dried grains from dry grind ethanol plants. Biorefineries of the future will utilize such residues for the production of valuable bioproducts, particularly those traditionally produced from fossil fuels. Schizophyllan...

Bioconversion of sago residue into value added products | Awg ...

African Journals Online (AJOL)

... value added products. DS Awg-Adeni, S Abd-Aziz, K Bujang, MA Hassan ... sago processing mills. This review focuses on the developments in processes and products for the value addition of sago residues through biotechnological means.

A radioactive controversy

International Nuclear Information System (INIS)

Engler, Veronica

2002-01-01

During 2002, the National Congress of Argentina began discussing the 'Agreement between the Republic of Argentina and Australia on cooperation in the peaceful uses of the nuclear energy'. This document has revived the debate regarding development of a national nuclear industry. The debate was spurred by a commercial contract signed in 2000 by INVAP, an Argentinean company who sold a nuclear reactor to the ANSTO, Australian Nuclear and Technology Organization. More than sixty non-governmental organizations are opposed to the ratification of the agreement, because they interpret that the text leaves the door wide open for the transport and deposit of Australian nuclear waste to Argentina, to be processed in national territory. Article 41 of the Argentinean National Constitution, explicitly prohibits the generation of any income from 'radioactive residues'. Those who support the agreement say that it does not promote the deposit of nuclear waste in Argentina, and argue that environmentalists are hampering efforts of this advanced technological industry to flourish in Argentina. The point of conflict in the agreement lies in article 12, which states that Argentina will continue the process of reactor-driven irradiated fuel outside Argentina. Once the treatment is completed, the fuel conditioned and the resulting waste must return to the country of origin for their storage. The possibility of spent fuel being sent to Argentina lies in the hypothetical case that the French company Cogema, which currently holds treatment responsibility, stops treatment sometime within the next fifteen years, when the fuel must be treated. The non-ratification of the agreement on Argentina part will not imply any sort of impediment in the realization of the reactor, it will only put on hold the possibility that the Australians spent fuels will complete treatment in Argentina. The constitutionality of the agreement lies in the question of waste, but this too is not a simple question. The

Natural radioactivity product from coal burning in PLTU Pacitan

International Nuclear Information System (INIS)

Sukirno; Sri Murniasih; Rosidi; Sutanto WW

2016-01-01

Monitoring of radioactivity in the coal-fired power plant has been carried out in the CAST-NAA laboratory at 2015. Monitoring includes analysis of soil, water, fly ash, bottom ash and coal. The basic purpose of this work is the investigation of natural radionuclide contents in coal and the actual product samples in the Pacitan power plant as a first step to estimate the radioactive in the vicinity. This paper presents the results of the analysis of radioactivity in samples of coal, fly ash and bottom ash as well as environment samples of soil and water. Ra-226, Th-232, K-40, U-235, U-238, and Pb-210 Natural radionuclides are determined by gamma spectrometry with HPGe detector. Natural radionuclide in fine grain coal, bottom ash and fly ash have concentrations range (162.182 to 0.057) Bq/kg. Radioactivity contained in soil ranges (0.041 to 169.34) Bq/kg, whereas in water ranges (0.003 to 0.045) Bq/L. According Perka BAPETEN. No. 7 of 2013. On Boundary Value Environmental Radioactivity, the results of measurement analysis contained water around the power plant Pacitan still below the limit values allowed by BAPETEN. (author)

Development of treatment method for stillage residues of liquid radioactive wastes to remove organic substances and transuranium elements

International Nuclear Information System (INIS)

Rudenko, L.I.; Dzhuzha, O.V.; Khan, V.E.

2008-01-01

The paper presents the results of the study into the laws that govern the process of treating by oxidation the stillage residues of liquid radioactive wastes to remove organic compounds and transuranium elements with the use of hydrogen peroxide, potassium permanganate and subsequent ultra-filtration. The optimum oxidisation regime has been defined on the basis of this study to ensure that the initial dichromate oxidability of LRW's stillage residues decreases from 6,000-9,500 to 500-1,000 mg O/I, whereas the TUE activity associated with the key isotopes is reduced by 74-87 % for 238,239,240 Pu, by 94-95 % for 241 Am, and by 90-95 % for 244 Cm. The concentration of uranium decreases by 94-99 %. It is proposed to implement this method at the Chernobyl NPP site.

Experimental and theoretical study of the residual nuclide production in 40-2600 MeV proton-irradiated thin targets of ads structure materials

International Nuclear Information System (INIS)

Titarenko, Yu.E.; Batyaev, V.F.; Belonozhenko, A.A.; Borovlev, S.P.; Butko, M.A.; Florya, S.N.; Pavlov, K.V.; Rogov, V.I.; Tikhonov, R.S.; Titarenko, A.Yu.; Zhivun, V.M.

2011-10-01

The Project is aimed at experimental and theoretical studying the independent and cumulative yields of residual radioactive nuclei produced in high-energy proton-irradiated structure materials intended for constructing the high-power Accelerator-Driven Systems (ADS) with a high-current proton accelerator. The Project is an extension of the researches carried out earlier under the ISTC Projects #017, #839, and #2002 which provided more 10000 residual nuclide production cross sections mainly in materials intended to use as target materials of the ADS. This Project includes 57 measurement runs carried out using the 97 targets made only of the ADS structural materials of both monoisotopic ( 56 Fe, 93 Nb, 181 Ta) and natural ( nat Cr, nat Ni, nat W) compositions within minutely fractionated proton energy range, namely, at 0.04, 0.07, 0.1, 0.15, 0.25, 0.4, 0.6, 0.8, 1.2, 1.6 and 2.6GeV. All the targets were irradiated using the ITEP U-10 proton synchrotron. The experimental nuclide yields are determined by the direct γ-spectrometry and α-spectrometry methods. As a result, 3839 cumulative and independent yields of residual β-radioactive product nuclei with lifetimes range from 6 minutes to 10 years as well as 12 cumulative yields of α- radioactive 148 Gd whose lifetime is 74.6 years have been measured. Besides, the cross sections for the 27 Al(p,x) 22 Na , 27 Al(p,x) 24 Na and 27 Al(p,x) 7 Be monitor reactions have been measured at the same proton energies with the use of the current transformer technique. The γ-spectrometer resolution is 1.8 keV in the 1332 keV 60 Co γ-line. The experimental γ-spectra were processed by the GENIE2000 code. The γ-lines were identified, and the cross sections calculated, by the ITEP-developed SIGMA code using the PCNUDAT database. The proton fluence was monitored by the 27 Al(p,x) 22 Na reaction. Measurement data have been compared with the calculation results of the BERTINI and ISABEL models of MCNPX code, CEM03.02, INCL 4.2, INCL4

Bioethanol production from forestry residues: A comparative techno-economic analysis

International Nuclear Information System (INIS)

Frankó, Balázs; Galbe, Mats; Wallberg, Ola

2016-01-01

Highlights: • A proposed cellulosic ethanol biorefinery in Sweden was simulated with Aspen Plus. • Forestry residues with different bark contents were evaluated as raw materials. • The bark content negatively influenced the minimum ethanol selling price. • Sensitivity analyses were performed to assess the influence of raw material cost. - Abstract: A techno-economic analysis was conducted to assess the feasibility of using forestry residues with different bark contents for bioethanol production. A proposed cellulosic ethanol biorefinery in Sweden was simulated with Aspen Plus. The plant was assumed to convert different forestry assortments (sawdust and shavings, fuel logs, early thinnings, tops and branches, hog fuel and pulpwood) to ethanol, pellets, biogas and electricity. The intention was not to obtain absolute ethanol production costs for future facilities, but to assess and compare the future potential of utilizing different forestry residues for bioethanol production. The same plant design and operating conditions were assumed in all cases, and the effect of including bark on the whole conversion process, especially how it influenced the ethanol production cost, was studied. While the energy efficiency (not including district heating) obtained for the whole process was between 67 and 69% regardless of the raw material used, the ethanol production cost differed considerably; the minimum ethanol selling price ranging from 0.77 to 1.52 USD/L. Under the basic assumptions, all the forestry residues apart from sawdust and shavings exhibited a negative net present value at current market prices. The profitability decreased with increasing bark content of the raw material. Sensitivity analyses showed that, at current market prices, the utilization of bark-containing forestry residues will not provide significant cost improvement compared with pulpwood unless the conversion of cellulose and hemicellulose to monomeric sugars is improved.

Waste processing system for product contaminated with radioactivity

International Nuclear Information System (INIS)

Sotoyama, Koichi; Takaya, Jun-ichi; Takahashi, Suehiro.

1987-01-01

Purpose: To enable to processing contaminated products while separating them into metals at high contamination level and non-metals at low contamination level. Constitution: Pulverized radioactive wastes conveyed on a conveyor belt are uniformly irradiated by a ring-illumination device and then they are picked-up by a television camera or the like. The picked-up signals are sent to an image processing device, applied with appropriate binarization and metal objects are separated by utilizing the light absorbing property of non-metal and light reflection property of metals. The graviational center for the metal object is calculated from the binarized image, the positional information is provided to a robot controller and the metal object is transferred to another position by a robot. Since only the metal object at high radioactive contamination level can be taken out separately, it is no more necessary to process the entire wastes as the high level decontamination products, to thereby provide an economical advantage. (Sekiya, K.)

Development of a purification technology for treatment of medium- and low-activity radioactive waste of radiochemical production from Co-60 and Cs-137

Directory of Open Access Journals (Sweden)

Apalkov Gleb

2016-01-01

Full Text Available The technological flowchart of purification of medium- and low-activity waste from Co-60 and Cs-137 is developed and introduced. The developed purification scheme has been successfully tested using genuine medium- and low-level liquid radioactive waste of radiochemical production containing complexing and colloid forming components complexons, surfactants. The optimal conditions of the presented method of purification ensure reduction of the residual specific activity of 60Co and 137Cs radionuclides in the solution to less than 0,9 Bq per litre.

Derivation of guidelines for uranium residual radioactive material in soil at the B ampersand T Metals Company site, Columbus, Ohio

International Nuclear Information System (INIS)

Kamboj, S.; Nimmagadda, Mm.; Yu, C.

1996-01-01

Guidelines for uranium residual radioactive material in soil were derived for the B ampersand T Metals Company site in Columbus, Ohio. This site has been identified for remedial action under the US Department of Energy's (DOE's) Formerly Utilized Sites Remedial Action Program (FUSRAP). Single-nuclide and total-uranium guidelines were derived on the basis of the requirement that following remedial action, the 50-year committed effective dose equivalent to a hypothetical individual living or working in the immediate vicinity of the site should not exceed a dose constraint of 30 mrem/yr for the current use and likely future use scenarios or a dose limit of 100 n-mrem/yr for less likely future use scenarios. The DOE residual radioactive material guideline computer code, RESRAD, was used in this evaluation. RESRAD implements the methodology described in the DOE manual for establishing residual radioactive material guidelines. Three scenarios were considered; each assumed that for a period of 1,000 years following remedial action, the site would be used without radiological restrictions. The three scenarios varied with regard to the type of site use, time spent at the site by the exposed individual, and sources of food and water consumed. The evaluations indicate that the dose constraint of 30 mrem/yr would not be exceeded for uranium (including uranium-234, uranium-235, and uranium-238) within 1,000 years, provided that the soil concentration of total uranium (uranium-234, uranium-235, and uranium-238) at the B ampersand T Metals site did not exceed 1, I 00 pCi/g for Scenario A (industrial worker, current use) or 300 pCi/g for Scenario B (resident with municipal water supply, a likely future use). The dose limit of 100 mrem/yr would not be exceeded at the site if the total uranium concentration of the soil did not exceed 880 pCi/g for Scenario C (resident with an on-site water well, a plausible but unlikely future use)

Radioactive waste containment

International Nuclear Information System (INIS)

Beranger, J.-C.

1978-01-01

The problem of confining the radioactive wastes produced from the nuclear industry, after the ore concentration stage, is envisaged. These residues being not released into the environment are to be stored. The management policy consists in classifying them in view of adapting to each type of treatment, the suitable conditioning and storage. This classification is made with taking account of the following data: radioactivity (weak, medium or high) nature and lifetime of this radioactivity (transuranians) physical nature and volume. The principles retained are those of volume reduction and shaping into insoluble solids (vitrification) [fr

Residual Isocyanates in Medical Devices and Products: A Qualitative and Quantitative Assessment

Directory of Open Access Journals (Sweden)

Gillian Franklin

2016-01-01

Full Text Available We conducted a pilot qualitative and quantitative assessment of residual isocyanates and their potential initial exposures in neonates, as little is known about their contact effect. After a neonatal intensive care unit (NICU stockroom inventory, polyurethane (PU and PU foam (PUF devices and products were qualitatively evaluated for residual isocyanates using Surface SWYPE ™ . Those containing isocyanates were quantitatively tested for methylene diphenyl diisocyanate (MDI species, using UPLC-UV-MS/MS method. Ten of 37 products and devices tested, indicated both free and bound residual surface isocyanates; PU/PUF pieces contained aromatic isocyanates; one product contained aliphatic isocyanates. Overall, quantified mean MDI concentrations were low (4,4‘-MDI = 0.52 to 140.1 pg/mg and (2,4‘-MDI = 0.01 to 4.48 pg/mg. The 4,4‘-MDI species had the highest measured concentration (280 pg/mg. Commonly used medical devices/products contain low, but measurable concentrations of residual isocyanates. Quantifying other isocyanate species and neonatal skin exposure to isocyanates from these devices and products requires further investigation.

Fuel gas production from animal and agricultural residues and biomass

Energy Technology Data Exchange (ETDEWEB)

Wise, D. L; Wentworth, R. L

1978-05-30

Progress was reported by all contractors. Topics presented include: solid waste to methane gas; pipeline fuel gas from an environmental cattle feed lot; heat treatment of organics for increasing anaerobic biodegradability; promoting faster anaerobic digestion; permselective membrane control of algae and wood digesters for increased production and chemicals recovery; anaerobic fermentation of agricultural residues; pilot plant demonstration of an anaerobic, fixed-film bioreactor for wastewater treatment; enhancement of methane production in the anaerobic diegestion of sewage; evaluation of agitation concepts for biogasification of sewage sludge; operation of a 50,000 gallon anaerobic digester; biological conversion of biomass to methane; dirt feedlot residue experiments; anaerobic fermentation of livestock and crop residues; current research on methanogenesis in Europe; and summary of EPA programs in digestion technology. (DC)

Distribution of natural occurring radionuclide in some industral residues used in new type wall materials

International Nuclear Information System (INIS)

Chen Yingmin; Li Fusheng; Xu Jiaang; Deng Daping; Yuan Ming; Ma Shi; Chen Yue

2006-01-01

Objective: To study the natural radioactive nuclide distribution characteristic of fly ash, gangue and various kinds of slag used in the new-type wall material and offer scientific basis for reducing the radiation dosage that the public suffers. Methods: The activity concentrations of the contents of natural radioactive nuclides of different industral waste residues have been determined by HPGe gamma-ray spectrometry. Results: The mean Raeq is successively fly ash (279.13 Bq kg -1 ), slag (225.69 Bq kg -1 ), gangue (141.26 Bq kg -1 ) from high to low and all of the samples is lower than the limit set in the OECD. The arithmetic mean activities of 236 Ra, 232 Th, 40 K in fly-ash samples are 127.88, 93.83, 221.75 Bq kg -1 ; for coal slag samples are 73.89, 97.13, 283.44 Bq kg -1 and for coal gangue samples are 47.85, 45.21, 413.56 Bq kg -1 . For the same power plant, the radioactive nuclide activity of the fly ash gathered in different time may have very great differences, the maximum can reach more than 2 times of the minimum. Conclusion: the fly ash and slag should be controlled strictly on rational proportion, which should not exceed 70% of the total mass. The mixing of the average radioactive level of the gangue is nearly equal that of to clay, it can be unrestricted in the mixing proportion in process of production. The manufacturer of new-type wall materials should often measure the radioactive level of the industrial waste residue in production. Make the content of radioactive nuclide in the products reach the rational level as low as possible. (authors)

From the HINDAS Project: Excitation Functions for Residual Nuclide Production by Proton-Induced Reactions

International Nuclear Information System (INIS)

Michel, R.; Gloris, M.; Protoschill, J.; Uosif, M.A.M.; Weug, M.; Herpers, U.; Kuhnhenn, J.; Kubik, P.-W.; Schumann, D.; Synal, H.-A.; Weinreich, R.; Leya, I.; David, J.C.; Leray, S.; Duijvestijn, M.; Koning, A.; Kelic, A.; Schmidt, K.H.; Cugnon, J.

2005-01-01

A survey is given about efforts undertaken during the HINDAS project to investigate the energy dependence of residual nuclide production by proton-induced reactions from thresholds up to 2.6 GeV. For proton-induced reactions, our experiments aimed to further develop and complete the cross-section database that was established by our collaboration in recent years. It was extended to the heavy-target elements Ta, W, Pb, and Bi for energies up to 2.6 GeV. In addition, new measurements for the target element iron were performed up to 2.6 GeV and for natural uranium for energies from 21 MeV to 69 MeV. For the target element lead, a comprehensive set of excitation functions published recently was completed by AMS-measurements of cross sections for the production of the long-lived radionuclides Be-10, Al-26, Cl-36, and I-129 and by mass spectrometric measurements for stable and radioactive rare gas isotopes of He, Ne, Ar, Kr, and Xe. Comprehensive tests of the nuclear-reaction codes TALYS and INCL4+ABLA, which were developed within the HINDAS project, were performed with the new experimental results over the entire energy range

Development of high-level radioactive waste treatment and conversion technologies 'Dry decontamination technology development for highly radioactive contaminants'

International Nuclear Information System (INIS)

Oh, Won Zin; Lee, K. W.; Won, H. J.; Jung, C. J.; Choi, W. K.; Kim, G. N.; Moon, J. K.

2001-04-01

The followings were studied through the project entitled 'Dry Decontamination Technology Development for Highly Radioactive Contaminants'. 1.Contaminant Characteristics Analysis of Domestic Nuclear Fuel Cycle Projects(NFCP) and Applicability Study of the Unit Dry-Decontamination Techniques A. Classification of contaminated equipments and characteristics analysis of contaminants B. Applicability study of the unit dry-decontamination techniques 2.Performance Evaluation of Unit Dry Decontamination Technique A. PFC decontamination technique B. CO2 decontamination technique C. Plasma decontamination technique 3.Development of Residual Radiation Assessment Methodology for High Radioactive Facility Decontamination A. Development of radioactive nuclide diffusion model on highly radioactive facility structure B. Obtainment of the procedure for assessment of residual radiation dose 4.Establishment of the Design Concept of Dry Decontamination Process Equipment Applicable to Highly Radioactive Contaminants 5.TRIGA soil unit decontamination technology development A. Development of soil washing and flushing technologies B. Development of electrokinetic soil decontamination technology

Sealed radioactive sources and method of their production

International Nuclear Information System (INIS)

Benadik, A.; Tympl, M.; Stopek, K.

1985-01-01

The active layer of the proposed sources consists of an inorganic sorbent activated with a radioactive component in form of gel, xerogel or glass. The active particles of the inorganic sorbent have the shape of spheres 2 to 2000 μm in diameter. The sources have a tubular, cylindrical or needle shape and are compact with low leachability. They feature minimal radionuclide leakage, they are reliable and safe. Their production technology is proposed. The inorganic sorbent is put in contact with the sollution of the radioactive compound, then separated from the liquid phase, filled into containers, dried, calcined or sintered or otherwise heat-processed into glass at temperatures of 250 -1800 degC. (M.D.)

Radioactive waste management and disposal

International Nuclear Information System (INIS)

Simon, R.; Orlowski, S.

1980-01-01

The first European Community conference on Radioactive Waste Management and Disposal was held in Luxembourg, where twenty-five papers were presented by scientists involved in European Community contract studies and by members of the Commission's scientific staff. The following topics were covered: treatment and conditioning technology of solid intermediate level wastes, alpha-contaminated combustible wastes, gaseous wastes, hulls and dissolver residues and plutonium recovery; waste product evaluation which involves testing of solidified high level wastes and other waste products; engineering storage of vitrified high level wastes and gas storage; and geological disposal in salt, granite and clay formations which includes site characterization, conceptual repository design, waste/formation interactions, migration of radionuclides, safety analysis, mathematical modelling and risk assessment

Production of adsorbent from palm shell for radioactive iodine scrubbing process

International Nuclear Information System (INIS)

Mohamad Azman Che Mat Isa; Ku Halim Ku Hamid; Muhd Noor Muhd Yunus; Mohamad Puad Abu; Abdul Halim Badaruddin; Mohammad Nizammudin Abd Aziz; Muhd Ridwan Abdul Rahim

2010-01-01

The biggest biomass source in Malaysia comes from oil palm industry. According to the statistic of year 2004, Malaysia produced 40 million tones per year of biomass which 30 million tones of biomass originated from the oil palm industries. Therefore, the biomass waste such as palm kernel shell can be used to produce granular adsorbent for radioactive materials. For that reason, a newly system, called Rocking Kiln - Fluidized Bed (RK - FB) was developed to utilize large amount of the biomass to produce high value added product. Charcoal or chemically produced activated carbon could be produced by using the kiln. Washing process was introduced to remove particles, minerals and volatile matters from charcoal produced and then would create more surface area in the adsorbent by creating more active sites. In this research, the adsorbent produced was used to scrub iodine 131. In nuclear power reactor, iodine isotope 131 is produced during nuclear fission, and this elementary radioactive iodine may pollute exhaust air streams that could cause thyroid cancer. For removal of radioactive iodine, normally a potassium iodide - impregnated activated carbon (KI - AC) is used. Thus, a process will be developed to produce KI - AC and this product will be used to calculate the efficiency to remove the radioactive iodine 131.The results obtain show that adsorbent produced has a high potential to be used in radioactive adsorbing and likely more economics. This paper will elaborate further the experimental set-up of in Kiln - Fluidized Bed (RK - FB), adsorbent quality and radioactive scrubbing process. (author)

Evaluation of radiation exposure from shoe-deodorants as radioactive consumer products

International Nuclear Information System (INIS)

Furuta, Etsuko; Yokota, Shigeaki; Aburai, Tamaru; Yoshizawa, Yukio

2007-01-01

Six shoe-deodorants on the market were analyzed using gamma-ray spectroscopy and radionuclide imaging techniques. The results reveal that at least three deodorants were 'radioactive consumer products' containing radionuclides of thorium (Th) series, uranium series, and potassium-40 that were added intentionally. Equivalent dose rates and effective dose rates were calculated using the activities in these deodorants. There were no samples breaking the nuclear reactor and fuel regulation law. Radioactive concentration of the deodorant for a shoe-shelf is higher than other deodorants, and the total concentrations of daughter nuclides of Th which are radioactive equilibrium with 224 Ra exceeded 90 Bq·g -1 . The effective dose rate at one meter from the shoe-shelf-deodorant is 8.6x10 -4 μSv·h -1 . Another type of shoe-deodorants is an insole that causes the surface dose of plantar skin. The equivalent dose was calculated as 1.9 μSv·h -1 at one millimeter from the insole. This study suggested that it needs to watch severely over the deodorants because many kinds of deodorants are used in home and some deodorants are radioactive consumer products. (author)

Radioactivity and deep geothermal energy; Radioaktivitaet und tiefe Geothermie

Energy Technology Data Exchange (ETDEWEB)

Janczik, Sebastian; Kaltschmitt, Martin [Technische Univ. Hamburg-Harburg (Germany). Inst. fuer Umwelttechnik und Energiewirtschaft; Merkel, Broder [Technische Univ. Bergakademie Freiberg (Germany). Inst. fuer Geologie

2012-02-15

Due to recent developments in energy politics renewable energies get more and more importance in Germany. This is especially true for geothermal energy representing a promising option for the environmentally sound and secure generation of heat and electricity. But there are a lot of very emotional discussions due to radioactive residues and wastes produced by a geothermal plant. Thus this paper compares radioactivity resulting from geothermal energy with radioactivity coming from other natural sources. In doing so it becomes obvious that naturally radioactive sources exist in all parts of the ecosphere (i.e. air, water, soil). The paper shows also that the specific activities of radioactive elements from geothermal energy in form of residues and waste emerge from radioactive decay of nuclides and that their radiation is not higher than the radiation of other naturally occurring radioactive elements. (orig.)

Vitrification of high-level radioactive and hazardous wastes

International Nuclear Information System (INIS)

Lutze, W.

1993-12-01

The main objective is to summarize work conducted on glasses as waste forms for high-level radioactive fission product solutions up to the late 1980's (section I and II). Section III addresses the question, whether waste forms designed for the immobilization of radioactive residues can be used for the same purpose for hazardous wastes. Of particular interest are those types of hazardous wastes, e.g., fly ashes from municipal combustion plants, easy to convert into glasses or ceramic materials. A large number of base glass compositions has been studied to vitrify waste from reprocessing but only borosilicate glasses with melting temperatures between 1100 C and 1200 C and very good hydrolytic stability is used today. (orig./HP) [de

Isotopic yields and kinetic energies of primary residues in 1 A GeV 208Pb + p reactions

International Nuclear Information System (INIS)

Enqvist, T.; Wlazlo, W.; Armbruster, P.

2000-09-01

The production of primary residual nuclei in the reaction 1 A GeV 208 Pb on proton has been studied by measuring isotopic distributions for all elements from titanium (Z=22) to lead (Z=82). Kinematical properties of the residues were also determined and used to disentangle the relevant reaction mechanisms, spallation (projectile fragmentation) and fission. The fragment separator FRS at GSI, Darmstadt, was used to separate and identify the reaction products. The measured production cross sections are highly relevant for the design of accelerator-driven subcritical reactors and for the planning of future radioactive-beam facilities. (orig.)

Application of industrial wood residues for combined heat and power production

International Nuclear Information System (INIS)

Majchrzycka, A.

2015-01-01

The paper discusses combined production of heat and power (CHP) from industrial wood residues. The system will be powered by wood residues generated during manufacturing process of wooden floor panels. Based on power and heat demands of the plant and wood residues potential, the CHP system was selected. Preliminary analysis of biomass conversion in CHP system and environmental impact was performed.

Targets for production of high-intensity radioactive ion-beams

International Nuclear Information System (INIS)

Hagebo, E.; Hoff, P.; Steffensen, K.

1991-01-01

The recent developments of target systems for production of high intensity radioactive ion-beams at the ISOLDE mass separators is described. Methods for chemically selective production through separation of molecular ions are outlined and the effects of the addition of reactive gases has been studied. Results and further possible applications in the light element region are discussed. (author) 10 refs.; 9 figs.; 1 tab

Nuclear reactor structural material forming less radioactive corrosion product

International Nuclear Information System (INIS)

Nakazawa, Hiroshi.

1988-01-01

Purpose: To provide nuclear reactor structural materials forming less radioactive corrosion products. Constitution: Ni-based alloys such as inconel alloy 718, 600 or inconel alloy 750 and 690 having excellent corrosion resistance and mechanical property even in coolants at high temperature and high pressure have generally been used as nuclear reactor structural materials. However, even such materials yield corrosion products being attacked by coolants circulating in the nuclear reactor, which produce by neutron irradiation radioactive corrosion products, that are deposited in primary circuit pipeways to constitute exposure sources. The present invention dissolves dissolves this problems by providing less activating nuclear reactor structural materials. That is, taking notice on the fact that Ni-58 contained generally by 68 % in Ni changes into Co-58 under irradiation of neutron thereby causing activation, the surface of nuclear reactor structural materials is applied with Ni plating by using Ni with a reduced content of Ni-58 isotopes. Accordingly, increase in the radiation level of the nuclear reactor structural materials can be inhibited. (K.M.)

Study on technology for radioactive waste treatment and management from uranium production

International Nuclear Information System (INIS)

Vu Hung Trieu; Vu Thanh Quang; Nguyen Duc Thanh; Trinh Giang Huong; Tran Van Hoa; Hoang Minh Chau; Ngo Van Tuyen; Nguyen Hoang Lan; Vuong Huu Anh

2007-01-01

There is some solid and liquid radioactive waste created during producing Uranium that needs being treated and managed to keep our environment safe. This radioactive waste contains Uranium (U-238), Thorium (Th-232), Radium (Ra-226) and some heavy metals and mainly is low radioactive waste. Our project has researched and built up appropriate technology for treating and managing the radioactive waste. After researching and experimenting, we have built up four technology processes as follows: Technology for separating Radium from liquid waste; Technology for treating and managing solid waste containing Ra; Technology for separating Thorium from liquid waste after recovering radium; Technology for stabilizing solid waste from Uranium production. (author)

Protection against radioactive contamination of foods and agricultural products

International Nuclear Information System (INIS)

Szabo, A.; Kovacs, Z.

1977-01-01

Methods suitable for diminishing radioactive contamination of foods and agricultural products and reducing at the same time the irradiation hazards for the human organism are dealt with. The possibilities for the decontamination of foods vegetal and of animal origin are discussed separately. (author)

Techno-economic evaluation of residue exhaustion in batch rectification ethanol production plant

Directory of Open Access Journals (Sweden)

Jaćimović Branislav M.

2017-01-01

Full Text Available This paper presents the techno-economic optimization of batch plant for production of rectified alcohol based on the concentration of ethanol in residue. The aim of the analysis was to determine the extent to which it is economically profitable to exhaust the residual liquid in boiler. The "profit production" criterion is used for calculations.

Evaluation of the increasing of radioactive wastes production at the Instituto de Energia Atomica, Brazil

International Nuclear Information System (INIS)

Sawakuchi, R.S.; Sordi, G.A.A.

1976-01-01

This evaluation has the purpose of selecting a new method for radioactive waste disposal at the IEA (Brazil). A production growth pattern for radioactive waste was established. The growth of radioactive wastes produced at the IEA was estimated for the next ten years

Radioactive Waste Management Produced from the Generator Tc-99m Products

International Nuclear Information System (INIS)

Suhaedi Muhammad; Rimin Sumantri; Affan Ahmad; Tuyono

2012-01-01

Generator Tc-99m product is used in hospitals will result in radioactive waste both solid waste in the form of a column compacted Tc-99m Generator, bottles vials and bottles of saline fluid path series: burning of solid waste in the form of paper straw, hand gloves, and cardboard (vial packing boxes and wrapping Generator) and liquid waste form leaching results lead pot and enclosure. So that these wastes pose no radiological consequences for both humans and the environment, it must be properly managed in accordance with the provisions. In order to realize these expectations should be made so that the radioactive waste management system can be handled effectively, optimal, economical, safe and secure and in accordance with applicable regulations. Management system is in it include: procedures for handling radioactive waste, solid waste compacted, burning of solid waste management, liquid waste handling, shipment of radioactive waste and determination of the amount of radiation doses received by workers who handle radioactive waste. (author)

New substrate containing agroindustrial carnauba residue for production of papaya under foliar fertilization

Directory of Open Access Journals (Sweden)

Francisca G. Albano

Full Text Available ABSTRACT The use of organic waste in the composition of substrates for seedlings constitutes an alternative to the recycling of these materials. Thus, an experiment was conducted with the objective to evaluate the production of ‘Formosa’ papaya seedlings in substrate containing carnauba wax residue, under foliar fertilization. The experimental design was completely randomized with five replicates, with treatments distributed in a 5 x 2 factorial scheme, corresponding to five materials used as substrates, in the presence and absence of foliar fertilization. The materials used were: earthworm humus, carnauba residue + fresh rice husk; carnauba residue in powder; carnauba residue semi-decomposed and mixture of carnauba residues: carnauba residue + fresh rice husk + carnauba residue semi-decomposed + carnauba residue in powder, at the proportion 1:1:1. The agroindustrial residue of carnauba wax semi-decomposed can be used as substrates in the production of ‘Formosa’ papaya seedlings. The foliar fertilization increases the quality of papaya seedlings, leading to increment in leaf area, root volume and sulfur content in the leaves, thus becoming a necessary practice.

Symposium: Treatment of radioactive residues at Hauptabteilung Dekontaminationsbetriebe (HDB)

International Nuclear Information System (INIS)

Pfeifer, W.

1994-05-01

The twelve seminar papers compiled in the KfK report deal with the current state of the art and the technology available in Germany for the management of radioactive liquid and solid wastes, and radioactive scrap. Some papers discuss particular technical aspects of techniques such as solidification, volume reduction, and compaction. The function of the Waste Collecting Centres of the Laender is explained. (HP) [de

Transmutation of radioactive wastes: how and why?

International Nuclear Information System (INIS)

Patarin, L.

2004-01-01

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

Treatment methods and comparative risks of thorium removal from waste residues

International Nuclear Information System (INIS)

Porter, R.D.; Hamby, D.M.; Martin, J.E.

1997-07-01

This study was done to examine the risks of remediation and the effectiveness of removal methods for thorium and its associated radioactive decay products from various soils and wastes associated with DOE's Formerly Utilized Sites Remedial Action Program (FUSRAP). Removal of 230 Th from uranium process residues would significantly reduce the buildup of 226 Ra (half-life of 1600 years), and since 230 Th concentrations at most of the important sites greatly exceed the 226 Ra concentrations, such removal would reduce the accumulation of additional radiation risks associated with 226 Ra and its products; and, if treatment also removed 226 Ra, these risks could be mitigated even further. Removal of 232 Th from thorium process residues would remove the source material for 228 Ra, and since 228 Ra has a half-life of 5.76 years, its control at FUSRAP sites could be done with land use controls for the 30--50 years required for 228 Ra and the risks associated with its decay products to decay away. It must be recognized, however, that treatment methods invariably require workers to process residues and waste materials usually with bulk handling techniques. These processes expose workers to the radioactivity in the materials, therefore, workers would incur radiological risks in addition to industrial accident risks. An important question is whether the potential reduction of future radiological risks to members of the public justifies the risks that are incurred by remediation workers due to handling materials. This study examines, first, the effectiveness of treatment and then the risks that would be associated with remediation

Derivation of strontium-90 and cesium-137 residual radioactive material guidelines for the Laboratory for Energy-Related Health Research, University of California, Davis

International Nuclear Information System (INIS)

Nimmagadda, M.; Yu, C.

1993-04-01

Residual radioactive material guidelines for strontium-90 and cesium-137 were derived for the Laboratory for Energy-Related Health Research (LEHR) site in Davis, California. The guideline derivation was based on a dose limit of 100 mrem/yr. The US Department of Energy (DOE) residual radioactive material guideline computer code, RESRAD, was used in this evaluation; this code implements the methodology described in the DOE manual for implementing residual radioactive material guidelines. Three potential site utilization scenarios were considered with the assumption that, for a period of 1,000 years following remedial action, the site will be utilized without radiological restrictions. The defined scenarios vary with regard to use of the site, time spent at the site, and sources of food consumed. The results of the evaluation indicate that the basic dose limit of 100 mrem/yr will not be exceeded within 1,000 years for either strontium-90 or cesium-137, provided that the soil concentrations of these radionuclides at the LEHR site do not exceed the following levels: 71,000 pCi/g for strontium-90 and 91 pCi/g for cesium-137 for Scenario A (researcher: the expected scenario); 160,000 pCi/g for strontium-90 and 220 pCi/g for cesium-137 for Scenario B (recreationist: a plausible scenario); and 37 pCi/g for strontium-90 and 32 pCi/g for cesium-137 for Scenario C (resident farmer ingesting food produced in the contaminated area: a plausible scenario). The derived guidelines are single-radionuclide guidelines and are linearly proportional to the dose limit used in the calculations. In setting the actual strontium-90 and cesium-137 guidelines for the LEHR site, DOE will apply the as low as reasonably achievable (ALARA) policy to the decision-making process, along with other factors such as whether a particular scenario is reasonable and appropriate

Control of Orphan Sources and Other Radioactive Material in the Metal Recycling and Production Industries. Specific Safety Guide

International Nuclear Information System (INIS)

2014-01-01

Accidents involving orphan sources and other radioactive material in the metal recycling and production industries have resulted in serious radiological accidents as … well as in harmful environmental, social and economic impacts. This Safety Guide provides recommendations, the implementation of which should prevent such accidents and provide confidence that scrap metal and recycled products are safe. Contents: 1. Introduction; 2. Protection of people and the environment; 3. Responsibilities; 4. Monitoring for radioactive material; 5. Response to the discovery of radioactive material; 6. Remediation of contaminated areas; 7. Management of recovered radioactive material; Annex I: Review of events involving radioactive material in the metal recycling and production industries; Annex II: Categorization of radioactive sources; Annex III: Some examples of national and international initiatives

Control of Orphan Sources and Other Radioactive Material in the Metal Recycling and Production Industries. Specific Safety Guide

International Nuclear Information System (INIS)

2012-01-01

Accidents involving orphan sources and other radioactive material in the metal recycling and production industries have resulted in serious radiological accidents as well as in harmful environmental, social and economic impacts. This Safety Guide provides recommendations, the implementation of which should prevent such accidents and provide confidence that scrap metal and recycled products are safe. Contents: 1. Introduction; 2. Protection of people and the environment; 3. Responsibilities; 4. Monitoring for radioactive material; 5. Response to the discovery of radioactive material; 6. Remediation of contaminated areas; 7. Management of recovered radioactive material; Annex I: Review of events involving radioactive material in the metal recycling and production industries; Annex II: Categorization of radioactive sources; Annex III: Some examples of national and international initiatives.

Investigation of the possibility of using hydrogranulation in reprocessing radioactive wastes of radiochemical production facilities

Energy Technology Data Exchange (ETDEWEB)

Revyakin, V.; Borisov, L.M. [All Russian Scientific and Research Institute of Non-Organic Materials, Moscow (Russian Federation)

1996-05-01

Radio-chemical production facilities are constantly accumulating liquid radioactive wastes (still residues as the result of evaporation of extraction and adsorption solutions etc.) which are a complex multicomponent mixtures. The wastes are frequently stored for extended periods of time while awaiting disposition and in some cases, and this is much worse, they are released into the environment. In this report, I would like to draw your attention to some results we have obtained from investigations aimed at simplifying handing of such wastes by the precipitation of hard to dissolve metal hydroxides, the flocculation of the above into granules with the help of surface-active agents (in this case a polyacrylamide - PAA), quickly precipitated and easily filtered. The precipitate may be quickly dried and calcinated, if necessary, and transformed into a dense oxide sinter. In other words it may be transformed into a material convenient for storage or burial.

Biogas production from energy crops and agriculture residues

Energy Technology Data Exchange (ETDEWEB)

Wang, G.

2010-12-15

In this thesis, the feasibility of utilizing energy crops (willow and miscanthus) and agriculture residues (wheat straw and corn stalker) in an anaerobic digestion process for biogas production was evaluated. Potential energy crops and agriculture residues were screened according to their suitability for biogas production. Moreover, pretreatment of these biomasses by using wet explosion method was studied and the effect of the wet explosion process was evaluated based on the increase of (a) sugar release and (b) methane potential when comparing the pretreated biomass and raw biomass. Ensiling of perennial crops was tested as a storage method and pretreatment method for enhancement of the biodegradability of the crops. The efficiency of the silage process was evaluated based on (a) the amount of biomass loss during storage and (b) the effect of the silage on methane potential. Co-digestion of raw and wet explosion pretreated energy crops and agriculture residues with swine manure at various volatile solids (VS) ratio between crop and manure was carried out by batch tests and continuous experiments. The efficiency of the co-digestion experiment was evaluated based on (a) the methane potential in term of ml CH4 produced per g of VS-added and (b) the amount of methane produced per m3 of reactor volume. (Author)

Biogas Production from Energy Crops and Agriculture Residues

DEFF Research Database (Denmark)

Wang, Guangtao

and wet explosion pretreated energy crops and agriculture residues with swine manure at various volatile solids (VS) ratio between crop and manure was carried out by batch tests and continuous experiments. The efficiency of the co-digestion experiment was evaluated based on (a) the methane potential......In this thesis, the feasibility of utilizing energy crops (willow and miscanthus) and agriculture residues (wheat straw and corn stalker) in an anaerobic digestion process for biogas production was evaluated. Potential energy crops and agriculture residues were screened according...... of perennial crops was tested as a storage method and pretreatment method for enhancement of the biodegradability of the crops. The efficiency of the silage process was evaluated based on (a) the amount of biomass loss during storage and (b) the effect of the silage on methane potential. Co-digestion of raw...

Development of high-level radioactive waste treatment and conversion technologies 'Dry decontamination technology development for highly radioactive contaminants'

Energy Technology Data Exchange (ETDEWEB)

Oh, Won Zin; Lee, K. W.; Won, H. J.; Jung, C. J.; Choi, W. K.; Kim, G. N.; Moon, J. K

2001-04-01

The followings were studied through the project entitled 'Dry Decontamination Technology Development for Highly Radioactive Contaminants'. 1.Contaminant Characteristics Analysis of Domestic Nuclear Fuel Cycle Projects(NFCP) and Applicability Study of the Unit Dry-Decontamination Techniques A. Classification of contaminated equipments and characteristics analysis of contaminants B. Applicability study of the unit dry-decontamination techniques 2.Performance Evaluation of Unit Dry Decontamination Technique A. PFC decontamination technique B. CO2 decontamination technique C. Plasma decontamination technique 3.Development of Residual Radiation Assessment Methodology for High Radioactive Facility Decontamination A. Development of radioactive nuclide diffusion model on highly radioactive facility structure B. Obtainment of the procedure for assessment of residual radiation dose 4.Establishment of the Design Concept of Dry Decontamination Process Equipment Applicable to Highly Radioactive Contaminants 5.TRIGA soil unit decontamination technology development A. Development of soil washing and flushing technologies B. Development of electrokinetic soil decontamination technology.

Regulatory and management approaches to NORM residues in Malaysia

International Nuclear Information System (INIS)

Omar, M.; Teng, I.L.

2006-01-01

Naturally Occurring Radioactive Material (NORM) processing industries in Malaysia include oil and gas production and mineral processing plants. These industries are controlled by the Atomic Energy Licensing Board of Malaysia (AELB) through the enforcement of the Atomic Energy Licensing Act 1984 (Act 304). Related regulations have been developed in order to ensure the safety of workers and members of the public. However, more regulations are necessary for the safe handling of NORM. NORM processing generates various types of NORM residues that require proper management. As for low-level NORM residues, landfill disposal can be exempted from regulatory control if the Radiological Impact Assessment (RIA) shows that the additional dose to the members of the public is below the limit set by the authority. This paper outlines the regulatory and management approaches to NORM residues in Malaysia. (author)

The role of research and development work on the production costs of logging residue chips

International Nuclear Information System (INIS)

Nousiainen, I.

1998-01-01

Purchase of logging residue chips in the early 80s was mainly based on production chains in which the residues were collected with load-carrying tractors at the road-side storage, from which it was chipped or crushed directly into the trailer of a waiting lorry. Six new production chains were developed in the national Bioenergy Research Programme. Three of these are now commercial. Kotimaiset Energiat Pekka Lahti Ky has developed, on the basis of a traditional logging residue production chain, a high-efficiency EVOLUTION intermediate storage chipper, suitable for chipping of logging residues. Oy Logset Ab has developed a new type of lot-chipping chip-harvester, the LOGSET 536C. Nested containers have also been developed for the lot-chipping method. MOHA multi-purpose chipper, in which the chipping and lorry-transportation of chips have been integrated, has also been developed as a part of the research programme. In addition to these, a chipper-container lorry combination, transportation of complete logging residues, and whole- tree skidding have been developed in the project for production of logging residue chips. In the beginning of the 80s the production costs of logging residues at the place of utilization were about 52 FIM/MWh, and the average transportation distance 50 km. In 1992 the production costs, 64 FIM/MWh at the distance of 100 km, was significantly higher than the price of alternative fuels. The lowest production cost level, obtainable by the developed methods is 46 FIM/MWh

Influence of radioactive contamination to agricultural products by rainfall during a nuclear accident

International Nuclear Information System (INIS)

Hwang, W. T.; Han, M. H.; Choi, Y. H.; Lee, H. S.; Lee, C. W.

2001-01-01

For the consideration of the effects on radioactive contamination of agricultural products by rainfall during a nuclear accident, the wet interception coefficients for the plants were derived, and the previous dynamic food chain model was also modified. From the results, radioactive contamination of agricultural products was greatly decreased by rainfall, and it decreased dramatically according to increase of rainfall amount. It means that the predictive contamination in agricultural products using the previous dynamic food chain model, in which dry interception to the plants is only considered, can be overestimated. Influence of rainfall on the contamination of agricultural products was the most sensitive for 131 I, and the least sensitive for 90 Sr

Laboratory study of the radioactivity from fission products in microscopic fallout particles

International Nuclear Information System (INIS)

Smith, H.A.; Ward, T.E.; Wesick, J.

1978-01-01

An experiment is described wherein simple γ-ray detection and analysis techniques were utilized to study the radioactivity in local precipitation. Gamma spectra from filtered particulate, evaporation residue, and water from a sample of freshly fallen snow were counted, and the relative amount of several radionuclides present were identified. These data show that several isotopes produced in the recent Chinese nuclear detonation (Lop Nor testing ground, Sinkiang Province, 17 November 1976) are observable. Furthermore the data are sufficient to estimate the date of the detonation and to determine some of the characteristics of the explosion

Deposition of naturally occurring radioactivity in oil and gas production

International Nuclear Information System (INIS)

Lysebo, I.; Strand, T.

1997-01-01

This booklet contains general information about naturally occurring radioactive materials, NORM, in production of oil and natural gas, occupational doses, radiation protection procedures and measures, and classification methods of contaminated equipment. 6 refs., 1 fig., 1 tab

Radioactive Ions Production Ring for Beta-Beams

CERN Document Server

Benedetto, E; Wehner, J

2010-01-01

Within the FP7 EUROnu program, Work Package 4 addresses the issues of production and acceleration of 8Li and 8B isotopes through the Beta-Beam complex, for the production of electron-neutrino. One of the major critical issues is the production of a high enougth ion ßux, to fulÞll the requirements for physics. In alternative to the direct ISOL production method, a new ap- proach is proposed in [1]. The idea is to use a compact ring for Litium ions at 25 MeV and an internal He or D target, in which the radioactive-isotopes production takes place. The beam is expected to survive for several thousands of turns, therefore cooling in 6D is required and, according this scheme, the ionization cooling provided by the target itself and a suitable RF system would be sufÞcient. We present some preliminary work on the Production ring lat- tice design and cooling issues, for the 7Li ions, and propose plans for future studies, within the EUROnu program.

Natural Radioactivity in Ceramic Materials

International Nuclear Information System (INIS)

Abu Khadra, S.A.; Kamel, N.H.

2005-01-01

Ceramics are one of the most important types of the industrial building materials. The raw materials of the ceramic are made of a mixture of clay, feldspar, silica, talc kaolin minerals together with zirconium silicates (ZrSiO4).The ceramic raw materials and the final products contain naturally occurring radionuclide mainly U-238 and, Th-232 series, and the radioactive isotope of potassium K-40. Six raw ceramic samples were obtained from the Aracemco Company at Egypt together with a floor tile sample (final product) for measuring radioactive concentration levels., The activity of the naturally U-238, Th-232, and K-40 were determined as (Bq/kg) using gamma spectroscopy (Hyperactive pure germanium detector). Concentration of U and Th were determined in (ppm) using spectrophotometer technique by Arsenazo 111 and Piridy l-Azo -Resorcinol (PAR) indicators. Sequential extraction tests were carried out in order to determine the quantity of the radionuclide associated with various fractions as exchangeable, carbonate, acid soluble and in the residue. The results evaluated were compared to the associated activity indices (AI) that were defined by former USSR and West Germany

Production of multicharged radioactive ion beams for spiral: studies and realization of the first target-ion source system

International Nuclear Information System (INIS)

Maunoury, L.

1998-01-01

In the framework of the SPIRAL project, which concerns the production and the acceleration of a multicharged radioactive ions beam, the following part has been studied: production and ionization of the radioactive ions beam. A first target-source (nanogan II), devoted exclusively to the production of multicharged radioactive ions gas type beams, has been studied and tested. The diffusion efficiency has been deduced from the diffusion equations (Fick laws). This efficiency is governed by the following parameters: the temperature, the grains size of the target, the Arrhenius parameters and the radioactive period. Another study concerning the production targets is presented. It deals with the temperature distribution allowing an utilization of more than one month at a temperature of 2400 K. Another development (SPIRAL II) is devoted to the production of high neutron content radioactive atoms created by the uranium fission, from fast neutrons. The neutrons beam is produced by the ''stripping break-up'' of a deutons beam in a converter. (A.L.B.)

Development of Value-Added Products from Residual Algae to Biomass

Energy Technology Data Exchange (ETDEWEB)

Behnke, Craig [Sapphire Energy, San Diego, CA (United States)

2016-02-29

DOE Award # EE0000393 was awarded to fund research into the development of beneficial uses of surplus algal biomass and the byproducts of biofuel production. At the time of award, Sapphire’s intended fuel production pathway was a fairly conventional extraction of lipids from biomass, resulting in a defatted residue which could be processed using anaerobic digestion. Over the lifetime of the award, we conducted extensive development work and arrived at the conclusion that anaerobic digestion presented significant technical challenges for this high-nitrogen, high-ash, and low carbon material. Over the same timeframe, Sapphire’s fuel production efforts came to focus on hydrothermal liquefaction. As a result of this technology focus, the residue from fuel production became unsuitable for either anaerobic digestion (or animal feed uses). Finally, we came to appreciate the economic opportunity that the defatted biomass could represent in the animal feed space, as well as understanding the impact of seasonal production on a biofuels extraction plant, and sought to develop uses for surplus biomass produced in excess of the fuel production unit’s capacity.

Effects of radioactive by-products along the extraction of rare earth elements on aquatic and terrestrial organisms

International Nuclear Information System (INIS)

Findeiss, Matthias

2016-01-01

throughout analysis of thorium fluxes along the process of SEE recovery was carried out, and the effects of disposals and other products involved were measured based on ecotoxicological tests with aquatic and terrestrial organisms. In experiments with thorium exclusively the heavy metal property was regarded since radiation effects with a radioactivity half-life of approximately 14 billion years play a subordinate role in typical ecotoxicological testing periods. Moreover, it should be noted that thorium occurs in nature alongside its decay products. Th(OH) 4 at pH 6.5 to 8 showed no toxic effects in all organisms studied, aquatic (bacteria, algae and daphnia) and terrestrial (springtails, earthworms). Thorium thus does not appear to be a problem in the range of water solubility and in soil concentrations typical found.The effects of process wastewater from various process steps in the production of REE were evaluated based on eudialyte, which was investigated as an example for REE minerals. Figure 1 shows the investigated process steps of eudialyte: after mining, drill, blast and load haul operation, the ore is milled and grinded. In order to enrich it, the wanted mineral is flotated. Afterwards chemicals (acids) are added to dissolve the minerals. Impurities are removed by pH adjustment and precipitation which is also used for REE separation later. Stronger REE separation is achieved by solvent extraction and finally pure REE are obtained by electrolysis. Ground and flotated eudialyte had no or very little ecotoxicological effects. By contrast, leaching residues showed that concentrations which arise during production have a negative impact on all tested organisms (see figure 1). Due to mixture toxicity, it is difficult to estimate which compound is responsible for the total toxicity. It is known that the toxicity of metals differs in various organisms. A general trend shows the following toxicity sequence: Hg> Ag> Cu> Cd> Zn> Ni> Pb> Cr> Sn (Luoma and Rainbow 2011; Merian

Effects of radioactive by-products along the extraction of rare earth elements on aquatic and terrestrial organisms

Energy Technology Data Exchange (ETDEWEB)

Findeiss, Matthias

2016-12-13

throughout analysis of thorium fluxes along the process of SEE recovery was carried out, and the effects of disposals and other products involved were measured based on ecotoxicological tests with aquatic and terrestrial organisms. In experiments with thorium exclusively the heavy metal property was regarded since radiation effects with a radioactivity half-life of approximately 14 billion years play a subordinate role in typical ecotoxicological testing periods. Moreover, it should be noted that thorium occurs in nature alongside its decay products. Th(OH){sub 4} at pH 6.5 to 8 showed no toxic effects in all organisms studied, aquatic (bacteria, algae and daphnia) and terrestrial (springtails, earthworms). Thorium thus does not appear to be a problem in the range of water solubility and in soil concentrations typical found.The effects of process wastewater from various process steps in the production of REE were evaluated based on eudialyte, which was investigated as an example for REE minerals. Figure 1 shows the investigated process steps of eudialyte: after mining, drill, blast and load haul operation, the ore is milled and grinded. In order to enrich it, the wanted mineral is flotated. Afterwards chemicals (acids) are added to dissolve the minerals. Impurities are removed by pH adjustment and precipitation which is also used for REE separation later. Stronger REE separation is achieved by solvent extraction and finally pure REE are obtained by electrolysis. Ground and flotated eudialyte had no or very little ecotoxicological effects. By contrast, leaching residues showed that concentrations which arise during production have a negative impact on all tested organisms (see figure 1). Due to mixture toxicity, it is difficult to estimate which compound is responsible for the total toxicity. It is known that the toxicity of metals differs in various organisms. A general trend shows the following toxicity sequence: Hg> Ag> Cu> Cd> Zn> Ni> Pb> Cr> Sn (Luoma and Rainbow 2011

Induced radioactivity in a 4 MW target and its surroundings

CERN Document Server

Agosteo, Stefano; Otto, Thomas; Silari, Marco

2003-01-01

An important aspect of a future CERN Neutrino Factory is the material activation arising from a 2.2 GeV, 4 MW proton beam striking a mercury target. An estimation of the hadronic inelastic interactions and the production of residual nuclei in the target, the magnetic horn, the decay tunnel, the surrounding rock and a downstream dump was performed by the Monte Carlo hadronic cascade code FLUKA. The aim was both to assess the dose equivalent rate to be expected during maintenance work and to evaluate the amount of residual radioactivity, which will have to be disposed of after the facility has ceased operation.

Radioactivity of raw materials, metallurgical and casting products

International Nuclear Information System (INIS)

Hons, J.

2000-01-01

At present, the radioactive contamination of metallurgical products and initial materials represent a potential obstacle in foreign and domestic trade. It is of course an undesirable threat o the living environment on the one side and, at the same time, a new incorrectly used means for suppressing competition and forming a protection 'umbrella' of the national market to desirable imports on the other hand

Development of risk-based computer models for deriving criteria on residual radioactivity and recycling

International Nuclear Information System (INIS)

Chen, S.Y.

1994-01-01

Argonne National Laboratory (ANL) is developing multimedia environmental pathway and health risk computer models to assess radiological risks to human health and to derive cleanup guidelines for environmental restoration, decommissioning, and recycling activities. These models are based on the existing RESRAD code, although each has a separate design and serves different objectives. Two such codes are RESRAD-BUILD and RESRAD-PROBABILISTIC. The RESRAD code was originally developed to implement the US Department of Energy's (DOE's) residual radioactive materials guidelines for contaminated soils. RESRAD has been successfully used by DOE and its contractors to assess health risks and develop cleanup criteria for several sites selected for cleanup or restoration programs. RESRAD-BUILD analyzes human health risks from radioactive releases during decommissioning or rehabilitation of contaminated buildings. Risks to workers are assessed for dismantling activities; risks to the public are assessed for occupancy. RESRAD-BUILD is based on a room compartmental model analyzing the effects on room air quality of contaminant emission and resuspension (as well as radon emanation), the external radiation pathway, and other exposure pathways. RESRAD-PROBABILISTIC, currently under development, is intended to perform uncertainty analysis for RESRAD by using the Monte Carlo approach based on the Latin-Hypercube sampling scheme. The codes being developed at ANL are tailored to meet a specific objective of human health risk assessment and require specific parameter definition and data gathering. The combined capabilities of these codes satisfy various risk assessment requirements in environmental restoration and remediation activities

Development of risk-based computer models for deriving criteria on residual radioactivity and recycling

International Nuclear Information System (INIS)

Chen, Shih-Yew

1995-01-01

Argonne National Laboratory (ANL) is developing multimedia environmental pathway and health risk computer models to assess radiological risks to human health and to derive cleanup guidelines for environmental restoration, decommissioning, and recycling activities. These models are based on the existing RESRAD code, although each has a separate design and serves different objectives. Two such codes are RESRAD-BUILD and RESRAD-PROBABILISTIC. The RESRAD code was originally developed to implement the U.S. Department of Energy's (DOE's) residual radioactive materials guidelines for contaminated soils. RESRAD has been successfully used by DOE and its contractors to assess health risks and develop cleanup criteria for several sites selected for cleanup or restoration programs. RESRAD-BUILD analyzes human health risks from radioactive releases during decommissioning or rehabilitation of contaminated buildings. Risks to workers are assessed for dismantling activities; risks to the public are assessed for occupancy. RESRAD-BUILD is based on a room compartmental model analyzing the effects on room air quality of contaminant emission and resuspension (as well as radon emanation), the external radiation pathway, and other exposure pathways. RESRAD-PROBABILISTIC, currently under development, is intended to perform uncertainty analysis for RESRAD by using the Monte Carlo approach based on the Latin-Hypercube sampling scheme. The codes being developed at ANL are tailored to meet a specific objective of human health risk assessment and require specific parameter definition and data gathering. The combined capabilities of these codes satisfy various risk assessment requirements in environmental restoration and remediation activities. (author)

Instructive for radioactive solid waste management

International Nuclear Information System (INIS)

Mora Rodriguez, Patricia

2014-01-01

An instructive is established for the management system of radioactive solid residues waste of the Universidad de Costa Rica, ensuring the collection, segregation, storage and disposal of waste. The radioactive solid waste have been segregated and transferred according to features and provisions of the Universidad de Costa Rica and CICANUM [es

Development and quality characteristics of shelf-stable soy-agushie: a residual by-product of soymilk production.

Science.gov (United States)

Nti, Christina A; Plahar, Wisdom A; Annan, Nana T

2016-03-01

A process was developed for the production of a high-protein food ingredient, soy-agushie, from the residual by-product of soymilk production. The product, with a moisture content of about 6%, was evaluated for its quality characteristics and performance in traditional dishes. The protein content was about 26% with similar amino acids content as that of the whole soybean. Lysine remained high in the dehydrated product (6.57 g/16 g N). While over 60% of the original B vitamins content in the beans was extracted with the milk, high proportions of the minerals were found to be retained in the residual by-product. The process adequately reduced the trypsin inhibitor levels in the beans from 25 to 1.5 mg/g. High sensory scores were obtained for recipes developed with soy-agushie in traditional dishes. The scope of utilization of the soy-agushie could be widened to include several traditional foods and bakery products for maximum nutritional benefits.

Construction of a risk assessment system for chemical residues in agricultural products.

Science.gov (United States)

Choi, Shinai; Hong, Jiyeon; Lee, Dayeon; Paik, Minkyoung

2014-01-01

Continuous monitoring of chemical residues in agricultural and food products has been performed by various government bodies in South Korea. These bodies have made attempts to systematically manage this information by creating a monitoring database system as well as a system based on these data with which to assess the health risk of chemical residues in agricultural products. Meanwhile, a database system is being constructed consisting of information about monitoring and, following this, a demand for convenience has led to the need for an evaluation tool to be constructed with the data processing system. Also, in order to create a systematic and effective tool for the risk assessment of chemical residues in foods and agricultural products, various evaluation models are being developed, both domestically and abroad. Overseas, systems such as Dietary Exposure Evaluation Model: Food Commodity Intake Database and Cumulative and Aggregate Risk Evaluation System are being used; these use the US Environmental Protection Agency as a focus, while the EU has developed Pesticide Residue Intake Model for assessments of pesticide exposure through food intake. Following this, the National Academy of Agricultural Science (NAAS) created the Agricultural Products Risk Assessment System (APRAS) which supports the use and storage of monitoring information and risk assessments. APRAS efficiently manages the monitoring data produced by NAAS and creates an extraction feature included in the database system. Also, the database system in APRAS consists of a monitoring database system held by the NAAS and food consumption database system. Food consumption data is based on Korea National Health and Nutrition Examination Survey. This system is aimed at exposure and risk assessments for chemical residues in agricultural products with regards to different exposure scenarios.

9 CFR 318.16 - Pesticide chemicals and other residues in products.

Science.gov (United States)

2010-01-01

..., DEPARTMENT OF AGRICULTURE AGENCY ORGANIZATION AND TERMINOLOGY; MANDATORY MEAT AND POULTRY PRODUCTS INSPECTION... ingredients. Residues of pesticide chemicals, food additives and color additives or other substances in or on ingredients (other than meat, meat byproducts, and meat food products) used in the formulation of products...

Recovering method for high level radioactive material

International Nuclear Information System (INIS)

Fukui, Toshiki

1998-01-01

Offgas filters such as of nuclear fuel reprocessing facilities and waste control facilities are burnt, and the burnt ash is melted by heating, and then the molten ashes are brought into contact with a molten metal having a low boiling point to transfer the high level radioactive materials in the molten ash to the molten metal. Then, only the molten metal is evaporated and solidified by drying, and residual high level radioactive materials are recovered. According to this method, the high level radioactive materials in the molten ashes are transferred to the molten metal and separated by the difference of the distribution rate of the molten ash and the molten metal. Subsequently, the molten metal to which the high level radioactive materials are transferred is heated to a temperature higher than the boiling point so that only the molten metal is evaporated and dried to be removed, and residual high level radioactive materials are recovered easily. On the other hand, the molten ash from which the high level radioactive material is removed can be discarded as ordinary industrial wastes as they are. (T.M.)

Treatment methods and comparative risks of thorium removal from waste residues

Energy Technology Data Exchange (ETDEWEB)

Porter, R.D.; Hamby, D.M.; Martin, J.E.

1997-07-01

This study was done to examine the risks of remediation and the effectiveness of removal methods for thorium and its associated radioactive decay products from various soils and wastes associated with DOE`s Formerly Utilized Sites Remedial Action Program (FUSRAP). Removal of {sup 230}Th from uranium process residues would significantly reduce the buildup of {sup 226}Ra (half-life of 1600 years), and since {sup 230}Th concentrations at most of the important sites greatly exceed the {sup 226}Ra concentrations, such removal would reduce the accumulation of additional radiation risks associated with {sup 226}Ra and its products; and, if treatment also removed {sup 226}Ra, these risks could be mitigated even further. Removal of {sup 232}Th from thorium process residues would remove the source material for {sup 228}Ra, and since {sup 228}Ra has a half-life of 5.76 years, its control at FUSRAP sites could be done with land use controls for the 30--50 years required for {sup 228}Ra and the risks associated with its decay products to decay away. It must be recognized, however, that treatment methods invariably require workers to process residues and waste materials usually with bulk handling techniques. These processes expose workers to the radioactivity in the materials, therefore, workers would incur radiological risks in addition to industrial accident risks. An important question is whether the potential reduction of future radiological risks to members of the public justifies the risks that are incurred by remediation workers due to handling materials. This study examines, first, the effectiveness of treatment and then the risks that would be associated with remediation.

Constraints due to the production of radioactive ion beams in the SPIRAL project

International Nuclear Information System (INIS)

Leroy, R.; Huguet, Y.; Jardin, P.; Marry, C.; Pacquet, J.Y.; Villari, A.C.C.

1997-01-01

The radioactive ion beams that will be delivered by the SPIRAL facility will be produced by the interaction of a stable high energy and high intensity primary ion beam delivered by the GANIL cyclotrons with a carbon target heated to 2000 deg C. During this interaction, some radioactive atoms will be created and will diffuse out of the target before entering into an electron cyclotron resonance ion source where they will be ionized and extracted. The production of radioactive ion beams with this method implies high radiation fields that activate and can damage materials located in the neighborhood of the target. Therefore, the production system which is composed of the permanent magnet ECR ion source coupled to a graphite target will be changed after two weeks of irradiation. As this ensemble will be very radioactive, this operation has to be supervised by remote control. The radiation levels around the target-ion source system and a detailed description of the different precautions that have been taken for safety and for prevention of contamination and irradiation are presented. (author)

Monitoring residue in animals and primary products of animal origin

Directory of Open Access Journals (Sweden)

Janković Saša

2008-01-01

Full Text Available The objective of control and systematic monitoring of residue is to secure, by the examination of a corresponding number of samples, the efficient monitoring of the residue level in tissues and organs of animals, as well as in primary products of animal origin. This creates possibilities for the timely taking of measures toward the securing of food hygiene of animal origin and the protection of public health. Residue can be a consequence of the inadequate use of medicines in veterinary medicine and pesticides in agriculture and veterinary medicine, as well as the polluting of the environment with toxic elements, dioxins, polychlorinated biphenyls, and others. Residue is being monitored in Serbia since 1972, and in 2004, national monitoring was brought to the level of EU countries through significant investments by the Ministry of Agriculture, Forestry and Water Management. This is also evident in the EU directives which permit exports of all kinds of meat and primary products of animal origin, covered by the Residue Monitoring Program. The program of systematic examinations of residue has been coordinated with the requirements of the European Union, both according to the type of examined substance, as well as according to the number of samples and the applied analytical techniques. In addition to the development of methods and the including of new harmful substances into the monitoring programme, it is also necessary to coordinate the national regulations that define the maximum permitted quantities of certain medicines and contaminants with the EU regulations, in order to protect the health of consumers as efficiently as possible, and for the country to take equal part in international trade.

Artificial radioactive products in the atmosphere at Paris. [In French

Energy Technology Data Exchange (ETDEWEB)

Abribat, M; Pouradier, J; Venet, A M

1952-01-01

The radioactivity of solid matter in rain water and air collected near Paris in November 1951, and in April and May 1952, follows the same decay law as that observed for fission products after a nuclear detonation in Nevada in November 1951.

Radioactive-site-remediation technologies seminar. Speaker slide copies

International Nuclear Information System (INIS)

1992-06-01

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

Plan 2008. Costs starting in 2010 for the radioactive residual products from nuclear power. Basis for fees and guarantees in 2010 and 2011

Energy Technology Data Exchange (ETDEWEB)

2008-12-15

reference calculation and the figures on which it is based are presented in the report as background information. The reference scenario includes the following facilities and systems in operation: - Transportation system for radioactive waste products. - Central interim storage facility for spent nuclear fuel, Clab. - Final repository for short-lived low- and intermediate-level operational waste, SFR. - Laboratories for development of encapsulation and final disposal technology. The reference scenario also includes the following additional facilities: - canister factory and encapsulation plant for spent nuclear fuel, - final repository for spent nuclear fuel, SFK, - interim storage facility for core components, BFA, - final repository for long-lived low- and intermediate-level waste, SFL, and - final repository for decommissioning waste (extension of SFR). The costs according to the reference scenario also include costs for research, development and demonstration (RDandD), as well as SKB's central functions. The latter include general functions such as corporate management, business support, EIA, overall safety matters, etc. Other costs include costs for decommissioning and dismantling of reactor plants as well as at-plant facilities for interim storage or final disposal of low- and intermediate-level waste. The Financing Act, along with the Ordinance, stipulates a number of conditions that have an effect on the scope of the reference scenario as well as on the calculation model used by SKB. Such conditions include the reactor operating time on which the estimate of the quantity of waste products is based, as well as the fact that uncertainties with regard to future developments in different areas have to be taken into account. In addition, the calculation should only include waste products, which, according to the Financing Act's definition of residual products, excludes the management of operational waste. Among other things, the existing facility at SFR is

Radioactive demonstration of DWPF product control strategy

International Nuclear Information System (INIS)

Andrews, M.K.; Bibler, N.E.

1992-01-01

The effectiveness of the product and process control strategies that will be utilized by the Defense Waste Processing Facility (DWPF) was demonstrated during a campaign in the Shielded Cells Facility (SCF) of the Savannah River Technology Center (SRTC). The remotely operated process included the preparation of the melter feed, vitrification in a slurry-fed 1/100th scale melter and analysis of the glass product both for its composition and durability. The campaign processed approximately 10 kg (on a dry basis) of radioactive sludge from Tank 51. This sludge is representative of the first batch of sludge that will be sent to the DWPF for immobilization into borosilicate glass. Additions to the sludge were made based on calculations using the Product Composition Control System (PCCS). Analysis of the glass produced during the campaign showed that a durable glass was produced with a composition similar to that predicted using the PCCS

Protection against radioactive contamination of food and agricultural products

International Nuclear Information System (INIS)

Szabo, A.; Kovacs, Z.

1977-01-01

Due to contaminating effects from nuclear explosions and nuclear power plants, the systematic investigation of environmental radioactive contamination is absolutely necessary. In order to reduce the artificial radiation dose to which the human body is exposed, isotope content of foods and agricultural products should be known. The authors evaluate the decontamination possibilities of food produced from vegetable and animal products, starting from the contamination of some products. For vegetable product decontamination the use of suitable fertilizers, thorough scrubbing in excess water and, for cereals, milling is proposed. As the most effective preventive measure of radiation contamination of food products of animal origin, appropriate packing is proposed. The storage and preservation problems are emphasized for short half-life radiation contamination. (P.J.)

The effect of delignification process with alkaline peroxide on lactic acid production from furfural residues

Directory of Open Access Journals (Sweden)

Yong Tang

2012-11-01

Full Text Available Furfural residues produced from the furfural industry were investigated as a substrate for lactic acid production by simultaneous saccharification and fermentation (SSF. Alkaline peroxide was used for delignification of furfural residues to improve the final lactic acid concentration. The residue was treated with 1.3% to 1.7% hydrogen peroxide at 80 °C for 1 h with a substrate concentration of 3.33%. SSF of furfural residues with different delignification degrees were carried out to evaluate the effect of delignification degree on lactic acid production. Using corn hydrolysates/ furfural residues as substrates, SSF with different media were carried out to investigate the effect of lignin on the interaction between enzymes and lactic acid bacteria. Lactic acid bacteria had a negative effect on cellulase, thus resulting in the reduction of enzyme activity. Lignin and nutrients slowed down the decreasing trend of enzyme activity. A higher delignification resulted in a slower fermentation rate and lower yield due to degradation products of lignin and the effect of lignin on the interaction between enzymes and lactic acid bacteria. For the purpose of lactic acid production, a moderate delignification (furfural residues with the lignin content of 14.8% was optimum.

The potential for energy production from crop residues in Zimbabwe

Energy Technology Data Exchange (ETDEWEB)

Jingura, R.M.; Matengaifa, R. [School of Engineering Sciences and Technology, Chinhoyi University of Technology, P. Bag 7724, Chinhoyi (Zimbabwe)

2008-12-15

There is increasing interest in Zimbabwe in the use of renewable energy sources as a means of meeting the country's energy requirements. Biomass provides 47% of the gross energy consumption in Zimbabwe. Energy can be derived from various forms of biomass using various available conversion technologies. Crop residues constitute a large part of the biomass available from the country's agriculture-based economy. The potential for energy production of crop residues is examined using data such as estimates of the quantities of the residues and their energy content. The major crops considered are maize, sugarcane, cotton, soyabeans, groundnuts, wheat, sorghum, fruits and forestry plantations. Quantities of residues are estimated from crop yields by using conversion coefficients for the various crops. Long-term crop yields data from 1970 to 1999 were used. Total annual residue yields for crops, fruits and forestry plantations are 7.805 Mt, 378 kt and 3.05 Mt, respectively. The crops, fruits and forestry residues have energy potential of 81.5, 4.9 and 44.3 PJ per year, respectively. This represents about 44% of the gross energy consumption in Zimbabwe. The need to balance use of crop residues for both energy purposes and other purposes such as animal feeding and soil fertility improvement is also highlighted. (author)

Study of immobilization of radioactive wastes in asphaltic matrices and elastomeric residues by using microwave technique

International Nuclear Information System (INIS)

Caratin, Reinaldo Leonel

2007-01-01

In the present work, the technique of microwave heating was used to study the immobilization of low and intermediate activity level radioactive waste, such as spent ion exchange resin used to remove undesirable ions of primary circuits of refrigeration in water refrigerated nuclear reactors, and those used in chemical and radionuclide separation columns in the quality control of radioisotopes. Bitumen matrices reinforced with some kinds of rubber (Neoprene R , silicon and ethylene-vinyl-acetate), from production leftovers or scraps, were used for incorporation of radioactive waste. The samples irradiation was made in a home microwave oven that operates at a frequency of 2.450 MHZ with 1.000 W power. The samples were characterized by developing assays on penetration, leaching resistance, softening, flash and combustion points, thermogravimetry and optical microscopy. The obtained results were compatible with the pattern of matrices components, which shows that technique is a very useful alternative to conventional immobilization methods and to those kinds of radioactive waste. (author)

Residues of tritium-labeled morantel in lactating dairy cattle

International Nuclear Information System (INIS)

Lynch, M.J.; Mosher, F.R.; Burnett, D.M.; Newby, T.J.

1987-01-01

Residues of morantel and its metabolites were monitored in plasma, urine, and milk of five lactating dairy cattle that received an oral dose of [4,4-pyrimidyl- 3 H 2 ]morantel tartrate at 10 mg/kg. Drug-related radioactivity peaked in plasma at 8 h and in milk by the second milking, postdose, and was 170 and 84 ng/mL, respectively. The fraction of total residues in milk convertible to the marker compound, N-methyl-1,3-propanediamine, was 0.38 on the basis of a comparison of the areas under the curves for total and marker residues. Five days after dosing, 3.9% of the total radioactivity in liver was recovered as tritium water. Total drug-related residues in this target tissue averaged 1.15 μg/g. About half of the drug-related residues in liver was unextractable and was classified by bound

Radiological considerations on multi-MW targets Part I Induced radioactivity

CERN Document Server

Agosteo, S; Silari, M

2005-01-01

CERN is designing a Superconducting Proton Linac (SPL) to provide a 2.2GeV, 4MW proton beam to feed facilities like, for example, a future Neutrino Factory or a Neutrino SuperBeam. The material activation in such facilities is an important aspect that has to be taken into account at an early design stage. In particular, the choice of the target has consequences on the induced radioactivity and dose rates in the target itself and in its surroundings. In the present work, the radiological aspects of a stationary target made up of small tantalum pellets are compared to those of a free-surface jet of mercury. An estimation of the hadronic inelastic interactions and the production of residual nuclei in the target, the magnetic horn, the decay tunnel, the surrounding rock and a downstream dump were performed for both targets by the Monte Carlo hadronic cascade code FLUKA. The aim was to assess the dose equivalent rate to be expected during maintenance work and to evaluate the amount of residual radioactivity, which...

Microbiological Production of Surfactant from Agricultural Residuals for IOR Application

Energy Technology Data Exchange (ETDEWEB)

Bala, Greg Alan; Bruhn, Debby Fox; Fox, Sandra Lynn; Noah, Karl Scott; Thompson, David Neal

2002-04-01

Utilization of surfactants for improved oil recovery (IOR) is an accepted technique with high potential. However, technology application is frequently limited by cost. Biosurfactants (surface-active molecules produced by microorganisms) are not widely utilized in the petroleum industry due to high production costs associated with use of expensive substrates and inefficient product recovery methods. The economics of biosurfactant production could be significantly impacted through use of media optimization and application of inexpensive carbon substrates such as agricultural process residuals. Utilization of biosurfactants produced from agricultural residuals may 1) result in an economic advantage for surfactant production and technology application, and 2) convert a substantial agricultural waste stream to a value-added product for IOR. A biosurfactant with high potential for use is surfactin, a lipopeptide biosurfactant, produced by Bacillus subtilis. Reported here is the production and potential IOR utilization of surfactin produced by Bacillus subtilis (American Type Culture Collection (ATCC) 21332) from starch-based media. Production of surfactants from microbiological growth media based on simple sugars, chemically pure starch medium, simulated liquid and solid potato-process effluent media, a commercially prepared potato starch in mineral salts, and process effluent from a potato processor is discussed. Additionally, the effect of chemical and physical pretreatments on starchy feedstocks is discussed.

Radioactive residues. Current and prospective problems. Les residus radioactifs. Problems actuels et perspectives

Energy Technology Data Exchange (ETDEWEB)

Gauvenet, A.

1975-07-01

After having described the principal characteristics of radioactive residues, the author examined the current problems posed by liquid and gaseous effluents and stressed that nuclear installations are definitely much less polluting, with an identical power output, than conventional power stations. Research programs have been undertaken in the face of the predictable increase in activity. The gist of the matter is to maintain the absorbed doses at their present level and to study the problem of compounds with a long lifetime, the accumulation of which would create considerable danger on a world scale. With respect to the stockpiling of wastes, the author described the various techniques currently used and cited studies in progress, some of which--such as vitrification--have already come into the first stages of application. After having noted that the waste problem undoubtedly constitutes a technical difficulty and perhaps even more so on the psychological plane, the author defined in conclusion the conditions that should be established so that this problem does not hinder the short- and long-term development of nuclear energy.

Control of Orphan Sources and Other Radioactive Material in the Metal Recycling and Production Industries. Specific Safety Guide (Arabic Edition)

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-09-01

Accidents involving orphan sources and other radioactive material in the metal recycling and production industries have resulted in serious radiological accidents as well as in harmful environmental, social and economic impacts. This Safety Guide provides recommendations, the implementation of which should prevent such accidents and provide confidence that scrap metal and recycled products are safe. Contents: 1. Introduction; 2. Protection of people and the environment; 3. Responsibilities; 4. Monitoring for radioactive material; 5. Response to the discovery of radioactive material; 6. Remediation of contaminated areas; 7. Management of recovered radioactive material; Annex I: Review of events involving radioactive material in the metal recycling and production industries; Annex II: Categorization of radioactive sources; Annex III: Some examples of national and international initiatives.

Control of Orphan Sources and Other Radioactive Material in the Metal Recycling and Production Industries. Specific Safety Guide (Arabic Edition)

International Nuclear Information System (INIS)

2014-01-01

Accidents involving orphan sources and other radioactive material in the metal recycling and production industries have resulted in serious radiological accidents as well as in harmful environmental, social and economic impacts. This Safety Guide provides recommendations, the implementation of which should prevent such accidents and provide confidence that scrap metal and recycled products are safe. Contents: 1. Introduction; 2. Protection of people and the environment; 3. Responsibilities; 4. Monitoring for radioactive material; 5. Response to the discovery of radioactive material; 6. Remediation of contaminated areas; 7. Management of recovered radioactive material; Annex I: Review of events involving radioactive material in the metal recycling and production industries; Annex II: Categorization of radioactive sources; Annex III: Some examples of national and international initiatives

Control of Orphan Sources and Other Radioactive Material in the Metal Recycling and Production Industries. Specific Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2013-01-01

Accidents involving orphan sources and other radioactive material in the metal recycling and production industries have resulted in serious radiological accidents as well as in harmful environmental, social and economic impacts. This Safety Guide provides recommendations, the implementation of which should prevent such accidents and provide confidence that scrap metal and recycled products are safe. Contents: 1. Introduction; 2. Protection of people and the environment; 3. Responsibilities; 4. Monitoring for radioactive material; 5. Response to the discovery of radioactive material; 6. Remediation of contaminated areas; 7. Management of recovered radioactive material; Annex I: Review of events involving radioactive material in the metal recycling and production industries; Annex II: Categorization of radioactive sources; Annex III: Some examples of national and international initiatives

Selective labelling of apolipoproteins A-I and C-I at methionine residues by (TH) methyl exchange

Energy Technology Data Exchange (ETDEWEB)

Hancock, W.S.; Harding, D.R.K.; Barling, P.M.; Sparrow, J.T.

1985-01-01

Apolipoproteins C-I and A-I were radioactively labelled with tritium by (TH)-methyl exchange. The methionine residues were first methylated with (TH)-methyl iodide at pH4 and the reaction products were purified by gel filtration and cation exchange chromatography. The products were then demethylated with 2-mercaptoethanol (6 M) at pH 8.6 to regenerate the apolipoproteins in an unmodified but tritiated form. The specific radioactivity for apolipoprotein C-I and A-I was 3.5 x 10W and 1.5 x 10X dpm/pmol respectively. The properties of (TH)-apolipoprotein C-I were examined by reversed phase HPLC and by incorporation into very low density lipoproteins (VLDL).

Application of x-ray residual stress measurement to products

International Nuclear Information System (INIS)

Goto, T.; Iwamura, T.

1975-01-01

The X-ray residual stress measuring method is the only nondestructive method for measuring residual stress in polycrystalline materials. It is capable of obtaining information not only on macroscopic stress but also microscopic stress. The authors are employing this method for the development of pre-service and in-service inspection methods and for the improvement of various manufacturing techniques. In this paper, the results of measurement of some products as examples of its application are described. The examples introduced concern the following: (1) Selection of optimum conditions in heat treatment and stress-relief treatment. (2) Residual stress produced by mechanical processes such as autofrettage and flow form. (3) Check of manufacturing processes of rotary shaft and welded parts. (4) Estimation of fatigue strength of shot-peened part. (5) Detection of fatigue damage of shot-peened part. (auth.)

Research Progress on Pesticide Residue Analysis Techniques in Agro-products

Directory of Open Access Journals (Sweden)

HE Ze-ying

2016-07-01

Full Text Available There are constant occurrences of acute pesticide poisoning among consumers and pesticide residue violations in agro-products import/export trading. Pesticide residue analysis is the important way to protect the food safety and the interest of import/export enterprises. There has been a rapid development in pesticide residue analysis techniques in recent years. In this review, the research progress in the past five years were discussed in the respects of samples preparation and instrument determination. The application, modification and development of the QuEChERS method in samples preparation and the application of tandem mass spectrometry and high resolution mass spectrometry were reviewed. And the implications for the future of the field were discussed.

Plan 2008. Costs starting in 2010 for the radioactive residual products from nuclear power. Basis for fees and guarantees in 2010 and 2011

International Nuclear Information System (INIS)

2008-12-01

calculation and the figures on which it is based are presented in the report as background information. The reference scenario includes the following facilities and systems in operation: - Transportation system for radioactive waste products. - Central interim storage facility for spent nuclear fuel, Clab. - Final repository for short-lived low- and intermediate-level operational waste, SFR. - Laboratories for development of encapsulation and final disposal technology. The reference scenario also includes the following additional facilities: - canister factory and encapsulation plant for spent nuclear fuel, - final repository for spent nuclear fuel, SFK, - interim storage facility for core components, BFA, - final repository for long-lived low- and intermediate-level waste, SFL, and - final repository for decommissioning waste (extension of SFR). The costs according to the reference scenario also include costs for research, development and demonstration (RDandD), as well as SKB's central functions. The latter include general functions such as corporate management, business support, EIA, overall safety matters, etc. Other costs include costs for decommissioning and dismantling of reactor plants as well as at-plant facilities for interim storage or final disposal of low- and intermediate-level waste. The Financing Act, along with the Ordinance, stipulates a number of conditions that have an effect on the scope of the reference scenario as well as on the calculation model used by SKB. Such conditions include the reactor operating time on which the estimate of the quantity of waste products is based, as well as the fact that uncertainties with regard to future developments in different areas have to be taken into account. In addition, the calculation should only include waste products, which, according to the Financing Act's definition of residual products, excludes the management of operational waste. Among other things, the existing facility at SFR is excluded from the

Evaluation of NORM residues in the Morro Redondo waterworks, Brazil

International Nuclear Information System (INIS)

Pinto, Michele C.F.; Rocha, Zildete

2007-01-01

Most mineral resources present naturally occurring radioactive material known by the acronym NORM. Some of them, specially those geological material originated from igneous rock present elevated radionuclides concentration. The exploration of these materials may elevate human exposure to the natural ionizing radiation, by removing them from the natural compartment or by increasing the radionuclides concentration in products, by products and more frequently in the industrial residues, these are referred as TENORM Technologically Enhanced NORM. The residues of the waterworks, especially those of the iron and manganese remotion are expected to contain radioactivity concentration due to geological reasons. The paper evaluates the natural radionuclide concentration in the waste water sludge of the iron removing process carried out by the Water Treatment Plant (WTP) - Morro Redondo waterwork operated by Companhia de Saneamento de Minas Gerais - COPASA. Such waterwork supplies drink water for more than 200.000 people, inhabitants of the south part of Belo Horizonte and Nova Lima. The water is extracted from three rock source formations in the iron quadrangle of Minas Gerais, namely Cercadinho, Fechos and Mutuca. The sludges samples analysed have shown values around 300 Bq kg -1 for 226 Ra, in radiological point of view, the most important radionuclide. Values taken from literature were considered - 10.000 Bq kg -1 are not rare, and the ones around 300 Bq kg -1 are normal. (author)

Radioactive characterization of the main materials involved in the titanium dioxide production process and their environmental radiological impact.

Science.gov (United States)

Mantero, J; Gazquez, M J; Bolivar, J P; Garcia-Tenorio, R; Vaca, F

2013-06-01

A study about the distribution of several radionuclides from the uranium and the thorium series radionuclides along the production process of a typical NORM industry devoted to the production of titanium dioxide has been performed. With this end the activity concentrations in raw materials, final product, co-products, and wastes of the production process have been determined by both gamma-ray and alpha-particle spectrometry. The main raw material used in the studied process (ilmenite) presents activity concentrations of around 300 Bq kg(-1) for Th-series radionuclides and 100 Bq kg(-1) for the U-series ones. These radionuclides in the industrial process are distributed in the different steps of the production process according mostly to the chemical behaviour of each radioelement, following different routes. As an example, most of the radium remains associated with the un-dissolved material waste, with activity concentrations around 3 kBq kg(-1) of (228)Ra and around 1 kBq kg(-1) of (226)Ra, while the final commercial products (TiO2 pigments and co-products) contain negligible amounts of radioactivity. The obtained results have allowed assessing the possible public radiological impact associated with the use of the products and co-products obtained in this type of industry, as well as the environmental radiological impact associated with the solid residues and liquid generated discharges. Copyright © 2013 Elsevier Ltd. All rights reserved.

Estimated effects of radioactive fallout on agricultural production in Sweden. Contamination of crop products

International Nuclear Information System (INIS)

Eriksson, Aake; Loensjoe, H.; Karlstroem, F.

1994-01-01

The study is part of a research project, 'Radioactivity problems within the food sector' performed in 1991-94 at the request of the National Board of Agriculture in Sweden by The National Research Establishment, Dept. of NBC Defence, and the Dept. of Radioecology and the Dept. of Biosystems and Technology, the latter two belonging to the Swedish Univ. of Agricultural Sciences. The aim of the study was to investigate the contamination levels that may occur in agricultural crop products in Sweden in a situation of radioactive fallout from the use of nuclear weapons. There is a risk for a major nuclide transport in agricultural systems by the feeds, mainly by pasture grass and silage and hay crops but also to some extent by grain crops. For that reason, cattle are expected to be important vectors of the fallout nuclides to the human diet, particularly in milk from dairy cattle but also in beef. The activity transport by grain to pig products may also be of some importance. 8 refs, 7 figs, 25 tabs

Characterization of residual biomass from the Arequipa region for the production of biofuels

Directory of Open Access Journals (Sweden)

María Laura Stronguiló Leturia

2015-12-01

Full Text Available The aim of this work is to select residual biomass from the Arequipa Region for the production of biofuels (biodiesel, bioethanol and biogas. In each case, the initial point is a matrix based on products with residual biomass available in the region, from the agricultural and livestock sectors, information that was obtained from the regional Management of Agriculture web site. Specific factors of the resudue that will be used as raw material for each biofuel production would be considered for the selection process. For the production of biodiesel it is necessary to start from the oil extracted from oilseeds. Regarding obtaining bioethanol, it requires that the residual biomass has high percent of cellulose. With regard to the generation of biogas, we will use animal droppings. Finally, the raw materials selected are: squash and avocado seeds for biodiesel, rice chaff and deseeded corncob for bioethanol and cow and sheep droppings for biogas

Experimental and theoretical studies of the yields of residual product nuclei produced in thin Pb and Bi targets irradiated by 40 - 2600 MeV protons

International Nuclear Information System (INIS)

Titarenko, Yu. E.; Batyaev, V.F.; Karpikhin, E.I.; Zhivun, V.M.; Ignatyuk, A.V.; Lunev, V.P.; Titarenko, N.N.; Shubin, Yu.N.; Barashenkov, V.S.

2009-10-01

The Project is aimed at experimental determining and computer-aided theoretical simulating the independent and cumulative yields of residual radioactive product nuclei in high-energy protonirradiated thin targets made of high-isotopic and natural lead ( 206 Pb, 207 Pb, 208 PB, natPb) and bismuth ( 209 Bi) that are the most probable choice to be the target materials in the acceleratordriven (hybrid) systems (ADS) coupled to a high-current proton accelerator. The yields of residual product nuclei are of great importance when estimating such basic radiation-technology characteristics of the hybrid facility targets as the total target activity, the target 'poisoning', the buildup of long-lived nuclides, the α-activity, the content of low-pressure evaporated nuclides (Hg), the content of the chemically-active nuclides that drastically spoil the corrosion resistance of the facility structure materials, etc. In view of the above, the radioactive product nuclide yields from targets materials were experimentally determined using the ITEP U-10 proton accelerator in 55 measurement runs using the monoisotopic and natural lead ( 206 Pb, 207 Pb, 208 PB, natPb) and bismuth ( 209 Bi) targets within the proton energy range fractionated minutely, namely at 0.04, 0.07, 0.10, 0.8, 1.2, 1.4, 1.6, and 2.6 GeV to cover the entire range of the internuclear hadron cascading. As a result, 5972 cumulative and independent yields of residual radioactive product nuclei, whose lifetimes range from 8 minutes to 32 years, have been measured. Besides, the cross sections for the 27 Al(p,x) 24 Na and 27 Al(p,x)7Be monitor reactions have been measured at the same proton energies together with the 27 Al(n,p) 27 Mg reaction rate that characterizes the neutron background contributions in each experiment. The experimental nuclide yields are determined by the direct γ-spectrometry method. The γ-spectrometer resolution is 1.8 keV in the 1332 keV 60 Co γ-line. The experimental γ-spectra are processed by

Production and Evaluation of 236gNp and Reference Materials for Naturally Occurring Radioactive Materials

Science.gov (United States)

Larijani, Cyrus Kouroush

This thesis is based on the development of a radiochemical separation scheme capable of separating both 236gNp and 236Pu from a uranium target of natural isotopic composition ( 1 g uranium) and 200 MBq of fission decay products. The isobaric distribution of fission residues produced following the bombardment of a natural uranium target with a beam of 25 MeV protons has been evaluated. Decay analysis of thirteen isobarically distinct fission residues were carried out using high-resolution gamma-ray spectrometry at the UK National Physical Laboratory. Stoichiometric abundances were calculated via the determination of absolute activity concentrations associated with the longest-lived members of each isobaric chain. This technique was validated by computational modelling of likely sequential decay processes through an isobaric decay chain. The results were largely in agreement with previously published values for neutron bombardments on natural uranium at energies of 14 MeV. Higher relative yields of products with mass numbers A 110-130 were found, consistent with the increasing yield of these radionuclides as the bombarding energy is increased. Using literature values for the production cross-section for fusion of protons with uranium targets, it is estimated that an upper limit of approximately 250 Bq of activity from the 236Np ground state was produced in this experiment. Using a radiochemical separation scheme, Np and Pu fractions were separated from the produced fission decay products, with analyses of the target-based final reaction products made using Inductively Couple Plasma Mass Spectrometry (ICP-MS) and high-resolution alpha and gamma-ray spectrometry. In a separate research theme, reliable measurement of Naturally Occurring Radioactive Materials is of significance in order to comply with environmental regulations and for radiological protection purposes. The thesis describes the standardisation of three reference materials, namely Sand, Tuff and TiO2 which

Benchmark calculations on residue production within the EURISOL DS project. Part 1: thin targets

Energy Technology Data Exchange (ETDEWEB)

David, J.C.; Blideanu, V.; Boudard, A.; Dore, D.; Leray, S.; Rapp, B.; Ridikas, D.; Thiolliere, N

2006-12-15

We have begun this benchmark study using mass distribution data of reaction products obtained at GSI in inverse kinematics. This step has allowed us to make a first selection among 10 spallation models; in this way the first assessment of the quality of the models was obtained. Then, in a second part, experimental mass distributions for some elements, which either are interesting as radioactive ion beams or important due to the safety and radioprotection issues (alpha or gamma emitters), will be also compared to model calculations. These data have been obtained for an equivalent 0.8 or 1.0 GeV proton beam, which is approximately the proposed projectile energy. We note that in realistic thick targets the proton beam will be slowed down and some secondary particles will be produced. Therefore, the residual nuclei production at lower energies is also important. For this reason, we also performed in the third part of this work some excitation function calculations and the associated data obtained with gamma-spectroscopy to test the models in a wide projectile energy range. We conclude that INCL4/Abla and Isabel/Abla are the best model combinations which we recommend. We also note that the agreement between model and data are better with 1 GeV protons than with 100-200 MeV protons.

Controlling the Outcome of Melting Radioactive Sources in Scrap Metal: from Exclusion, Exemption and Clearance towards a 'Codex Metallarius'

Energy Technology Data Exchange (ETDEWEB)

Gonzalez, A.J., E-mail: agonzale@sede.arn.gov.ar [Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)

2011-07-15

Orphan radiation sources have been inadvertently incorporated into scrap metal and traces of radioactive residues have appeared in finished metal products causing public anxiety, despair in industry and governmental concern. The international principles of exclusion, exemption and clearance can be used to tackle this problem. They are described in detail, as they are becoming universally established for defining the scope of radiation protection regulations. However, notwithstanding the relevance of these principles, the paper suggests a straightforward professional consensus for discontinuing radiological control of commodities with minute traces of radioactive residues. The consensus should unambiguously specify a generic activity concentration in inedible commodities, including metals, below which radiological control may be effectively relinquished. A subsequent legally binding intergovernmental undertaking could resolve the current regulatory ambiguity, facilitate commercial exchange and ensure adequate public protection. For metals, it might take the form of a 'Codex Metallarius' (similar to the existing Codex Alimentarius for edible commodities) establishing a generic level of radiological acceptability for finished metal products. Furthermore, it is proposed that there should be an international convention to prevent radioactive sources becoming orphaned from regulatory control and then inadvertently appearing in trash and scrap. (author)

Radiating residues from production and consumption. On the political economy of radioactive waste; Strahlende Hinterlassenschaften aus Produktion und Konsumtion. Zur Politischen Oekonomie des Atommuells

Energy Technology Data Exchange (ETDEWEB)

Brunnengraeber, Achim; Mez, Lutz

2014-09-15

The contribution on radiating residues from production and consumption discusses the following issues: (1) Endless production of waste - not only from NPP operation but in every phase of the fuel cycle starting with uranium mining. (2) Paradoxes and polarizations: the discrepancy between the continuous production of nuclear waste and the unsolved question of final disposal is accompanying the whole nuclear energy age: the experiences show that neither technical nor geological barriers can guarantee the safe retention of fission products from the environment. (3) Private goods, public bads: the NPP owner tend to reach highest profit but want to shift the cost for waste disposal to the public; the situation in Germany is discussed in detail. (4) Conclusions and the final repository governance: the ongoing search for a final repository site in Germany demonstrates the development of the waste problem to a wicked problem.

Radioactivity metrology

International Nuclear Information System (INIS)

Legrand, J.

1979-01-01

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

Process for ultimate storage of radioactive fission products

International Nuclear Information System (INIS)

Baukal, W.; Gruenthaler, K.H.; Neumann, K.

1980-01-01

In order to exclude cracking in the cooling phase during sealing of radioactive oxidic fission products in glass melts, metallic filling elements - e.g. wires, tissues - are proposed to be incorporated in the mould before the glass melt is poured in. Especially nickel alloys with corrosion proof surface layers, e.g. titanium nitride, silicon carbide, silicon nitride, aluminium oxide, suit best. These elements reduce thermal stresses and effect high thermal conductance towards the mould wall. (UWI) [de

Production of calibration sources and/or radioactive tracers with the cyclotron CV-28

International Nuclear Information System (INIS)

Osso Junior, Joao Alberto

1995-01-01

The present stage of production of calibration sources and radioactive tracers with the Cyclotron CV-28 is described. Among the methods already developed special attention is given to the production of 57 Co, 109 Cd and 111 In. (author). 3 refs

Radioactivity of combustion residues from coal-fired power stations

International Nuclear Information System (INIS)

Vom Berg, W.; Puch, K.H.

1996-01-01

Each year in Germany, about 18 mill. t of combustion residues are produced from the combustion of bituminous coal and lignite. They are utilized to a great extent in the construction industry and in mining. During the combustion of coal, the radio-nuclides remain predominantly in the ash. The radionuclide concentration in lignite ash is within the range of that in natural soil. The combustion residues of bituminous coal contain radio-nuclides of a similar order of magnitude as also can occur in natural rock. The utilization of combustion residues in construction materials makes a negligible contribution to radiation exposure through retention in buildings. (orig.) [de

Production of petroleum bitumen by oxidation of heavy oil residue with sulfur

Science.gov (United States)

Tileuberdi, Ye.; Akkazyn, Ye. A.; Ongarbayev, Ye. K.; Imanbayev, Ye. I.; Mansurov, Z. A.

2018-03-01

In this paper production of bitumen adding elemental sulfur at oxidation of oil residue are investigated. The objects of research were distilled residue of Karazhanbas crude oil and elemental sulfur. These oil residue characterized by a low output of easy fractions and the high content of tar-asphaltene substances, therefore is the most comprehensible feedstock for producing bitumen. The sulfur is one of the oil product collected in oil extraction regions. Oxidation process of hydrocarbons carried out at temperatures from 180 up to 210 °С without addition of sulfur and with the addition of sulfur (5-10 wt. %) for 4 hours. At 200 °С oxidation of hydrocarbons with 5, 7 and 10 wt.% sulfur within 3-4 h allows receiving paving bitumen on the mark BND 200/300, BND 130/200, BN 90/130 and BN 70/30. Physical and mechanical characteristics of oxidation products with the addition of 5-7 wt. % sulfur corresponds to grade of paving bitumen BND 40/60. At the given temperature oxidized for 2.5-3 h, addition of 10 wt. % sulfur gave the products of oxidation describing on parameters of construction grades of bitumen (BN 90/10).

Radioactive waste management

International Nuclear Information System (INIS)

Blomek, D.

1980-01-01

The prospects of nuclear power development in the USA up to 2000 and the problems of the fuel cycle high-level radioactive waste processing and storage are considered. The problems of liquid and solidified radioactive waste transportation and their disposal in salt deposits and other geologic formations are discussed. It is pointed out that the main part of the high-level radioactive wastes are produced at spent fuel reprocessing plants in the form of complex aqueous mixtures. These mixtures contain the decay products of about 35 isotopes which are the nuclear fuel fission products, about 18 actinides and their daughter products as well as corrosion products of fuel cans and structural materials and chemical reagents added in the process of fuel reprocessing. The high-level radioactive waste management includes the liquid waste cooling which is necessary for the short and middle living isotope decay, separation of some most dangerous components from the waste mixture, waste solidification, their storage and disposal. The conclusion is drawn that the seccessful solution of the high-level radioactive waste management problem will permit to solve the problem of the fuel cycle radioactive waste management as a whole. The salt deposits, shales and clays are the most suitable for radioactive waste disposal [ru

Research on atmospheric radioactivity. [In French

Energy Technology Data Exchange (ETDEWEB)

Garrigue, H

1954-01-01

In flight at 2800 m, traces of radioactive particles were gathered, by means of a corona effect similar to that of Sella, and of long period, on April 24, 1954. At Puy-de-Dome (1465 m) after a fall of rain and snow on May 3 to 4, 1954, samples of the fallen residue showed very feeble radioactivity of period 10 days or more. This radioactivity of the airborne particles was independent of their probable natural electrical charge and mobility and was indicative of an atomic cloud.

Mass balances by uranium-series disequilibria in natural phosphate deposits and mine products

International Nuclear Information System (INIS)

Osmond, J.K.; Cowart, J.B.

1985-01-01

In a closed system U-238 is in radioactive equilibrium with its longer lived daughters, U-234, Th-230, and Ra-226. In a system that is open on a time scale of 10 4 to 10 5 years, as in rock weathering, the various daughters and isotopes become separated. Nevertheless, equilibrium still pertains to the total system, so that material balances between weathering components and residual products can be calculated, based on parent-daughter radioactivity ratios. The authors have applied this balancing concept to the weathering of phosphatic ores in central Florida and to phosphate mining products. In the natural system studied in Florida, the leached zones are ten times more extensive than enriched zones, and have higher concentrations of Th-230 and Ra-226 relative to U-238 and U-234. Although there are significant movements of long-lived radio-elements locally, and occasional notable disequilibria of short-lived daughters, leaching by ground water is not a major factor in the regional budget. In the mining process, uranium follows the enriched phosphate and also the clay residues. Thorium and radium follow the clay residues and the gypsum by-product. Mine effluent waters, although somewhat higher in radioactivity than natural waters, do not remove appreciable amounts of the radio-elements

The potential of residues of furfural and biogas as calcareous soil amendments for corn seed production.

Science.gov (United States)

Zhao, Yunchen; Yan, Zhibin; Qin, Jiahai; Ma, Zhijun; Zhang, Youfu; Zhang, Li

2016-04-01

Intensive corn seed production in Northwest of China produced large amounts of furfural residues, which represents higher treatment cost and environmental issue. The broad calcareous soils in the Northwest of China exhibit low organic matter content and high pH, which led to lower fertility and lower productivity. Recycling furfural residues as soil organic and nutrient amendment might be a promising agricultural practice to calcareous soils. A 3-year field study was conducted to evaluate the effects of furfural as a soil amendment on corn seed production on calcareous soil with compared to biogas residues. Soil physical-chemical properties, soil enzyme activities, and soil heavy metal concentrations were assessed in the last year after the last application. Corn yield was determined in each year. Furfural residue amendments significantly decreased soil pH and soil bulk density. Furfural residues combined with commercial fertilizers resulted in the greater cumulative on soil organic matter, total phosphorus, available phosphorus, available potassium, and cation exchange capacity than that of biogas residue. Simultaneously, urease, invertase, catalase, and alkaline phosphatase increased even at the higher furfural application rates. Maize seed yield increased even with lower furfural residue application rates. Furfural residues resulted in lower Zn concentration and higher Cd concentration than that of biogas residues. Amendment of furfural residues led to higher soil electrical conductivity (EC) than that of biogas residues. The addition of furfural residues to maize seed production may be considered to be a good strategy for recycling the waste, converting it into a potential resource as organic amendment in arid and semi-arid calcareous soils, and may help to reduce the use of mineral chemical fertilizers in these soils. However, the impact of its application on soil health needs to be established in long-term basis.

Release of radioactive fission products from BN-600 reactor untight fuel elements

International Nuclear Information System (INIS)

Osipov, S.L.; Tsikunov, A.G.; Lisitsin, E.C.

1996-01-01

The experimental data on the release of radioactive fission products from BN-600 reactor untight fuel elements are given in the report. Various groups of radionuclides: inert gases Xe, Kr, volatile Cs, J, non-volatile Nb, and La are considered. The results of calculation-experimental study of transfer and distribution of radionuclides in the reactor primary circuit, gas system and sodium coolant are considered. It is shown that some complex radioactivity transfer processes can be described by simple mathematical models. (author)

Production of ferrous sulfate from residue from the iron mining

International Nuclear Information System (INIS)

Cardoso, K.A; Riella, H.G.; Abreu, E.F.; Carvalho, E.F. Urano de; Durazzo, M.

2012-01-01

This paper was developed from a residue obtained by processing iron ore exploited by the mining company Samarco S/A. The residue was characterized and the analyses showed that it contains about 70% of the mineral hematite (Fe 2 O 3 ) and also that some economically important products could be produced. One is the ferrous sulfate that can be used in pharmaceuticals and also that can be used in the treatment of iron deficiency anemia. The iron, in addition to is importance for the industrial production of steel and parts in general, also has great biological importance in all living beings. In order to produce ferrous sulfate from the byproduct in question, it was developed a obtaining route using metallic iron as hematite reductor and sulfuric acid to form the salt. (author)

Treatment of low level radioactive liquid waste containing appreciable concentration of TBP degraded products.

Science.gov (United States)

Valsala, T P; Sonavane, M S; Kore, S G; Sonar, N L; De, Vaishali; Raghavendra, Y; Chattopadyaya, S; Dani, U; Kulkarni, Y; Changrani, R D

2011-11-30

The acidic and alkaline low level radioactive liquid waste (LLW) generated during the concentration of high level radioactive liquid waste (HLW) prior to vitrification and ion exchange treatment of intermediate level radioactive liquid waste (ILW), respectively are decontaminated by chemical co-precipitation before discharge to the environment. LLW stream generated from the ion exchange treatment of ILW contained high concentrations of carbonates, tributyl phosphate (TBP) degraded products and problematic radio nuclides like (106)Ru and (99)Tc. Presence of TBP degraded products was interfering with the co-precipitation process. In view of this a modified chemical treatment scheme was formulated for the treatment of this waste stream. By mixing the acidic LLW and alkaline LLW, the carbonates in the alkaline LLW were destroyed and the TBP degraded products got separated as a layer at the top of the vessel. By making use of the modified co-precipitation process the effluent stream (1-2 μCi/L) became dischargeable to the environment after appropriate dilution. Based on the lab scale studies about 250 m(3) of LLW was treated in the plant. The higher activity of the TBP degraded products separated was due to short lived (90)Y isotope. The cement waste product prepared using the TBP degraded product was having good chemical durability and compressive strength. Copyright © 2011 Elsevier B.V. All rights reserved.

Radiotracer studies of pesticide residues in edible oil seeds and related products

International Nuclear Information System (INIS)

1979-01-01

Ten papers were presented in which chemical pollution due to insecticides was examined in edible oil seeds and their products. They include hexachlorocyclohexane residues in groundnut; carbaryl in groundnut; maize and cotton seed products, and in lactating goats; propoxur in cocoa beans; and leptophos residues in cotton seed and its products and in lactating goats. Eight of these papers constitute separate INIS entries. Egypt, Ghana, India, Korea, Lebanon, Pakistan, the Philippines, Poland, and the Sudan participated under the coordinated research programme. The progress of the programme is reviewed, and problems and priorities for future development of the programme are identified. A number of recommendations are addressed to the Joint FAO/IAEA Secretariat

Radioactivity at the summit of Puy de Dome. [In French

Energy Technology Data Exchange (ETDEWEB)

Garrigue, H

1951-01-01

The radioactivity of the atmosphere was studied systematically by counting the disintegrations of the residue obtained by evaporating melted snow. Three separate radioactivity measurements in the atmosphere apparently reached a max. sometime in 1946.

Anaerobic digestion of microalgae residues resulting from the biodiesel production process

International Nuclear Information System (INIS)

Ehimen, E.A.; Sun, Z.F.; Carrington, C.G.; Birch, E.J.; Eaton-Rye, J.J.

2011-01-01

The recovery of methane from post transesterified microalgae residues has the potential to improve the renewability of the 'microalgae biomass to biodiesel' conversion process as well as reduce its cost and environmental impact. This paper deals with the anaerobic digestion of microalgae biomass residues (post transesterification) using semi-continuously fed reactors. The influence of substrate loading concentrations and hydraulic retention times on the specific methane yield of the anaerobically digested microalgae residues was investigated. The co-digestion of the microalgae residues with glycerol as well as the influence of temperature was also examined. It was found that the hydraulic retention period was the most significant variable affecting methane production from the residues, with periods (>5 days) corresponding to higher energy recovery. The methane yield was also improved by a reduction in the substrate loading rates, with an optimum substrate carbon to nitrogen ratio of 12.44 seen to be required for the digestion process.

Radioactive aerosols

International Nuclear Information System (INIS)

Chamberlain, A.C.

1991-01-01

Radon. Fission product aerosols. Radioiodine. Tritium. Plutonium. Mass transfer of radioactive vapours and aerosols. Studies with radioactive particles and human subjects. Index. This paper explores the environmental and health aspects of radioactive aerosols. Covers radioactive nuclides of potential concern to public health and applications to the study of boundary layer transport. Contains bibliographic references. Suitable for environmental chemistry collections in academic and research libraries

Production rates and costs of cable yarding wood residue from clearcut units

Science.gov (United States)

Chris B. LeDoux

1984-01-01

Wood residue is a little used source of fiber, chips, and fuel because harvest costs are largely unknown. This study calculates incremental production rates and costs for yarding and loading logging residue in clearcut old-growth Douglas-fir/western hemlock forests. Harvest operations were observed for two timber sales in western Oregon. Three different cable yarding...

Co-benefits of utilizing logging residues for bioenergy production: The case for East Texas, USA

International Nuclear Information System (INIS)

Gan, Jianbang; Smith, C.T.

2007-01-01

This study evaluated the co-benefits associated with the utilization of logging residues for electricity production in East Texas, USA. The benefits evaluated included the value of CO 2 emissions displaced due to substituting logging residues for coal in power generation, reductions in site preparation costs during forest regeneration, and creation of jobs and income in local communities. Based on the 2004 Forest Inventory Analysis data and a 70% biomass recovery rate, annual recoverable logging residues in East Texas were estimated at 1.3 Mt (dry). These residues, if used for electricity production, would displace about 2.44 Mt of CO 2 , valued at some 9M$ at the current CO 2 price traded at the Chicago Climate Exchange (accounting for about 2% of the stumpage value). Removing logging residues would also save $200-250 ha -1 in site preparation costs. In addition, input-output modeling revealed that logging residue procurement and electricity generation together would have a stronger ripple effect on employment than on output or value-added, with about 1340 new jobs created and 215M$ in value-added generated annually. These results offer new insights into the cost-competitiveness of forest biomass and bioenergy production. (author)

Production of no carrier added residue free /sup 22/Na

Energy Technology Data Exchange (ETDEWEB)

Britto, J L.Q. de; Bastos, M A.V.; Silva, R.F. da; Silva, A.G. da

1988-05-02

A method for the production of no carrier added and residue free /sup 22/Na, was developed via the /sup 24/Mg(d,..cap alpha..)/sup 22/Na nuclear reaction applying 14 MeV deuterons and a high current MG-Cu target. The yield for the reaction was measured and the chemical separation was performed using a Dowex 50WX8 resin in H/sup +/ form. The overall yield was higher than 98%. Residue could not be detected. All experiments were carried out at IEN's CV-28 cyclotron. (author) 13 refs.; 2 figs.

Residual Nitrite in Some Egyptian Meat Products and the Reduction Effect of Electron Beam Irradiation

OpenAIRE

Dalia A. Zahran; Gehan M.A. Kassem

2011-01-01

Nitrite, a curing agent of meat products, is a precursor of carcinogenic N-nitrosamines during processing of meat products or under human stomach conditions, as well as having its own toxicity. To investigate the residual nitrite level in meat products marketed in Egyptian markets, 160 samples of cured cooked (luncheon and frankfurter) and cured raw (oriental sausages and pastirma) meat products (40 sample each) were analyzed for residual nitrite by a spectrophotometric method. Samples were s...

Naturally occurring radioactive materials in construction integrating radiation protection in Reuse

CERN Document Server

Schroeyers, Wouter

2017-01-01

Naturally Occurring Radioactive Materials in Construction (COST Action NORM4Building) discusses the depletion of energy resources and raw materials and its huge impact not only on the building market, but also in the development of new synthetic building materials, whereby the reuse of various (waste) residue streams becomes a necessity. It is based on the outcome of COST Action TU 1301, where scientists, regulators, and representatives from industry have come together to present new findings, sharing knowledge, experiences, and technologies to stimulate research on the reuse of residues containing enhanced concentrates of natural radionuclides (NORM) in tailor-made building materials. Chapters address legislative issues, measurement, and assessment of building materials, physical and chemical aspects, from raw materials, to residues with enhanced concentrations of natural radionuclides (NORM), processes, building products containing NORM, and end-of-life and reuse requirements. Presents a holistic app...

Partial sums of lagged cross-products of AR residuals and a test for white noise

NARCIS (Netherlands)

de Gooijer, J.G.

2008-01-01

Partial sums of lagged cross-products of AR residuals are defined. By studying the sample paths of these statistics, changes in residual dependence can be detected that might be missed by statistics using only the total sum of cross-products. Also, a test statistic for white noise is proposed. It is

Deposits of naturally occurring radioactivity in production of oil and natural gas

International Nuclear Information System (INIS)

Strand, T.; Lysebo, I.; Kristensen, D.; Birovljev, A.

1997-01-01

Deposits of naturally occurring radioactive materials is an increasing problem in Norwegian oil and gas production. Activity concentration in solid-state samples and production water, and doses to workers involved in different operations off-shore, have been measured. The report also includes a discussion of different methods of monitoring and alternatives for final disposal of wastes. 154 refs

Use of MRF residue as alternative fuel in cement production.

Science.gov (United States)

Fyffe, John R; Breckel, Alex C; Townsend, Aaron K; Webber, Michael E

2016-01-01

Single-stream recycling has helped divert millions of metric tons of waste from landfills in the U.S., where recycling rates for municipal solid waste are currently over 30%. However, material recovery facilities (MRFs) that sort the municipal recycled streams do not recover 100% of the incoming material. Consequently, they landfill between 5% and 15% of total processed material as residue. This residue is primarily composed of high-energy-content non-recycled plastics and fiber. One possible end-of-life solution for these energy-dense materials is to process the residue into Solid Recovered Fuel (SRF) that can be used as an alternative energy resource capable of replacing or supplementing fuel resources such as coal, natural gas, petroleum coke, or biomass in many industrial and power production processes. This report addresses the energetic and environmental benefits and trade-offs of converting non-recycled post-consumer plastics and fiber derived from MRF residue streams into SRF for use in a cement kiln. An experimental test burn of 118 Mg of SRF in the precalciner portion of the cement kiln was conducted. The SRF was a blend of 60% MRF residue and 40% post-industrial waste products producing an estimated 60% plastic and 40% fibrous material mixture. The SRF was fed into the kiln at 0.9 Mg/h for 24h and then 1.8 Mg/h for the following 48 h. The emissions data recorded in the experimental test burn were used to perform the life-cycle analysis portion of this study. The analysis included the following steps: transportation, landfill, processing and fuel combustion at the cement kiln. The energy use and emissions at each step is tracked for the two cases: (1) The Reference Case, where MRF residue is disposed of in a landfill and the cement kiln uses coal as its fuel source, and (2) The SRF Case, in which MRF residue is processed into SRF and used to offset some portion of coal use at the cement kiln. The experimental test burn and accompanying analysis indicate

Radioactive releases from a thorium-contaminated site in Wayne, New Jersey

International Nuclear Information System (INIS)

Wang, J.; Yang, J.; Merry-Libby, P.

1985-01-01

Various residues and wastes from the production of thorium and rare earths from monazite ore are buried on a hillside in Wayne, New Jersey. In addition, contaminated materials (primarily soils) from nearby vicinity properties are being consolidated onto the Wayne site. The US Department of Energy plans to stabilize all the contaminated materials on an interim basis (20 years) until funding is available to remove them to another location. In order to evaluate the effectiveness of interim stabilization measures, pre-remedial action radioactive releases are compared to estimated releases under a reference stabilization option (one meter of soil cover). Two potential pathways are examined: (1) airborne radioactive gases (thoron and radon) and particulates, and (2) seepage into the near-surface groundwater. The relative reduction of releases into the air and groundwater for the reference stabilization option is analyzed using mathematical models for radioactive gas fluxes and atmospheric dispersion as well as groundwater transport and dispersion. The consequent health implications for nearby individuals and the general population are also estimated. Health effects due to radioactive releases are estimated to be insignificant

DIRECTIONS FOR THE RECOVERY OF AGRICULTURAL PRODUCTION ON RADIOACTIVELY CONTAMINATED LANDS

Directory of Open Access Journals (Sweden)

Kustovska O.V.

2016-05-01

Full Text Available Effective management of agricultural production in the Polesie Ukraine traditionally was complicated through the low natural land fertility, their high acidity, perevolotsky valley. During the centrally planned economic system that the natural contrast of the Polesie land had been somewhat neglected by the state through differentiation of purchase prices for agricultural products, which gave the possibility of redistribution of the rent in favor of the farms with poorer land. With transition to market relations the role of the state, and hence the possibility of its influence on this situation has changed dramatically. Economic conditions have become more profitable for the farmers that are occupying the best lands. However, the situation in the regions has not yet been investigated systematically taking into account the modern complex socio-economic processes and phenomena caused by increased environmental stress on land resources. One of the most pernicious environmental effects of the Chernobyl accident was radioactive contamination of agricultural land, defined in the final stage of transfer of radionuclides in the human body and further irradiation. The main danger of the accumulation by plants of radionuclides lies in the fact that they are a major link in the migratory chain of transmission of radionuclides to the more radiosensitive species and, above all, human. Economic feature of agricultural production in the study area is insufficient pricesambien, transformation of land use, violations of industrial-economic relations, the structure of agricultural production, changes in the natural-cost structure commodity products, the reform of the organizational structure of agricultural production. In the farms located in contaminated areas, the necessary conversion of dairy cattle for meat. In conditions of high pollution, the production of milk requires a serious sanitary objections in that time, as meat production is more environmentally

Problems concerning food production, supply and use caused by radioactive deposition: A study directed towards needs for early decision making after radioactive fallout

International Nuclear Information System (INIS)

Bergman, R.

1995-12-01

The primary aim of this study is to analyze and describe how a radioactive deposition after nuclear weapons employment outside Sweden would affect the domestic food production in a short time perspective and in the sequence of events from primary production over processing and transport to food consumption. The study is an attempt at a comprehensive treatment of knowledge needed as a basis for decisions on operative issues, often of a time-urgent nature. Actions to alleviate the problems pertinent to the food supply in the event of radioactive fallout are also discussed, although without any claim of exhaustive coverage. Other aspects, as the economical consequences of the disturbances due to the fallout situation (or of possible counteractions) are not dealt with, however. With certain restrictions mentioned in the text the results are also applicable in connection with radioactive deposition caused by accidental release from a nuclear power plant. 60 refs, 32 figs

Production of radioactive molecular beams for CERN-ISOLDE

CERN Document Server

AUTHOR|(SzGeCERN)703149; Kröll, Thorsten

SOLDE, the Isotope Separation On-Line facility, at CERN is a leading facility for the production of beams of exotic radioactive isotopes. Currently over 1000 different isotopes with half lives down to milliseconds can be extracted with beam intensities of up to 10^11 ions per second. However, due to the reactive target environment not all isotopes are extractable in sufficient amounts. In this work the extraction of short lived carbon and boron isotopes is investigated. Therefore a variety of experimental and computanional techniques have been used.

Management of radioactive waste from 99Mo production by nuclear fission

International Nuclear Information System (INIS)

Rego, Maria Eugenia de Melo

2013-01-01

Brazil intends to build a facility for the 99 Mo production through 235 U fission, once this radioisotope is largely used in nuclear medicine. This study aimed at estimating the physical, chemical and radiological characteristics of radioactive waste expected to be generated in that facility, and to provide theoretical subsides that can be used on the definition of a proper waste management system. Two production scenarios were established and the radioisotope inventories of the wastes were calculated by Scale®. From the chemical processing of the uranium targets the wastes were characterized on their chemical and radiological features. MicroShield® was used to determine the activity concentrations up to three months of 99 Mo production. In addition, this work presents dose rate calculation for several sizes of shielding and different amount of wastes, collected in a proper package for in-site transportation. Radionuclides responsible for higher doses were identified in order to facilitate choosing the most appropriate method for managing the wastes after their chemical separation and before their storage. These results are part of what is expected on radioactive wastes at a 99 Mo production facility and might help on the development of the waste management planning for that facility. (author)

Studies of radioactivity from nuclear explosions for peaceful purposes

Energy Technology Data Exchange (ETDEWEB)

Siddons, R A [AWRE, Aldermaston (United Kingdom)

1970-05-01

Estimates are made of the extent and duration of hazards from radioactivity to the general public due to fallout from a cratering explosion. The nuclear explosive is assumed to be 'clean' in the sense that only a small fraction of the yield is derived from fission. Hypothetical examples take an explosive of total yield 100 kT, of which 10 kT, 1 kT and zero - the ultimate in cleanliness - are derived from fission. The maximum permitted level to the public is taken as 0.5 rem in a period of one year. Sources of activity considered are fission products, residual thermonuclear material (tritium), neutron induced activity in the device materials and neutron induced activity in the surrounding rock. Estimates of the production are made, and are associated with a distribution function derived from the Sedan fallout measurements. The hazards from radioactivity associated with the creation of a storage reservoir for natural gas have also been considered. In this case the main problem is contamination of the product by tritium left in the chimney. The possibility of flushing out this tritium with water is discussed. (author)

Studies of radioactivity from nuclear explosions for peaceful purposes

International Nuclear Information System (INIS)

Siddons, R.A.

1970-01-01

Estimates are made of the extent and duration of hazards from radioactivity to the general public due to fallout from a cratering explosion. The nuclear explosive is assumed to be 'clean' in the sense that only a small fraction of the yield is derived from fission. Hypothetical examples take an explosive of total yield 100 kT, of which 10 kT, 1 kT and zero - the ultimate in cleanliness - are derived from fission. The maximum permitted level to the public is taken as 0.5 rem in a period of one year. Sources of activity considered are fission products, residual thermonuclear material (tritium), neutron induced activity in the device materials and neutron induced activity in the surrounding rock. Estimates of the production are made, and are associated with a distribution function derived from the Sedan fallout measurements. The hazards from radioactivity associated with the creation of a storage reservoir for natural gas have also been considered. In this case the main problem is contamination of the product by tritium left in the chimney. The possibility of flushing out this tritium with water is discussed. (author)

The radioactive waste management at IAEA laboratories

International Nuclear Information System (INIS)

Deron, S.; Ouvrard, R.; Hartmann, R.; Klose, H.

1992-10-01

The report gives a brief description of the nature of the radioactive wastes generated at the IAEA Laboratories in Seibersdorf, their origin and composition, their management and monitoring. The management of the radioactive waste produced at IAEA Laboratories in Seibersdorf is governed by the Technical Agreements of 1985 between the IAEA and the Austrian Health Ministry. In the period of 1982 to 1991 waste containers of low activity and radiotoxicity generated at laboratories other than the Safeguards Analytical Laboratory (SAL) were transferred to the FZS waste treatment and storage plant: The total activity contained in these drums amounted to < 65 MBq alpha activity; < 1030 MBq beta activity; < 2900 MBq gamma activity. The radioactive waste generated at SAL and transferred to the FZs during the same period included. Uranium contaminated solid burnable waste in 200 1 drums, uranium contaminated solid unburnable waste in 200 1 drums, uranium contaminated liquid unburnable waste in 30 1 bottles, plutonium contaminated solid unburnable waste in 200 1 drums. In the same period SAL received a total of 146 Kg uranium and 812 g plutonium and exported out of Austria, unused residues of samples. The balance, i.e.: uranium 39 kg, plutonium 133 g constitutes the increase of the inventory of reference materials, and unused residues awaiting export, accumulated at SAL and SIL fissile store as a result of SAL operation during this 10 year period. The IAEA reexports all unused residues of samples of radioactive and fissile materials analyzed at his laboratories, so that the amount of radioactive materials ending in the wastes treated and stored at FZS is kept to a minimum. 5 refs, 7 figs, 3 tabs

Technical feasibility and carbon footprint of biochar co-production with tomato plant residue.

Science.gov (United States)

Llorach-Massana, Pere; Lopez-Capel, Elisa; Peña, Javier; Rieradevall, Joan; Montero, Juan Ignacio; Puy, Neus

2017-09-01

World tomato production is in the increase, generating large amounts of organic agricultural waste, which are currently incinerated or composted, releasing CO 2 into the atmosphere. Organic waste is not only produced from conventional but also urban agricultural practices due recently gained popularity. An alternative to current waste management practices and carbon sequestration opportunity is the production of biochar (thermally converted biomass) from tomato plant residues and use as a soil amendment. To address the real contribution of biochar for greenhouse gas mitigation, it is necessary to assess the whole life cycle from the production of the tomato biomass feedstock to the actual distribution and utilisation of the biochar produced in a regional context. This study is the first step to determine the technical and environmental potential of producing biochar from tomato plant (Solanum lycopersicum arawak variety) waste biomass and utilisation as a soil amendment. The study includes the characterisation of tomato plant residue as biochar feedstock (cellulose, hemicellulose, lignin and metal content); feedstock thermal stability; and the carbon footprint of biochar production under urban agriculture at pilot and small-scale plant, and conventional agriculture at large-scale plant. Tomato plant residue is a potentially suitable biochar feedstock under current European Certification based on its lignin content (19.7%) and low metal concentration. Biomass conversion yields of over 40%, 50% carbon stabilization and low pyrolysis temperature conditions (350-400°C) would be required for biochar production to sequester carbon under urban pilot scale conditions; while large-scale biochar production from conventional agricultural practices have not the potential to sequestrate carbon because its logistics, which could be improved. Therefore, the diversion of tomato biomass waste residue from incineration or composting to biochar production for use as a soil amendment

Standard guide for radioactive pathway methodology for release of sites following decommissioning

International Nuclear Information System (INIS)

Anon.

1989-01-01

The purpose of this guide is to provide guidance in determining site-specific conversion factors for translating between dose limits and residual radioactive contamination levels on equipment structures, and land areas. This guide is to serve as a guide to acceptable methodology for translating the yet to be determined dose limits into allowable levels of residual radioactive materials that can be left at a site following decommissioning

Environmental toxicity and radioactivity assessment of a titanium-processing residue with potential for environmental use.

Science.gov (United States)

Wendling, Laura A; Binet, Monique T; Yuan, Zheng; Gissi, Francesca; Koppel, Darren J; Adams, Merrin S

2013-07-01

Thorough examination of the physicochemical characteristics of a Ti-processing residue was undertaken, including mineralogical, geochemical, and radiochemical characterization, and an investigation of the environmental toxicity of soft-water leachate generated from the residue. Concentrations of most metals measured in the leachate were low; thus, the residue is unlikely to leach high levels of potentially toxic elements on exposure to low-ionic strength natural waters. Relative to stringent ecosystem health-based guidelines, only chromium concentrations in the leachate exceeded guideline concentrations for 95% species protection; however, sulfate was present at concentrations known to cause toxicity. It is likely that the high concentration of calcium and extreme water hardness of the leachate reduced the bioavailability of some elements. Geochemical modeling of the leachate indicated that calcium and sulfate concentrations were largely controlled by gypsum mineral dissolution. The leachate was not toxic to the microalga Chlorella sp., the cladoceran Ceriodaphnia dubia, or the estuarine bacterium Vibrio fischeri. The Ti-processing residue exhibited an absorbed dose rate of 186 nGy/h, equivalent to an annual dose of 1.63 mGy and an annual effective dose of 0.326 mGy. In summary, the results indicate that the Ti-processing residue examined is suitable for productive use as an environmental amendment following 10 to 100 times dilution to ameliorate potential toxic effects due to chromium or sulfate. Copyright © 2013 SETAC.

Assessing the Availability of Wood Residues and Residue Markets in Virginia

OpenAIRE

Alderman, Delton R. Jr.

1998-01-01

A statewide mail survey of primary and secondary wood product manufacturers was undertaken to quantify the production and consumption of wood residues in Virginia. Two hundred and sixty-six wood product manufacturers responded to the study and they provided information on the production, consumption, markets, income or disposal costs, and disposal methods of wood residues. Hardwood and pine sawmills produce approximately 66 percent of Virginia's wood residues. Virginia's wood product man...

A two-stage bioprocess for hydrogen and methane production from rice straw bioethanol residues.

Science.gov (United States)

Cheng, Hai-Hsuan; Whang, Liang-Ming; Wu, Chao-Wei; Chung, Man-Chien

2012-06-01

This study evaluates a two-stage bioprocess for recovering hydrogen and methane while treating organic residues of fermentative bioethanol from rice straw. The obtained results indicate that controlling a proper volumetric loading rate, substrate-to-biomass ratio, or F/M ratio is important to maximizing biohydrogen production from rice straw bioethanol residues. Clostridium tyrobutyricum, the identified major hydrogen-producing bacteria enriched in the hydrogen bioreactor, is likely utilizing lactate and acetate for biohydrogen production. The occurrence of acetogenesis during biohydrogen fermentation may reduce the B/A ratio and lead to a lower hydrogen production. Organic residues remained in the effluent of hydrogen bioreactor can be effectively converted to methane with a rate of 2.8 mmol CH(4)/gVSS/h at VLR of 4.6 kg COD/m(3)/d. Finally, approximately 75% of COD in rice straw bioethanol residues can be removed and among that 1.3% and 66.1% of COD can be recovered in the forms of hydrogen and methane, respectively. Copyright © 2012 Elsevier Ltd. All rights reserved.

Safety aspects in handling naturally occurring radioactive material (NORM) at geothermal usage; Arbeitssicherheitstechnische Aspekte im Umgang mit NORM bei der Geothermie

Energy Technology Data Exchange (ETDEWEB)

Kettler, John; Havenith, Andreas [Aachen Institute for Nuclear Training GmbH (Germany); Hirsch, Marius

2015-06-01

This article describes potential radiological hazards, which originate through the mobilization of naturally occurring radioactive material (NORM) from deep geological deposits. The process of geothermal usage requires the artifical lift of injected fluids, which may also transport undesired by-products to the surface. As a result these by-products may precipitate, form residues and require radiation protection measures to cope with this task.

Accumulative effect of food residues on intestinal gas production.

Science.gov (United States)

Mego, M; Accarino, A; Malagelada, J-R; Guarner, F; Azpiroz, F

2015-11-01

As mean transit time in the colon is longer than the interval between meals, several consecutive meal loads accumulate, and contribute to colonic biomass. Our aim was to determine the summation effect of fermentable food residues on intestinal gas production. In eight healthy subjects, the volume of endogenous intestinal gas produced in the intestine over a 4-h period was measured by means of a wash-out technique, using an exogenous gas infusion into the jejunum (24 mL/min) and collection of the effluent via a rectal Foley catheter. The exogenous gas infused was labeled (5% SF6 ) to calculate the proportion of endogenous intestinal gas evacuated. In each subject, four experiments were performed ≥1 week apart combining a 1-day high- or low-flatulogenic diet with a test meal or fast. Basal conditions: on the low-flatulogenic diet, intestinal gas production during fasting over the 4-h study period was 609 ± 63 mL. Effect of diet: during fasting, intestinal gas production on the high-flatulogenic diet was 370 ± 146 mL greater than on the low-flatulogenic diet (p = 0.040). Effect of test meal: on the low-flatulogenic diet, intestinal gas production after the test meal was 681 ± 114 mL greater than during fasting (p = 0.001); a similar effect was observed on the high-flatulogenic diet (599 ± 174 mL more intestinal gas production after the test meal than during fasting; p = 0.021). Our data demonstrate temporal summation effects of food residues on intestinal gas production. Hence, intestinal gas production depends on pre-existing and on recent colonic loads of fermentable foodstuffs. © 2015 John Wiley & Sons Ltd.

Natural Gamma Emitters after a Selective Chemical Separation of a TENORM residue: Preliminary Results

International Nuclear Information System (INIS)

Alves de Freitas, Antonio; Abrao, Alcidio; Godoy dos Santos, Adir Janete; Pecequilo, Brigitte Roxana Soreanu

2008-01-01

An analytical procedure was established in order to obtain selective fractions containing radium isotopes ( 228 Ra), thorium ( 232 Th), and rare earths from RETOTER (REsiduo de TOrio e TErras Raras), a solid residue rich in rare earth elements, thorium isotopes and small amount of natural uranium generated from the operation of a thorium pilot plant for purification and production of pure thorium nitrate at IPEN -CNEN/SP. The paper presents preliminary results of 228 Ra, 226 Ra, 238 U, 210 Pb, and 40 K concentrations in the selective fractions and total residue determined by high-resolution gamma spectroscopy, considering radioactive equilibrium of the samples

From the discovery of radioactivity to the production of radioactive beams

International Nuclear Information System (INIS)

Bimbot, R.

1999-01-01

The evolution of the projectiles used to explore the nucleus influenced strongly the development of Nuclear Physics. The alpha particles from radioactivity were the projectiles mostly used up to the second world war. This period was marked by fundamental discoveries, as those of artificial radioactivity and of fission. From the 1930's to 1070, light accelerated particles (electrons, protons, deuterons, isotopes of helium) became universally used. A third period began in the 1960's with the emergence of heavy ion accelerators, the use of which led to a true revolution in the study of nuclear matter. Finally, the fourth period started in 1985 when the first secondary beams of radioactive nuclei were produced, and opened new ways in physics. (authors)

Ethanol production from Lycoris radiata Herbert (Amarylllidaceae) residues as a new resource

International Nuclear Information System (INIS)

Liu, Shuangping; Ding, Zhongyang; Zhang, Liang; Gu, Zhenghua; Wang, Xiaolan; Sun, Xiaojun; Shi, Guiyang

2012-01-01

The large quantities of Lycoris radiata Herbert (Amarylllidaceae) residues, left after the extraction of alkaloids from the bulbs, could threaten the environment if not properly disposed. Therefore, the aim of this research is to investigate the feasibility of bioconversion of L. radiata Herbert residues to ethanol through batch fermentation. In L. radiata Herbert residues, the average contents (g kg −1 ) of non-structural carbohydrates, crude fiber, crude protein, ash, and lignin are 485.1, 177.3, 124.7, 108.9, and 91.0, respectively. Five commercial enzymes (β-glucanase, pectinase, xylanase, phytase and cellulase) were employed in pretreatment process and ethanol bioconversion was evaluated with three yeasts (Saccharomyces cerevisiae, osmotolerant S. cerevisiae and genetically engineered S. cerevisiae constructed to use cellobiose). The results showed that pretreament by β-glucanase successfully facilitated the penetration of α-amylase into ground material. After residues pretreatment by 10 g kg −1 of β-glucanase for 14 h at 50 °C, the viscosity decreased from 1135 to 59 Pa·s which was equivalent to that obtained by the combined whole five enzymes. Further experiments proved that osmotolerant S. cerevisiae was desirable for ethanol production from Lycoris radiate Herbert residues. The results are helpful to develop non-grain bioethanol production. -- Highlights: ► The residuals from Lycoris radiata Herbert bulbs were able to generate 55% ethanol concentrations by yeast fermentation. ► Treatment with xylanase significantly reduced the viscosity more than 10-fold and improved fermentable sugars by ∼35%. ► An osmotolerant Saccharomyces cerevisiae strain that showed improved fermentation rates was identified.

Biogas and mineral fertiliser production from plant residues of phytoremediation

Energy Technology Data Exchange (ETDEWEB)

Chu, Thi Thu Ha

2011-07-01

The former uranium mining site in Ronneburg, Thuringia, Germany was known as a big source of uranium with more than 113,000 tons of uranium mined from 1946 to 1990. This area has been remediated since the nineties of the last century. However, nowadays the site in Ronneburg is still specially considered because of the heterogeneous contamination by many heavy metals and the vegetation can be affected. Three plant species including Indian mustard - Brassica juncea L., triticale - x. Triticosecale Wittmaek and sunflower - Helianthus annuus L. were seeded as accumulators of heavy metals and radionuclides in the phytoremediation process in 2009 and 2010 in Ronneburg. The subsequent utilization of the plant residues after phytoremediation is of special consideration. Batch fermentation of harvested plant materials under the mesophilic condition showed that all of the investigated plant materials had much higher biogas production than liquid cow manure except triticale root, of which biogas yield per volatile solid was not significantly higher than the one of sludge. The highest biogas yields (311 L{sub N}/kg FM and 807 L{sub N}/kg VS) were achieved from the spica of triticale after 42 days of retention of anaerobic digestion. Triticale shoot residues generated higher biogas and methane yields than the previously reported triticale materials that were harvested from the uncontaminated soil Triticale was considered as the highest potential species in biogas production, beside the best growth ability on the acidic soil at the test field site with highest biomass production. Biogas yield of Indian mustard shoot was also high but dramatically varied from 2009 to 2010. Digestates after anaerobic digestion of plant residues contained various macronutrients such as nitrogen, potassium, phosphorus and sulphur, and various micronutrients such as iron, manganes, zinc, etc. The accumulation levels of heavy metals in the investigated plant materials were not the hindrance factors

Production of radioactive molecular beams for CERN-ISOLDE

Energy Technology Data Exchange (ETDEWEB)

Seiffert, Christoph

2015-06-15

ISOLDE, the Isotope Separation On-Line facility, at CERN is a leading facility for the production of beams of exotic radioactive isotopes. Currently over 1000 different isotopes with half lives down to milliseconds can be extracted with beam intensities of up to 10{sup 11} ions per second. However, due to the reactive target environment not all isotopes are extractable in sufficient amounts. In this work the extraction of short lived carbon and boron isotopes is investigated. Therefore a variety of experimental and computational techniques have been used.

Effects of processing treatment on pesticide residues in fruits and their products

International Nuclear Information System (INIS)

Mao Xuefei; Jiao Bining; Fu Chenmei; Qian Yongzhong; Wang Jing

2008-01-01

The influence of processing treatments on pesticide residues in fruits and their products was reviewed. The effects on pesticide residues and relative control treatments for each processing step, including peeling, washing, sterilization, juicing, clarification, filtration, drying and fermentation, were discussed, respectively. Meanwhile we analyzed the future development prospectin of this field, in order to provide some suggestions for commercial fruit industry and consumers' health. (authors)

Fermentative utilization of glycerol residue for the production of acetic acid

Science.gov (United States)

Irvan; Trisakti, B.; Hasibuan, R.; Joli, M.

2018-02-01

Glycerol residue, frequently known as pitch, is a waste produced from the downstream product of crude glycerine distillation. With the increasing need of pure glycerine in the world, the glycerol residue produced is also increasing. Glycerol residue is a solid waste at room temperature, highly alkaline (pH > 13), corrosive, and categorized as hazardous and poisonous waste. In this research, acetic acid was produced from glycerol residue through the anaerobic fermentation process by using purple non-sulphur photosynthetic bacteria. The purpose of this study was to find out the influence of concentration change of glycerol residue on time and to find out the possibility of glycerol residue to be utilized as acetic acid. In this research, at first 400 g of glycerol residue was diluted with 200 ml of distilled water to change the glycerine phase, from solid to liquid at room temperature, acidified by using hydrochloric acid until pH 2. The top layer formed was fatty acid and triglycerides that should be removed. Meanwhile, the bottom layer was diluted glycerol residue which was then neutralized with caustic soda. To produce acetic acid, glycerol residue with various concentrations, salt, and purple non-sulphur photosynthetic bacteria were put together into a 100 ml bottle which had been previously sterilized, then incubated for four weeks under the light of 40-watt bulb. The result showed that on the 28th day of fermentation, the produced acetic acid were 0.28, 1.85, and 0.2% (w/w) by using glycerine with the concentration of 0.5, 1.0, and 1.5% (w/w), respectively.

Growth and Productivity of Response of Hybrid Rice to Application of Animal Manures, Plant Residues and Phosphorus

Directory of Open Access Journals (Sweden)

Dr. Amanullah

2016-10-01

Full Text Available The objective of this research was to evaluate the impact of organic sources (animal manures vs. plant residues at the rate of 10 t ha-1 each on the productivity profitability of small land rice (Oryza sativa L. grower under different levels of phosphorus (0, 30, 60 and 90 kg P ha-1 fertilization. Two separate field experiments were conducted. In experiment (1, impact of three animal manures sources (cattle, sheep & poultry manures and P levels was studied along with one control plot (no animal manure and P applied as check was investigated. In experiment (2, three plant residues sources (peach leaves, garlic residues & wheat straw and P levels was studied along with one control plot (no plant residues and P applied as check. Both the experiments were carried out on small land farmer field at District Swabi, Khyber Pakhtunkhwa Province (Northwest Pakistan during summer 2015. The results revealed that in both experiments the control plot had significantly (p≤0.05 less productivity than the average of all treated plots with organic sources and P level. The increase in P levels in both experiments (animal manure vs. plant residues had resulted in higher rice productivity (90 = 60 > 30 > 0 kg P ha-1. In the experiment under animal manures, application of poultry manure increased rice productivity as compared with sheep and cattle manures (poultry > sheep > cattle manures. In the experiment under plant residues, application of peach leaves or garlic resides had higher rice productivity over wheat straw (peach leaves = garlic residues > wheat straw. On the average, the rice grown under animal manures produced about 20% higher grain yield than the rice grown under crop residues. We concluded from this study that application of 90 kg P ha-1 along with combined application of animal manures especially poultry manure could increase rice productivity. We conclude from this study that application of 90 kg P ha-1 along with combined application of animal

Inulin-125I-tyramine, an improved residualizing label for studies on sites of catabolism of circulating proteins

International Nuclear Information System (INIS)

Maxwell, J.L.; Baynes, J.W.; Thorpe, S.R.

1988-01-01

Residualizing labels for protein, such as dilactitol-125I-tyramine (125I-DLT) and cellobiitol-125I-tyramine, have been used to identify the tissue and cellular sites of catabolism of long-lived plasma proteins, such as albumin, immunoglobulins, and lipoproteins. The radioactive degradation products formed from labeled proteins are relatively large, hydrophilic, resistant to lysosomal hydrolases, and accumulate in lysosomes in the cells involved in degradation of the carrier protein. However, the gradual loss of the catabolites from cells (t1/2 approximately 2 days) has limited the usefulness of residualizing labels in studies on longer lived proteins. We describe here a higher molecular weight (Mr approximately 5000), more efficient residualizing glycoconjugate label, inulin-125I-tyramine (125I-InTn). Attachment of 125I-InTn had no effect on the plasma half-life or tissue sites of catabolism of asialofetuin, fetuin, or rat serum albumin in the rat. The half-life for hepatic retention of degradation products from 125I-InTn-labeled asialofetuin was 5 days, compared to 2.3 days for 125I-DLT-labeled asialofetuin. The whole body half-lives for radioactivity from 125I-InTn-, 125I-DLT-, and 125I-labeled rat serum albumin were 7.5, 4.3, and 2.2 days, respectively. The tissue distribution of degradation products from 125I-InTn-labeled proteins agreed with results of previous studies using 125I-DLT, except that a greater fraction of total degradation products was recovered in tissues. Kinetic analyses indicated that the average half-life for retention of 125I-InTn degradation products in tissues is approximately 5 days and suggested that in vivo there are both slow and rapid routes for release of degradation products from cells

Long-term trend of radioactive contamination of food products in Bulgaria after the Chernobyl accident

International Nuclear Information System (INIS)

Kirov, K.; Marinov, V.; Naidenov, M.

1997-01-01

Results which characterize the dynamics for the power of radioactive contamination of foods in the Bulgaria with Cesium radionuclides from May 1986 to December 1995 are presented. It was done for motivation of some conclusions during the progress of radiation situation in Bulgaria after the Chernobyl accident. The data are compared with Maximum residues limits (MRL) of our country as well as that of international organizations. They are compared with the background contamination of foods descended from regions affected after experimental nuclear explosion till 1963 too

Hungarian situation of the technologically enhanced naturally occuring radioactive materials

International Nuclear Information System (INIS)

Juhasz, L.; Szerbin, P.; Czoch, I.

2003-01-01

Full text: In Hungary, the main goal is that the Hungarian regulations should meet with the EU Directive No. 96/29. For this aim, a surveying project has been launched in order to collect all relevant information about the Hungarian TENORM situation. This surveying programme covers a lot of data collection (work activities, disposal places, residue quantities) and radiological measurements on the TENORM site. The Hungarian situation of TENORM definitely differs from other countries in the aspect of occurrence forms of natural sources (or in the imported raw materials), in the quantities of exploitation, in the level of the radioactivity and in the applied technological processes. Firstly, those work activities have been choosen where the huge amount of residues have been produced. The other criteria is that the activity concentration in a great portion of the given residues is much higher than the average activity concentration of the typical Hungarian soil. After filtering and ranking, the following main activities enhanced the radioactivity level are left: uranium mining and milling, coal mining, coal firing in power plants, bauxite mining and aluminous earth production. At the uranium mining and milling area the uranium content of residues ranges from 20 to 70 g t -1 , and above those the dose rate is 0.4-10 μSv h -1 . The waste rock piles and heaps for leaching were restored and the remediation of tailings ponds is still under way. In the mountain Mecsek and on the territory from the highland Balaton to the mountain Vertes, the radioactivity level of the coals is 10-50 times higher than the worldwide average. The coal fired plants have piled up in the order of magnitude of 10 million tons of fly ash, bottom ash and slag in ponds around the plants. The radioactivity of U-238 series of ash and slag is in the range from 200 to 2000 Bq·kg -1 . The radionuclide concentrations of bauxite ores range from 200 to 300 Bq·kg -1 . At the refining factories, a lot of red

Biochar from different residues on soil properties and common bean production

Directory of Open Access Journals (Sweden)

Isley Cristiellem Bicalho da Silva

Full Text Available ABSTRACT: The production of biochar from organic residues promises to be an interesting strategy for the management of organic waste. To assess the effect of biochar on soil properties and the production and nutrition of common bean (Phaseolus vulgaris L., three simultaneous experiments were conducted in a greenhouse with different biochar from organic residues (rice husk, sawdust, and sorghum silage used as filtration material for swine biofertilizer. In each experiment the treatments consisted of five different biochar concentrations (0, 25, 50, 75 and 100 L m−3, arranged in a completely randomized design, with four repetitions. In the experiments, the use of biochar increased soil pH, cation exchange capacity, nutrient availability in the soil, and nutrient accumulation in grains. The biochar concentrations corresponding to the maximum production of grain dry matter of bean plants were 100, 68, and 71 L m−3 for biochar from rice husk filter (BRHF, biochar from sawdust filter (BSF, and biochar from sorghum silage filter (BSSF, respectively.

Influence of turkey meat on residual nitrite in cured meat products.

Science.gov (United States)

Kilic, B; Cassens, R G; Borchert, L L

2001-02-01

A response surface experimental design was employed to estimate residual nitrite level at various initial nitrite concentrations, percent turkey meat in the formula, and heat quantity (F) values using a typical wiener as the test system. Pork and mechanically separated turkey were used as the meat ingredients. Residual nitrite and pH were measured at day 1, 7 days, 14 days, and 49 days after processing. Protein, fat, salt, moisture, and CIE (L*a*b*) color values were also determined. Results showed that the effect of turkey meat on residual nitrite level was significant (P meat in the formula resulted in lower residual nitrite levels at a fixed pH. The residual nitrite level was initially proportional to initial nitrite concentration, but it became a nonsignificant factor during longer storage time. Differences in heat quantity had a significant effect (P nitrite level initially. Greater heat quantity decreased residual nitrite level in finished cured meat products at a fixed pH. However, this effect became nonsignificant during longer storage. Reduction of residual nitrite in wieners because of turkey meat addition at a fixed pH was due to characteristics of the turkey tissue, but the mechanism of action remains unknown. It was also established that commercial wieners had a higher pH if poultry meat was included in the formulation.

JUSTIFICATION FOR THE RADIOLOGICAL CRITERIA FOR THE USE OF AREAS WITH RESIDUAL RADIOACTIVE CONTAMINATION BASED ON THE DOSE APPROACH

Directory of Open Access Journals (Sweden)

V. Yu. Golikov

2017-01-01

Full Text Available The article presents a methodology for assessing the radiological criteria for the use of the territory (a land plot with buildings with residual radioactive contamination from the so-called “green area”, i.e., complete release from radiation control until a number of restrictions are imposed on the use of the territory. In accordance with the further use of the territory, a range of scenarios and pathways for the exposure of the population was considered. A set of models and their parameters, corresponding to the number of the considered pathways of exposure, was defined. Assuming a uniform distribution of a radionuclide with a unit concentration in the source zone, the distribution of effective doses for the population living in the territory with the residual radioactive contamination for different irradiation scenarios was calculated by stochastic modeling, 95% of the quantile of which was attributed to the dose in the representatives of the critical population group. Next, the value of radiological criteria, depending on the implemented scenario, was determined as the ratio of the dose constraint EL = 0,3 mSv/yr and 95% quantile in the distribution of the effective dose from a unit contamination. The numerical values of radiological criteria for the presence of radionuclides in the soil are presented, both for the radiation scenarios that correspond to the permanent residence of the population in the contaminated territory and for recreational use. A further consideration is given to the so-called worker scenario, which corresponds to the limited time spent on the contaminated territory and the simultaneous effects of radionuclides contained both in the soil and in the construction of the buildings. A comparison of the results of the own calculations with the data of other authors was carried out.

Radioactive demonstration of DWPF product control strategy

International Nuclear Information System (INIS)

Andrews, M.K.; Bibler, N.E.

1994-01-01

The Defense Waste Processing Facility at the Savannah River Site (SRS) will vitrify high-level nuclear waste into borosilicate glass. The waste will be mixed with properly formulated glass-making frit and fed to a melter at 1150 degrees C. Process reliability and product quality are ensured by proper control of the melter feed composition. The effectiveness of the product and process control strategies that will be utilized by the Defense Waste Processing Facility (DWPF) was demonstrated during a campaign in the Shielded Cells Facility of the Savannah River Technology Center (SRTC). The remotely operated process included the preparation of the melter feed, vitrification in a slurry-fed 1/100th scale melter an analysis of the glass product both for its composition an durability. The campaign processed approximately 10 kg (on a dry basis) of radioactive sludge from Tank 51. This sludge is representative of the first batch of sludge that will be sent to the DWPF for immobilization into borosilicate glass. Additions to the sludge were made based on calculations using the Product Composition Control System (PCCS). Analysis of the glass produced during the campaign showed that a durable glass was produced with a composition very close to that predicted using the PCCS. 10 refs., 4 tabs

Polarized secondary radioactive beams

International Nuclear Information System (INIS)

Zaika, N.I.

1992-01-01

Three methods of polarized radioactive nuclei beam production: a) a method nuclear interaction of the non-polarized or polarized charged projectiles with target nuclei; b) a method of polarization of stopped reaction radioactive products in a special polarized ion source with than following acceleration; c) a polarization of radioactive nuclei circulating in a storage ring are considered. Possible life times of the radioactive ions for these methods are determined. General schemes of the polarization method realizations and depolarization problems are discussed

The production of accelerated radioactive ion beams

International Nuclear Information System (INIS)

Olsen, D.K.

1993-01-01

During the last few years, substantial work has been done and interest developed in the scientific opportunities available with accelerated radioactive ion beams (RIBs) for nuclear physics, astrophysics, and applied research. This interest has led to the construction, development, and proposed development of both first- and second-generation RIB facilities in Asia, North America, and Europe; international conferences on RIBs at Berkeley and Louvain-la-Neuve; and many workshops on specific aspects of RIB production and science. This paper provides a discussion of both the projectile fragmentation, PF, and isotope separator on-line, ISOL, approach to RIB production with particular emphasis on the latter approach, which employs a postaccelerator and is most suitable for nuclear structure physics. The existing, under construction, and proposed facilities worldwide are discussed. The paper draws heavily from the CERN ISOLDE work, the North American IsoSpin Laboratory (ISL) study, and the operating first-generation RIB facility at Louvain-la-Neuve, and the first-generation RIB project currently being constructed at ORNL

Colloquium C.L.I. operators and others... the becoming of radioactive products after use

International Nuclear Information System (INIS)

Ancelin, G.; Artus, J.C.; Atteia, M.; Audebert, P.; Ballat, J.; Balle, St.; Bardols, M.; Basse-Cathalinat, B.; Baylet, J.M.; Bazot, G.; Beaufils, B.; Benech, R.; Bongiovanni, J.; Bontoux, J.; Boueilh, M.; Brunet, F.; Calafat, A.; Cartier, M.; Cavereau, S.; Cavereau, G.; Chambon, B.; Chouchan, M.; Criton, P.; Coudre-Genetti, S.; Bretesche, O. de la; Delcourt, R.; Delibes, J.L.; Diaham, A.; Dupouis, N.; Dutil, V.; Eimer, M.; Fauvre, D.; Figueredo, G.; Fongaro, G.; Gaillard, P.; Gazal, S.; Graschaire, G.; Grenier, St.; Ibert, J.; Jacob, E.; Kozlowski, E.; Laroche, D.; Le Bars, Y.; Linfort, J.M.; Sabatier, M.A.; Sasseigne, Ph.; Saut, C.; Sornein, J.F.; Terrenne, J.P.; Donzac, M. de; Thiese, I.; Tfibel, V.; Vidal, J.; Vieillard-Baron, B.; Vincent, D.

2006-01-01

Colloquium to Golfech on September 17. and 18., 2003. The 3. colloquium of the A.N.C.L.I. took place to Golfech, to Alexis Calafat invitation, President of the C.L.I. of Golfech. The reserved subject was ' the C.L.I., the developers and the others: than can bring the various bodies of the nuclear power to the C.L.I.? ' A half-day was dedicated in particular to the future of the radioactive products after use, where the question of the transport of radioactive products was approached. 80 persons participated. The titles of the approached subjects were: dimensions of the expertise and the construction of the information; the C.L.I and its various interlocutors; C.L.I.N., the developer, the others and the transparency of the information; waste and radioactive waste in a hospital environment; safety of the transport of radioactive material; the relations of the Golfech C.N.P.E. with the C.L.I.; the new institute of radiation protection and nuclear safety; the national agency for the management of the radioactive waste, what projects; Implementation of municipal protection plans on the C.L.I. initiative; Socio-economic effects from the installation of Paluel and Penly C.N.P.E.; The case of the Garonne: the iodine 131 contamination; Analysis of the environment in contact with the secondary school of Bar-sur-Aube; C.L.I., the developer and the others: what relations. (N.C.)

Research and development for the production of radioactive ions for SPIRAL; Recherche et developpement concernant la production d'ions radioactifs dans le cadre de SPIRAL

Energy Technology Data Exchange (ETDEWEB)

Eleon, C

2007-12-15

This thesis is related to the research and development program for the production of radioactive ion beams by the ISOL method for SPIRAL at GANIL. Two studies concerning improvements to the performance of SPIRAL target-source system have been made, using a statistical approach to the atoms-to-ions transformation. The first study concerns the transformation time between the production of the radioactive atoms of Ar{sup 35} inside a target and the extraction of the radioactive ions from the source with the TARGISOL set-up (target + ECR source). The goal was to determine the diffusion coefficients of the Ar for the carbon target. The results that are presented illustrate the difficulty of this work. The second study is the application of the statistical approach to the surface ionization source. It allowed one to define and to build a new MonoNaKe set-up for the production of 1{sup +} radioactive alkaline ions. Radioactive ions of K{sup 37,47}, Na{sup 25,26,27,28,30}, Li{sup 8,9} and Al{sup 28,29,30,31} were produced. For the production of the multicharged radioactive alkali ions, the MonoNaKe target/ion-source system was coupled to the ECR source of SPIRAL-1 without a mass separator (1{sup +}/N{sup +} direct method). A first radioactive ion beam of {sup 47}K{sup 5+} was extracted at the SIRa test bench. A surface ionization test source based on the same technical characteristics of MonoNaKe has been built. The goal of this system will be to define a prototype of source adapted to the constraints of SPIRAL-2 (ionization efficiency and lifetime). (author)

Management of radioactive by-products from the uses of atomic energy in the German Democratic Republic

International Nuclear Information System (INIS)

1990-01-01

Radioactive by-products arise in the form of spent nuclear fuel, radioactive wastes and effluents from the generation of electricity by nuclear power as well as the production and uses of radionuclides in industry, medicine and research. Their safe management and their disposal without endangering man and the environment have to be ensured. This report presents an overview of the system of central collection and final disposal of low-level and intermediate-level radioactive wastes developed in the GDR by using an abandoned rock salt mine, including the relevant regulations, the licensing procedure and the control activities performed by the plant operator and, independently, by government authorities. It also addresses questions concerning the management of spent nuclear fuel and the decommissioning of nuclear facilities. (author)

Radioactive waste management practices in India

International Nuclear Information System (INIS)

Kaushik, C.P.

2016-01-01

Nuclear technologies are used for generation of electricity and for production of a wide range of radionuclides for use in research and development, health care and industry. One of the special features of nuclear industry is that it uses nuclear fission as source of energy. As a result, a large amount of energy is available from relatively small amount of fuel. The resultant quantities of waste are relatively very small in case of nuclear power as compared to same for conventional thermal power stations. In India, 'closed fuel cycle' has been adopted treating spent nuclear fuel as a material of resource. The closed fuel cycle aims at recovery and recycle of U and Pu, separation of useful isotopes of Cs and Sr for use in health care and industry. This finally leads to a very small percentage of residual material present in spent nuclear fuel requiring their management as radioactive waste. Another special feature of the Indian Atomic Energy Programme is the attention paid from the very beginning to the safe management of radioactive waste

Radioactive residues at nuclear sites in the United States of America

International Nuclear Information System (INIS)

Fiore, J.; Rampertaap, A.; Greeves, J.; MacKinney, J.; Raguso, M.; Selstrom, J.

2000-01-01

The United States of America has a large number of sites where radioactive materials have been mined, processed, produced, or used. Upon completion of activities at these sites, some will be cleaned up completely and released for unrestricted future use. However, at other sites, contamination will remain on the site following cleanup, requiring long term institutional controls. Depending on the purpose or the activity conducted at a specific site, these locations are generally under the jurisdiction of a federal agency: the United States Department of Energy, the United States Nuclear Regulatory Commission, the United States Environmental Protection Agency, or the United States Department of Defense. However, under certain conditions, the Nuclear Regulatory Commission relinquishes regulatory authority to individual states to regulate the commercial uses of radioactive materials (except for nuclear reactors), so some locations with radioactive materials are under the jurisdiction of individual states. Other sites with naturally occurring radioactive contamination may also be controlled by individual states. One or two sites under the jurisdiction of each agency are discussed where radioactive materials either existed in the past or exist today, and the source of contamination, the anticipated end state, and the process by which the responsible agency did or will conduct cleanup and site closure are described. Several issues are reviewed that must be addressed in order to design and implement remediations that will ensure long term protection for the environment and future inhabitants. The role of citizens in environmental cleanups is examined, and how institutional controls may be applied to ensure long term protection of remediations that leave some contaminants in place. (author)

Development of In-situation radioactivity Inspection system

International Nuclear Information System (INIS)

Min, Sujung; Lee, Sanghun; Kim, Miyoung; Kim, Myungjin; Lee, Unjang; Park, Jungkyun

2015-01-01

Many Korean people worry about radioactive contamination of Japanese and Korean marine products. Radioactive contamination of processed foodstuffs, livestock, marine products, farm products imported from Japan and fishes caught in coastal waters of Korea has become an important social issue. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. In consequence, there are some problem of time delay and low reliability. To protect the health of citizens from radioactivity contained in Japanese marine products imported to Korea, a system to inspect radioactivity in real time will be developed. The system is to measure the radioactivity level of farm and marine products continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Product performance assessment and tests will be conducted later. When the system develops and its commercialization begins, people's anxiety about radioactive contamination of foods after the Fukushima nuclear accident will be eased and people will be able to trust the radioactive inspection

Development of In-situation radioactivity Inspection system

Energy Technology Data Exchange (ETDEWEB)

Min, Sujung; Lee, Sanghun; Kim, Miyoung; Kim, Myungjin; Lee, Unjang [ORIONENC Co., Seoul (Korea, Republic of); Park, Jungkyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

Many Korean people worry about radioactive contamination of Japanese and Korean marine products. Radioactive contamination of processed foodstuffs, livestock, marine products, farm products imported from Japan and fishes caught in coastal waters of Korea has become an important social issue. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. In consequence, there are some problem of time delay and low reliability. To protect the health of citizens from radioactivity contained in Japanese marine products imported to Korea, a system to inspect radioactivity in real time will be developed. The system is to measure the radioactivity level of farm and marine products continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Product performance assessment and tests will be conducted later. When the system develops and its commercialization begins, people's anxiety about radioactive contamination of foods after the Fukushima nuclear accident will be eased and people will be able to trust the radioactive inspection.

Controlling radioactive waste

International Nuclear Information System (INIS)

Wurtinger, W.

1992-01-01

The guideline of the Ministry for Environmental Protection for controlling radioactive waste with a negligible development of heat defines in detail what data are relevant to the control of radioactive waste and should be followed up on and included in a system of documentation. By introducing the AVK (product control system for tracing the course of waste disposal) the operators of German nuclear power plants have taken the requirements of this guideline into account. In particular, possibilities for determining the degree of radioactivity of radioactive waste, which the BMU-guidelines call for, were put into practice by means of the programming technology of the product control system's module MOPRO. (orig.) [de

A productivity and cost comparison of two systems for producing biomass fuel from roadside forest treatment residues

Science.gov (United States)

Nathaniel Anderson; Woodam Chung; Dan Loeffler; John Greg Jones

2012-01-01

Forest operations generate large quantities of forest biomass residues that can be used for production of bioenergy and bioproducts. However, a significant portion of recoverable residues are inaccessible to large chip vans, making use financially infeasible. New production systems must be developed to increase productivity and reduce costs to facilitate use of these...

Comparison of biogas production from rapeseed and wheat residues in compound with cattle manure

Directory of Open Access Journals (Sweden)

M Safari

2016-09-01

process pH was observed in the first few days of the digestion and this is due to high volatile fatty acid (VFA formation. These results were compatible with sanaee moghadam et al. (2013. The results obtained showed that, the highest rate of VS reduction belonged to rapeseed residues at 52.22%.The lowest rate of VS reduction attributed to wheat residues at 36.79%. The rapeseed residues with 311.45 Lit.kg-1 VS had the highest accumulated methane followed by wheat straw with 167.69.28 L.Kg-1 VS in probability level of 5%. The average percentages of methane production for rapeseed straw and wheat straw during the 140 days experiment under mesophilic condition were 66% and 55%, respectively. Production of methane had delay and started after 46th day. Much reason may be possible. Inoculums used in this study were only fresh cattle dung. The mixture of fresh cattle dung and effluent of anaerobic digester or fresh rumen fluid may be decrease retention time and increase biogas production. According results of Budiyono the rumen fluid inoculated to biodigester significantly affected the biogas production. Rumen fluid inoculums caused biogas production rate and efficiency increase more than two times in compare to manure substrate without rumen fluid inoculums (Budyono et al., 2010. The other reason was pretreatment. This study applied just mechanical pretreatment. According to Cecilia studies, different pretreatment combined with mechanical pretreatment decrease retention time and increase biogas production efficiency (Cecilia et al, 2013. However, Zhang et al. claimed that it is hard to say which method is the best because each has its own strong point and weak point. Yet, until now, none of the pretreatment technologies has found a real breakthrough. Conclusions According to this study, rapeseed residues had the highest level of methane production in comparison with wheat residues. The rapeseed residues combine with cattle dung had suitable potential to methane production. The

Fate of ivermectin residues in ewes' milk and derived products.

Science.gov (United States)

Cerkvenik, Vesna; Perko, Bogdan; Rogelj, Irena; Doganoc, Darinka Z; Skubic, Valentin; Beek, Wim M J; Keukens, Henk J

2004-02-01

The fate of ivermectin (IVM) residues was studied throughout the processing of daily bulk milk from 30 ewes (taken up to 33 d following subcutaneous administration of 0.2 mg IVM/kg b.w.) in the following milk products: yoghurt made from raw and pasteurized milk; cheese after pressing; 30- and 60-day ripened cheese; and whey, secondary whey and whey proteins obtained after cheese-making (albumin cheese). The concentration of the H2B1a component of IVM was analysed in these dairy products using an HPLC method with fluorescence detection. The mean recovery of the method was, depending on the matrix, between 87 and 100%. Limits of detection in the order of only 0.1 microg H2B1a/kg of product were achieved. Maximum concentrations of IVM were detected mostly at 2 d after drug administration to the ewes. The highest concentration of IVM was found on day 2 in 60-day ripened cheese (96 microg H2B1a/kg cheese). Secondary whey was the matrix with the lowest concentration of IVM (milk fat and solid content were evident. During yoghurt production, fermentation and thermal stability of IVM was observed. During cheese production, approximately 35% of the IVM, present in the raw (bulk) milk samples, was lost. From the results it was concluded that the processing of ewes' milk did not eliminate the drug residues under investigation. The consequences of IVM in the human diet were discussed. Milk from treated animals should be excluded from production of fat products like cheese for longer after treatment with IVM than for lower fat products.

Biodiesel production from residual oils recovered from spent bleaching earth

International Nuclear Information System (INIS)

Huang, Yi-Pin; Chang, James I.

2010-01-01

This work was to study technical and economic feasibilities of converting residual oils recovered from spent bleaching earth generated at soybean oil refineries into useable biodiesel. Experimental results showed that fatty acids in the SBE residual oil were hexadecenoic acid (58.19%), stearic acid (21.49%) and oleic acid (20.32%), which were similar to those of vegetable oils. The methyl ester conversion via a transesterification process gave a yield between 85 and 90%. The biodiesel qualities were in reasonable agreement with both EN 14214 and ASTM D6751 standards. A preliminary financial analysis showed that the production cost of biodiesel from SBE oils was significantly lower than the pre-tax price of fossil diesel or those made of vegetable oils or waste cooking oils. The effects of the crude oil price and the investment on the production cost and the investment return period were also conducted. The result showed that the investment would return faster at higher crude oil price. (author)

Residual monomer reduction in polymer latex products by extraction with supercritical carbon dioxide

NARCIS (Netherlands)

Aerts, M.; Meuldijk, J.; Kemmere, M.F.; Keurentjes, J.T.F.

2011-01-01

Extraction of residual monomer from a latex product with supercritical carbon dioxide ((sc)CO2) in a column was studied. Operating conditions were chosen at 35¿°C and 100 bar. For reducing the residual styrene level in a polystyrene latex from 104 ppm to 100¿ppm and from 104 ppm to 10¿ppm, a

Study of glass ceramic material on the base of ash group simulating slag of plasma shaft furnace for high temperature reprocessing of radioactive wastes

International Nuclear Information System (INIS)

Aloj, A.S.; Dmitriev, S.A.; Stefanovskij, S.V.

1997-01-01

Using the methods of X-ray diffraction, differential thermal and micro-probe analysis it is shown that the processes of minerals formation and homogenization in ash residue based charge under the heating up to 1450 deg C take place with a high rate and completely finish during 10 minutes. Homogeneous materials containing besides glassy phase crystalline phases and metallic shots are formed in this process. The products obtained with fluxes (dolomite and clay) additions are more homogeneous than a flux-less fused slag. Losses of α-radioactive nuclides during the melting of ash residue at 1300 deg C do not exceed 1.5% and is likely attributed with the products of uranium decay. Hydrolytic stability of the slags estimated from the rate of α-radioactive elements lixiviation is on the level of (1.4-5.7)x10 -4 g/(cm 2 x day) at 95 deg C

The prospect for recycle of radioactive scrap metals to products for restricted and unrestricted use

International Nuclear Information System (INIS)

Liby, A.L.

1995-01-01

Large quantities of radioactive scrap metals will arise from decontamination and decommissioning of nuclear power plants and DOE facilities. Much of this metal can be easily decontaminated and released to the existing secondary metals industry for recycling. For metal that can not be readily released, recycle into restricted-use end products is an economically attractive alternative to burial as low level radioactive waste. This paper will examine sources and types of scrap metal, technical approaches, potential products, and economics of metals recycle. Construction, licensing, environmental compliance, and possible reuse of existing nuclear facilities for metals recycling will be discussed. (author)

Recovery of biogas as a source of renewable energy from ice-cream production residues and wastewater.

Science.gov (United States)

Demirel, Burak; Orok, Murat; Hot, Elif; Erkişi, Selin; Albükrek, Metin; Onay, Turgut T

2013-01-01

Proper management of waste streams and residues from agro-industry is very important to prevent environmental pollution. In particular, the anaerobic co-digestion process can be used as an important tool for safe disposal and energy recovery from agro-industry waste streams and residues. The primary objective of this laboratory-scale study was to determine whether it was possible to recover energy (biogas) from ice-cream production residues and wastewater, through a mesophilic anaerobic co-digestion process. A high methane yield of 0.338 L CH4/gCOD(removed) could be achieved from anaerobic digestion of ice-cream wastewater alone, with almost 70% of methane in biogas, while anaerobic digestion of ice-cream production residue alone did not seem feasible. When wastewater and ice-cream production residue were anaerobically co-digested at a ratio of 9:1 by weight, the highest methane yield of 0.131 L CH4/gCOD(removed) was observed. Buffering capacity seemed to be imperative in energy recovery from these substrates in the anaerobic digestion process.

The state of the art on the radioactive metal waste recycling technologies

International Nuclear Information System (INIS)

Oh, Won Jin; Moon, Jei Kwon; Jung, Chong Hun; Park, Sang Yoon

1997-09-01

As the best strategy to manage the radioactive metal wastes which are generated during operation and decommissioning of nuclear facilities, the following recycling technologies are investigated. 1. decontamination technologies for radioactive metal waste recycling 2. decontamination waste treatment technologies. 3. residual radioactivity evaluation technologies. (author). 260 refs., 26 tabs., 31 figs

Radioactive waste management in Belgium

International Nuclear Information System (INIS)

Dejonghe, P.

1977-01-01

In 1975 the research association BelgoWaste was founded in order to prepare a technical and administrative plan for radioactive waste management in Belgium and to take the preliminary steps for establishing an organization which would be responsible for this activity. The association made a survey of all forecasts concerning radioactive waste production by power reactors and the fuel cycle industry based on various schemes of development of the nuclear industry. From the technical point of view, the reference plan for waste management envisages: purification at the production site of large volumes of low-level effluents; construction of a central facility for the treatment and intermediate storage of process concentrates (slurries, resins, etc.) and medium-level waste, centralization assuming that adequate arrangements are made for transporting waste before final treatment; maximum recovery of plutonium from waste and treatment of residual material by incineration at very high temperatures; treatment at the production site of high-level effluents from irradiated fuel reprocessing; construction of an underground long-term storage site for high-level treated waste and plutonium fuel fabrication waste (deep clay formations are at present preferred); and disposal of low-level treated waste into the Atlantic Ocean. It is intended to entrust the entire responsibility for treatment, disposal and storage of treated waste to a single body with participation by the State, the Nuclear Energy Research Centre (CEN/SCK), the electricity companies and Belgonucleaire. The partners intend to set up their facilities and services in the area of Mol. (author)

Method of reducing the volume of radioactive waste

International Nuclear Information System (INIS)

Buckley, L.P.; Burrill, K.A.; Desjardins, C.D.; Salter, R.S.

1984-01-01

There is provided a method of reducing the volume of radioactive waste, comprising: pyrolyzing the radioactive waste in the interior of a vessel, while passing superheated steam through the vessel at a temperature in the range 500 to 700 degrees C, a pressure in the range 1.0 to 3.5 MPa, and at a flow rate in the range 4 to 50 mL/s/m 3 of the volume of the vessel interior, to cause pyrohydrolysis of the waste and to remove carbon-containing components of the pyrolyzed waste from the vessel as gaseous oxides, leaving an ash residue in the vessel. Entrained particles present with the gaseous oxides are filtered and acidic vapours present with the gaseous oxides are removed by solid sorbent. Steam and any organic substances present with the gaseous oxides are condensed and the ash is removed from the vessel. The radioactive waste may be deposited upon an upper screen in the vessel, so that a substantial portion of the pyrolysis of the radioactive waste takes place while the radioactive waste is on the upper screen, and pyrolyzed waste falls through the upper screen onto a lower screen, where another substantial portion of the pyrohydrolysis takes place. The ash residue falls through the lower screen

Radioactivity

International Nuclear Information System (INIS)

Chelet, Y.

2006-01-01

The beginning of this book explains the why and how of the radioactivity, with a presentation of the different modes of disintegration. Are tackled the reports between radioactivity and time before explaining how the mass-energy equivalence appears during disintegrations. Two chapters treat natural radioisotopes and artificial ones. This book makes an important part to the use of radioisotopes in medicine (scintigraphy, radiotherapy), in archaeology and earth sciences (dating) before giving an inventory of radioactive products that form in the nuclear power plants. (N.C.)

Studies on treatment of radioactive animal carcass, (1)

International Nuclear Information System (INIS)

Matsuoka, Osamu; Koizumi, Akira; Fukuda, Satoshi

1979-01-01

A new method of waste treatment of animal carcass contaminated with plutonium was proposed. A multi-step process was designed and tested at a laboratory scale which was composed of the following processes; microwave dehydration, heat decomposition and ashing. Microwave dehydration was found the most adequate as the first step of the treatment because of the negligible release of nonvolatile radioactivity. About 70% of body weight was reduced by microwave dehydration. Dehydrated animal carcass was decomposed by graded electric heating under anaerobic condition. Burnable gas and vapour produced by the heat decomposition were oxidized by passing through a reheating tube with excess air. The exhaust gas had no significant radioactivity. The residue of charred carcass was oxidized by heating with excess air. The weight of final product was up to 8% of original wet weight. The proposed multi-step process provided to be adequate for the waste disporsal of Pu contaminated animal carcass. (author)

Studies of natural radioactivity in cement products using gamma ray spectroscopy

International Nuclear Information System (INIS)

Ibrahim, N.; Periasamy, V.

2000-01-01

Evidence from our earlier study on several types of building materials has shown that cement contains a substantial amount of natural occurring radioactive materials. There are many brands of cement products available in Malaysia. Although the basic ingredients of cement are similar across brand, their proportion varies. In this study we have selected twelve brands of cement products which are analysed for natural radioactivity (U,Th,K) using gamma ray spectrometry. The gamma energies of interest are 583.1 keV, 609.3 keV and 1460 keV for nuclides 208 Tl, 214 Bi and 40 K respectively. Our findings show a relatively high activity of 40 K for all cement brands, ranging from 33 Bq/kg to as high as 3010 Bq/kg. Uranium activity ranges from 9Bq/kg to 672 Bq/kg while thorium activity was found range from 6Bq/kg to 94 Bq/kg. The radium equivalent activity is calculated for all brands and the values obtained range between 24 Bq/kg to 879 Bq/kg. Eight out of twelve products possess radium equivalent greater than 370 Bq/kg, a threshold limit for radiation dose equivalent to 1.5 mSv per annum. (author)

Safety aspects in fuel reprocessing and radioactive waste management

International Nuclear Information System (INIS)

Agarwal, K.

2018-01-01

Nuclear energy is used for generation of electricity and for production of a wide range of radionuclides for use in research and development, healthcare and industry. Nuclear industry uses nuclear fission as source of energy so a large amount of energy is available from very small amount of fuel. As India has adopted c losed fuel cycle , spent nuclear fuel from nuclear reactor is considered as a material of resource and reprocessed to recovery valuable fuel elements. Main incentive of reprocessing is to use the uranium resources effectively by recovering/recycling Pu and U present in the spent fuel. This finally leads to a very small percentage of residual material present in spent nuclear fuel requiring their management as radioactive waste. Another special feature of the Indian Atomic Energy Program is the attention paid from the very beginning to the safe management of radioactive waste

Report on air and water radioactivity measurement presented to the Commission for Protection against Ionizing Radiations of the State Secretary for Public Health (sessions of the 6 January and 18 February 1957). Report on the determination of radioactivity of mineral waters presented to High Council for Thermal cures of the State Secretary for Public Health (6 February 1957)

International Nuclear Information System (INIS)

Fallot, P.; Bugnard, L.

1957-06-01

The first part of this document discusses radioactivity measurement techniques which seem to be recommended for the monitoring of the release of radio-elements by civil and military applications of nuclear energy. These methods first concern air radioactivity due to uranium ore extraction, ore storage, air-cooling of piles, uranium fuel sheath failure, plutonium extraction and fission product processing, and nuclear explosion. Methods are discussed for the measurement of gas or aerosol radioactivity. The measurement of water radioactivity is then addressed by distinguishing measurements performed on rainfalls or snow, on effluents from nuclear plants. The second part discusses the determination of radioactivity of mineral waters. The authors describe the three main principles on which measurement methods are based: direct measurement of radioactivity of gases contained by water, direct measurement of gas radioactivity by the active deposit method, and measurement of alpha and beta radiations of the evaporation residue or of water precipitation product. Notably about radon measurement in waters, the instrumentation, dosing procedure, measurement sensitivity and precision are presented and discussed

Separation of thorium (IV) from lanthanide concentrate (LC) and water leach purification (WLP) residue

International Nuclear Information System (INIS)

AL-Areqi, Wadeeah M.; Majid, Amran Ab.; Sarmani, Sukiman

2014-01-01

Thorium (IV) content in industrial residue produced from rare earth elements production industry is one of the challenges to Malaysian environment. Separation of thorium from the lanthanide concentrate (LC) and Water Leach Purification (WLP) residue from rare earth elements production plant is described. Both materials have been tested by sulphuric acid and alkaline digestions. Th concentrations in LC and WLP were determined to be 1289.7 ± 129 and 1952.9±17.6 ppm respectively. The results of separation show that the recovery of Th separation from rare earth in LC after concentrated sulphuric acid dissolution and reduction of acidity to precipitate Th was found 1.76-1.20% whereas Th recovery from WLP was less than 4% after concentrated acids and alkali digestion processes. Inductively Coupled Plasma-Mass Spectroscopy (ICP-MS) was used to determine Th concentrations in aqueous phase during separation stages. This study indicated that thorium maybe exists in refractory and insoluble form which is difficult to separate by these processes and stays in WLP residue as naturally occurring radioactive material (NORM)

Soil fertility and soil loss constraints on crop residue removal for energy production

Energy Technology Data Exchange (ETDEWEB)

Flaim, S.

1979-07-01

A summary of the methodologies used to estimate the soil fertility and soil loss constraints on crop residue removal for energy production is presented. Estimates of excess residue are developed for wheat in north-central Oklahoma and for corn and soybeans in central Iowa. These sample farming situations are analyzed in other research in the Analysis Division of the Solar Energy Research Institute.

Crop residue harvest for bioenergy production and its implications on soil functioning and plant growth: A review

Directory of Open Access Journals (Sweden)

Maurício Roberto Cherubin

Full Text Available ABSTRACT: The use of crop residues as a bioenergy feedstock is considered a potential strategy to mitigate greenhouse gas (GHG emissions. However, indiscriminate harvesting of crop residues can induce deleterious effects on soil functioning, plant growth and other ecosystem services. Here, we have summarized the information available in the literature to identify and discuss the main trade-offs and synergisms involved in crop residue management for bioenergy production. The data consistently showed that crop residue harvest and the consequent lower input of organic matter into the soil led to C storage depletions over time, reducing cycling, supply and availability of soil nutrients, directly affecting the soil biota. Although the biota regulates key functions in the soil, crop residue can also cause proliferation of some important agricultural pests. In addition, crop residues act as physical barriers that protect the soil against raindrop impact and temperature variations. Therefore, intensive crop residue harvest can cause soil structure degradation, leading to soil compaction and increased risks of erosion. With regard to GHG emissions, there is no consensus about the potential impact of management of crop residue harvest. In general, residue harvest decreases CO2 and N2O emissions from the decomposition process, but it has no significant effect on CH4 emissions. Plant growth responses to soil and microclimate changes due to crop residue harvest are site and crop specific. Adoption of the best management practices can mitigate the adverse impacts of crop residue harvest. Longterm experiments within strategic production regions are essential to understand and monitor the impact of integrated agricultural systems and propose customized solutions for sustainable crop residue management in each region or landscape. Furthermore, private and public investments/cooperations are necessary for a better understanding of the potential environmental

75 FR 75482 - Draft Guidance for Industry on Residual Solvents in Animal Drug Products; Questions and Answers...

Science.gov (United States)

2010-12-03

...] Draft Guidance for Industry on Residual Solvents in Animal Drug Products; Questions and Answers... Solvents in Animal Drug Products; Questions and Answers.'' The draft questions and answers (Q&A) guidance addresses the United States Pharmacopeia (USP) General Chapter Residual Solvents that applies to both human...

Influence of radioactive contamination to agricultural products due to dry and wet deposition processes during a nuclear emergency

International Nuclear Information System (INIS)

Hwang, Won Tae; Kim, Eun Han; Suh, Kyung Suk; Han, Moon Hee; Choi, Yong Ho; Lee, Chang Woo

2002-01-01

Combined with deposition model onto the ground of radionuclides, the influence of radioactive contamination to agricultural products was analyzed due to wet deposition as well as dry deposition from radioactive air concentration during a nuclear emergency. The previous dynamic food chain model, in which initial input parameter is only radionuclide concentrations on the ground, was improved for the evaluating of radioactive contamination to agricultural products from either radionuclide concentrations in air or radionuclide concentrations on the ground. As the results, in case of deposition onto the ground, wet deposition was more dominant process than dry deposition. While the contamination levels of agricultural products were dependent on the a variety of factors such as radionuclides and rainfall rate. It means that the contamination levels of agricultural products are determined from which is more dominant process between deposition on the ground and interception onto agricultural plants

Final disposal of radioactive wastes

Energy Technology Data Exchange (ETDEWEB)

Kroebel, R [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Projekt Wiederaufarbeitung und Abfallbehandlung; Krause, H [Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Abt. zur Behandlung Radioaktiver Abfaelle

1978-08-01

This paper discusses the final disposal possibilities for radioactive wastes in the Federal Republic of Germany and the related questions of waste conditioning, storage methods and safety. The programs in progress in neighbouring CEC countries and in the USA are also mentioned briefly. The autors conclude that the existing final disposal possibilities are sufficiently well known and safe, but that they could be improved still further by future development work. The residual hazard potential of radioactive wastes from fuel reprocessing after about 1000 years of storage is lower that of known inorganic core deposits.

Valorization of agroindustrial solid residues and residues from biofuel production chains by thermochemical conversion: a review, citing Brazil as a case study

Directory of Open Access Journals (Sweden)

E. Virmond

2013-06-01

Full Text Available Besides high industrial development, Brazil is also an agribusiness country. Each year about 330 million metrics tons (Mg of biomass residues are generated, requiring tremendous effort to develop biomass systems in which production, conversion and utilization of bio-based products are carried out efficiently and under environmentally sustainable conditions. For the production of biofuels, organic chemicals and materials, it is envisaged to follow a biorefinery model which includes modern and proven green chemical technologies such as bioprocessing, pyrolysis, gasification, Fischer-Tropsch synthesis and other catalytic processes in order to make more complex molecules and materials on which a future sustainable society will be based. This paper presents promising options for valorization of Brazilian agroindustrial biomass sources and residues originating from the biofuel production chains as renewable energy sources and addresses the main aspects of the thermochemical technologies which have been applied.

FAO/IAEA model protocol for the determination of bound residues in soil

International Nuclear Information System (INIS)

1986-01-01

A protocol for determining bound pesticide residue content in soils was developed and collaboratively tested by 11 members of the FAO/IAEA Research Co-ordination Committee. The method assumes prior incubation of soil with a radioactive pesticide or related organic compound. The major process steps of the protocol include: (a) Soxhlet extraction of air-dry soil with methanol for 24 h; (b) determination of radioactivity in unextracted soil, in methanol-extracted soil (yielding bound residue content), and in the methanol extract (yielding extractable residue content); and (c) use of triplicate samples per analysis. The participants received lysimeter soils treated six to seven years earlier with 14 C-allyl alcohol (Soil A) or 14 C-hexachloro-benzene (Soil H). The inter-laboratory results first indicated non-homogeneity of Soil A sub-samples, since the initial and bound radioactivity for four laboratories was about half of that found by the remaining seven laboratories. Intra-laboratory (in one laboratory) analyses of sub-subsamples from six 'high-group' laboratories, two 'low-group' laboratories and two additional laboratories confirmed the homogeneity of Soil A and implicated error in the combustion methods at 'low-group' laboratories. The intra- and inter-laboratory coefficients of variation for initial 14 C-content were 4.7% and 7.0%, respectively. Of the residual 14 C in Soil A, 95% was bound; in contrast, only 15% of 14 C in Soil H was bound. The coefficients of variation among ten laboratories, for Soil H, were 8.4% and 18.1% for percentage extractable residue and percentage bound residue, respectively. Some limited testing of alternative protocols, using other solvents or batch extraction, confirmed that the IAEA protocol was most efficient in the extraction of non-bound radioactivity; pre-wetting Soil A may, however, improve extraction. (author)

Diffusion of disintegration products of radioactive gases in circular and flat channels

International Nuclear Information System (INIS)

Ingham, D.B.

1975-01-01

The problem of steady state diffusion of the decaying products resulting from the disintegration of a radioactive gas flowing through circular and flat channels is presented. Axial diffusion is neglected and a small diffusion parameter is assumed. Results are obtained for the axial displacement and density distribution of atoms deposited on the walls when the laminar flow is Poiseuille and plug. These results can be used to determine diffusion coefficients of disintegration products. (author)

Concept of an immersive assistance system with augmented reality for the support of manual activities in radioactive production environments

International Nuclear Information System (INIS)

Eursch, Andreas A.

2010-01-01

The thesis on an immersive assistance system concept with augmented reality for the support of manual activities in radioactive production environments covers the following topics: analysis of the situation: production and use of radioactive materials, problem analysis of the work in the production facilities, necessity of manual activities, automation, prediction in hot cells; status of research and development; assistance system concept, immersive camera system; augmented reality support in hot cells; economic evaluation and generalization.

International directory of certified radioactive sources

Energy Technology Data Exchange (ETDEWEB)

Grosse, G; Bambynek, W

1983-01-01

This directory lists the products of 16 suppliers of certified reference materials (CRM) of radioactivity as given in their catalogues. Included are only products for which certificates are delivered and whose uncertainties are given according to the rules defined in ICRU Report No. 12, ''Certification of Standardized Radioactive Sources'' (International Commission on Radiation and Measurements, Washington, 1968). Only those products are included of which the standard uncertainties according to the above rules are less than 10%. Prices of the products are not mentioned since they frequently change. The products are divided into four groups: Radioactive Solutions, Radioactive Gases, Solid Sources and Sources for Liquid Scintillation Counting).

International directory of certified radioactive sources

International Nuclear Information System (INIS)

Grosse, G.; Bambynek, W.

1983-01-01

This directory lists the products of 16 suppliers of certified reference materials (CRM) of radioactivity as given in their catalogues. Included are only products for which certificates are delivered and whose uncertainties are given according to the rules defined in ICRU Report No. 12, ''Certification of Standardized Radioactive Sources'' (International Commission on Radiation and Measurements, Washington, 1968). Only those products are included of which the standard uncertainties according to the above rules are less than 10%. Prices of the products are not mentioned since they frequently change. The products are divided into four groups: Radioactive Solutions, Radioactive Gases, Solid Sources and Sources for Liquid Scintillation Counting). (orig./WL)

Classification of solid wastes as non-radioactive wastes

International Nuclear Information System (INIS)

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

1995-01-01

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

The medical effects of radioactive fall-out: role of stable end-products

International Nuclear Information System (INIS)

Burrows, B.A.; Cardarelli, J.C.; Boling, E.A.; Sinex, F.M.

1980-01-01

To summarize, from preliminary observations on the possible effects of radioactive fall-out, it may be inferred that in addition to the secondary products of ionizing irradiation per se, the stable end-products of the transmutation of certain radionuclides may adversely influence cellular metabolism, including mutagenesis. The discussion of the possible role of intracellular barium as an end-product of 137Cs decay is offered as an example of an unpredictable number of broad ecological, as well as the more limited medical, effects that may be of both clinical and climatological significance

CACAO: A project for a laboratory for the production and characterization of thin radioactive layers

Energy Technology Data Exchange (ETDEWEB)

Bacri, C.O., E-mail: bacri@ipno.in2p3.f [Institut de Physique Nucleaire d' Orsay, 91406 Orsay Cedex, CNRS (UMR8608-IN2P3), Universite Paris-Sud (Paris XI) (France); Petitbon, V.; Pierre, S. [Institut de Physique Nucleaire d' Orsay, 91406 Orsay Cedex, CNRS (UMR8608-IN2P3), Universite Paris-Sud (Paris XI) (France)

2010-02-11

CACAO, Chimie des Actinides et Cibles radioActives a Orsay (actinide chemistry and radioactive targets at Orsay), is a project under construction that consists of the installation of a hot laboratory dedicated to the production and characterization of thin radioactive layers. The project aims to be a joint CNRS-CEA national laboratory to overcome difficulties related mainly to safety issues and to the lack of knowledge and potential manpower. The first goal is to fulfill, at least, the needs of the whole French community, and to be able to coordinate the different activities related to radioactive targets. For this purpose, itis important to be complementary to already existing international installations. Inside this framework, it will of course be possible to produce and/or characterize targets for other users.

CACAO: A project for a laboratory for the production and characterization of thin radioactive layers

Science.gov (United States)

Bacri, C. O.; Petitbon, V.; Pierre, S.; Cacao Group

2010-02-01

CACAO, Chimie des Actinides et Cibles radioActives à Orsay (actinide chemistry and radioactive targets at Orsay), is a project under construction that consists of the installation of a hot laboratory dedicated to the production and characterization of thin radioactive layers. The project aims to be a joint CNRS-CEA national laboratory to overcome difficulties related mainly to safety issues and to the lack of knowledge and potential manpower. The first goal is to fulfill, at least, the needs of the whole French community, and to be able to coordinate the different activities related to radioactive targets. For this purpose, itis important to be complementary to already existing international installations. Inside this framework, it will of course be possible to produce and/or characterize targets for other users.

CACAO: A project for a laboratory for the production and characterization of thin radioactive layers

International Nuclear Information System (INIS)

Bacri, C.O.; Petitbon, V.; Pierre, S.

2010-01-01

CACAO, Chimie des Actinides et Cibles radioActives a Orsay (actinide chemistry and radioactive targets at Orsay), is a project under construction that consists of the installation of a hot laboratory dedicated to the production and characterization of thin radioactive layers. The project aims to be a joint CNRS-CEA national laboratory to overcome difficulties related mainly to safety issues and to the lack of knowledge and potential manpower. The first goal is to fulfill, at least, the needs of the whole French community, and to be able to coordinate the different activities related to radioactive targets. For this purpose, itis important to be complementary to already existing international installations. Inside this framework, it will of course be possible to produce and/or characterize targets for other users.

Torrefaction of residues and by-products from sunflower chain

Directory of Open Access Journals (Sweden)

G. Riva

2013-09-01

Full Text Available The high heterogeneity of some residual biomasses makes rather difficult their energy use and standardisation is a key aspect for these fuel products. Torrefaction is an interesting process used to improve the quality of ligno-cellulosic biomasses and to achieve standardisation. In the present study torrefaction has been employed on residues and by-products deriving from sunflower production chain, in particular sunflower stalks and oil press cake. The thermal behaviour of materials has been studied at first by thermo-gravimetric analysis in order to identify torrefaction temperatures range. Different residence time and torrefaction temperatures have been employed in a bench top torrefaction reactor afterwards. Analyses of raw and torrefied materials have been carried out to assess the influence of the process. As a consequence of torrefaction, the carbon and ash contents increase while the volatilisation range is reduced making the material more stable and standardised. Mass yield, energy yield and energy densification reach values of about 60 %, 80 % and 1.33 for sunflower stalks and 64 %, 85 % and 1.33 for sunflower oil press cake respectively. As highlighted by results, torrefaction is more interesting for sunflower stalks than oil cake and husks because of the different starting characteristics. Untreated oil cake and husks already show a good high heating value and the eventual torrefaction should be mild. On the contrary for sunflower stalks the process is more useful and could be more severe.

Utilization of lignite power generation residues for the production of lightweight aggregates.

Science.gov (United States)

Anagnostopoulos, Iason M; Stivanakis, Victor E

2009-04-15

A novel process is proposed for the utilization of lignite combustion solid residues in the production of inflammable lightweight aggregates (LWA). The process consists of two stages, pelletization and sintering, and carbon contained in BA was used as the process fuel. The main residues bottom ash (BA) and fly ash (FA) from Megalopolis power plant were characterized, mixed in different proportions and treated through pelletization and sintering process. Sintering benefits from combustion of BA carbon content and the product is a hardened porous cake. The energy required for achievement of high temperatures, in the range of 1250 degrees C, was offered by carbon combustion and CO(2) evolution is responsible for porous structure formation. Selected physical properties of sintered material relevant to use as lightweight aggregates were determined, including bulk density, porosity and water absorption. Bulk density varies from 0.83 to 0.91 g/cm(3), porosity varies from 60% to 64% and water absorption varies from 66% to 80%. LWA formed is used for the production of lightweight aggregate concrete (LWAC). Thermal conductivity coefficient varies from 0.25 to 0.37 W/mK (lower than maximum limit 0.43 W/mK) and compressive strength varies from 19 to 23 MPa (higher than minimum limit 17 MPa). The results indicate that sintering of lignite combustion residues is an efficient method of utilization of carbon containing BA and production of LWA for structural and insulating purposes. Carbon content of BA is a key factor in LWA production. Finally, this research work comprises the first proposed application for utilization of BA in Greece.

Radioactive Contamination of Agricultural Products in Poland

International Nuclear Information System (INIS)

Muszynski, W.; Grabowski, D.; Rubel, B.; Kurowski, W.; Swietochowska, J.; Smagala, G.

2003-01-01

Radiological contamination of the environment is caused by nuclear activities on the globe: nuclear weapon tests and the Chernobyl accident. The transfer of radionuclides to the organism via ingestion is one of the sources of doses obtained by people. To assess the doses received by humans the intake of isotopes with daily diet was defined. The concentration of radionuclides in foodstuffs was determined. The network of Service for Measurement of Radioactive Contamination systematically controls all kinds of important agricultural products such as milk, meat, vegetables, fruit, cereals and forest products: mushrooms, blueberries etc. Measurement stations involved in food monitoring act within Sanitary-Epidemiological Stations, Veterinary Hygiene Units and Chemical-Agricultural Stations. All activities are co-ordinated by the Central Laboratory for Radiological Protection. The level of activity of caesium isotopes has regularly been monitored in collected samples originating from different administrative districts of Poland. Since 1994 the 134 Cs concentration has been below the detection limit. The activity of 137 Cs has been measured to determine long-term effect of the accident on the contamination of milk, meat and other foodstuffs. (orig.)

Production of surfactin from rice mill polishing residue by submerged fermentation using Bacillus subtilis MTCC 2423.

Science.gov (United States)

Gurjar, Jigar; Sengupta, Bina

2015-08-01

Rice mill polishing residue (RMPR), an abundant and cheap agro residue, was used as substrate for microbial growth of Bacillus subtilis MTCC 2423 by submerged fermentation process to produce surfactin. Nutrients present in the residue were sufficient to sustain the growth of the microorganism. Multi stage foam fractionation followed by acid precipitation was used to concentrate and recover the product. Recoverable yield of surfactin was 4.17 g/kg residue. Product recovered in the foamate accounted for 69% of the total yield. The residual broth containing ∼ 30% surfactin exhibited biological oxygen demand and chemical oxygen demand values of 23 and 69 mg/L respectively. The microbial growth data was correlated using three parameter sigmoid models. Surfactin synthesized had a predominance of molecular weight 1076 Da. Foam separation of copper using surfactin resulted in a maximum removal of 72.5%. Copyright © 2015 Elsevier Ltd. All rights reserved.

Enhanced biogas production from penicillin bacterial residue by thermal-alkaline pretreatment

International Nuclear Information System (INIS)

Zhong, Weizhang; Li, Guixia; Gao, Yan; Li, Zaixing; Geng, Xiaoling; Li, Yubing; Yang, Jingliang; Zhou, Chonghui

2015-01-01

In this study, the orthogonal experimental design was used to determine the optimum conditions for the effect of thermal alkaline; pretreatment on the anaerobic digestion of penicillin bacterial residue. The biodegradability of the penicillin; bacterial residue was evaluated by biochemical methane potential tests in laboratory. The optimum values of temperature,; alkali concentration, pretreatment time and moisture content for the thermal-alkaline pretreatment were determined as; 70 °C, 6% (w/v), 30 min, and 85%, respectively. Thermal-alkaline pretreatment could significantly enhance the soluble; chemical oxygen demand solubilization, the suspended solid solubilization and the biodegradability. Biogas production; was enhanced by the thermal-alkaline pretreatment, probably as a result of the breakdown of cell walls and membranes of; micro-organisms, which may facilitate the contact between organic molecules and anaerobic microorganisms.; Keywords: penicillin bacterial residue; anaerobic digestion; biochemical methane potential tests; pretreatment

Fate of ivermectin residues in ewes' milk and derived products

NARCIS (Netherlands)

Cerkvenik, V.; Perko, B.; Rogelj, I.; Doganoc, D.Z.; Skubic, V.; Beek, W.M.J.; Keukens, H.J.

2004-01-01

The fate of ivermectin (IVM) residues was studied throughout the processing of daily bulk milk from 30 ewes (taken up to 33 d following subcutaneous administration of 0·2 mg IVM/kg b.w.) in the following milk products: yoghurt made from raw and pasteurized milk; cheese after pressing; 30- and 60-day

Approval of radioactive consumer goods

International Nuclear Information System (INIS)

Paynter, R.A.

1992-01-01

The 1980 Euratom Directive obliges the UK to draw up a system of prior authorization for the use of radioactive substances in a range of consumer products, and the Government intends to make regulations to fulfil the requirements of the Directive. These regulations will empower NRPB to approve such products prior to their supply to the public. In this brief article, the NRPB reviews the criteria against which to consider any proposed use of radioactive substances, considers radiological production standards for products and discusses the questions of the labelling of radioactive consumer goods. (UK)

Radioactive waste safety appraisal. An international peer review of the licence application for the Australian near surface radioactive waste disposal facility. Report of the IAEA International Review Team

International Nuclear Information System (INIS)

2004-05-01

Radioactive waste has been generated in Australia for a number of decades from the production and use of radioactive materials in medicine and industry, from the processing of various minerals containing natural radionuclides and from various research activities. It has been decided in the overall interest of safety and security to develop a radioactive waste disposal facility to accommodate the low level and short lived intermediate level waste, which make up the bulk of the waste, other than mining and minerals processing residues. A site selection process has been undertaken and environmental impact statement report prepared and approved. A licence application has been submitted to the national nuclear regulatory authority, the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) for siting, construction and operation of the facility. In order to assist the CEO of ARPANSA with his deliberations in this regard a request was made to the IAEA, in terms of its statutory mandate to establish international safety standards for radioactive waste safety and to provide for their application, to undertake an international peer review of the licence application and to advise the CEO accordingly. The outcome and recommendations of this peer review are presented in the report

Biogas production from energy crops and crop residues

Energy Technology Data Exchange (ETDEWEB)

Lehtomaeki, A.

2006-07-01

The feasibility of utilising energy crops and crop residues in methane production through anaerobic digestion in boreal conditions was evaluated in this thesis. Potential boreal energy crops and crop residues were screened for their suitability for methane production, and the effects of harvest time and storage on the methane potential of crops was evaluated. Codigestion of energy crops and crop residues with cow manure, as well as digestion of energy crops alone in batch leach bed reactors with and without a second stage upflow anaerobic sludge blanket reactor (UASB) or methanogenic filter (MF) were evaluated. The methane potentials of crops, as determined in laboratory methane potential assays, varied from 0.17 to 0.49 m3 CH{sub 4} kg-1 VS{sub added} (volatile solids added) and from 25 to 260 m3 CH4 t-1 ww (tons of wet weight). Jerusalem artichoke, timothy-clover and reed canary grass gave the highest methane potentials of 2 900-5 400 m3 CH{sub 4} ha-1, corresponding to a gross energy potential of 28-53 MWh ha-1 and 40 000-60 000 km ha-1 in passenger car transport. The methane potentials per ww increased with most crops as the crops matured. Ensiling without additives resulted in minor losses (0-13%) in the methane potential of sugar beet tops but more substantial losses (17-39%) in the methane potential of grass, while ensiling with additives was shown to have potential in improving the methane potentials of these substrates by up to 19-22%. In semi-continuously fed laboratory continuously stirred tank reactors (CSTRs) co-digestion of manure and crops was shown feasible with feedstock VS containing up to 40% of crops. The highest specific methane yields of 0.268, 0.229 and 0.213 m3 CH{sub 4} kg-1 VS{sub added} in co-digestion of cow manure with grass, sugar beet tops and straw, respectively, were obtained with 30% of crop in the feedstock, corresponding to 85-105% of the methane potential in the substrates as determined by batch assays. Including 30% of crop in

Nuclear fuel cycle waste recycling technology deverlopment - Radioactive metal waste recycling technology development

International Nuclear Information System (INIS)

Oh, Won Zin; Moon, Jei Kwon; Jung, Chong Hun; Park, Sang Yoon

1998-08-01

With relation to recycling of the radioactive metal wastes which are generated during operation and decommissioning of nuclear facilities, the following were described in this report. 1. Analysis of the state of the art on the radioactive metal waste recycling technologies. 2. Economical assessment on the radioactive metal waste recycling. 3. Process development for radioactive metal waste recycling, A. Decontamination technologies for radioactive metal waste recycling. B. Decontamination waste treatment technologies, C. Residual radioactivity evaluation technologies. (author). 238 refs., 60 tabs., 79 figs

Heavy concrete shieldings made of recycled radio-active steel

International Nuclear Information System (INIS)

Holland, D.; Quade, U.; Sappok, M.; Heim, H.

1998-01-01

Maintenance and decommissioning of nuclear installations will generate increasing quantities of radioactively contaminated metallic residues. For many years, Siempelkamp has been melting low-level radioactive scrap in order to re-use it for containers of nuclear industry. Another new recycling path has recently been developed by producing steel granules from the melt. These granules are used as replacement for hematite (iron ore) in the production of heavy concrete shieldings. In the CARLA plant (central plant for the recycling of low-level radioactive waste) of Siempelkamp Nuklear- und Umwelttechnik GmbH and Co., the scrap is melted in a medium frequency induction furnace. The liquid iron is poured into a cooling basin through a water jet, which splits the iron into granules. The shape of these granules is determined by various factors, such as water jet speed, pouring rate of the liquid iron and different additives to the melt. In this process, massive spheres with diameters ranging from 1 to 8 mm can be produced which add to the density of heavy concrete elements for optimum shielding. In close cooperation with Boschert, which indeed is an expert for the production of concrete shieldings, a new technology for manufacturing heavy concrete shieldings, containing low-level radioactive steel granules, has been developed. The portion of steel granules in the concrete is approx. 50 weight-%. A concrete density between 2.4 kg/dm 3 and 4.0 kg/dm 3 is available. The compressive strength for the concrete reaches values up to 65 MPa. Different types of Granulate Shielding Casks (GSC) are offered by Siempelkamp. The most famous one is the GSC 200 for 200 1 drums, which has already been qualified for final storage of radioactive wastes at the German Morsleben final repository (ERAM). This newly developed recycling process further increases the quantities of low-level radioactive metallic wastes available for recycling. Expensive storage area can thus be saved respectively

Residue management practices and planter attachments for corn production in a conservation agriculture system

Directory of Open Access Journals (Sweden)

J. Nejadi

2013-11-01

Full Text Available Seed placement and failure to establish a uniform plant stand are critical problems associated with production of corn (Zea mays following wheat (Triticum aestivum in a conservation agriculture system in Iran. Our objectives were to evaluate the performance of a corn row- crop planter equipped with two planter attachments (smooth/toothed coulters at six wheat residue management systems (three tillage systems and two levels of surface residue at two forward speeds of 5 and 7 km h-1. Residue retained after planting, seeding depth, emergence rate index (ERI and seed spacing indices were determined. The baled residue plots tilled by chisel plow followed by disc harrow (BRCD resulted in minimum residue after planting as compared to other residue treatments. Furthermore, the maximum values of the ERI and uniformity of plant spacing pertained to this treatment. Other results showed that the ERI increased up to 18% for the toothed coulter as compared to the smooth coulter. The toothed coulter also established a deeper seed placement as compared to the smooth coulter. Planting at forward speed of 5 km h-1 resulted in deeper seeding depth as compared to a forward speed of 7 km h-1. However, lower values of miss and precision indices were obtained at forward speed of 7 km h-1, indicating a more uniformity of plant spacing. Results of this study showed that equipping the conventional planter with toothed coulter and planting in soil prepared under the BRCD residue management system can result in a satisfactory conservation crop production system.

Identification of a highly reactive threonine residue at the active site of γ-glutamyl transpeptidase

International Nuclear Information System (INIS)

Stole, E.; Seddon, A.P.; Wellner, D.; Meister, A.

1990-01-01

γ-Glutamyl transpeptidase an enzyme of major importance in glutathione metabolism, was inactivated by treating it with L-(αS,5S)-α-amino-3-chloro-4,5-dihydro-5-[3- 14 C]isoxazoleacetic acid. This selective reagent binds stoichiometrically to the enzyme; more than 90% of the label was bound to its light subunit. Enzymatic digestion of the light subunit gave a 14 C-labeled peptide that corresponds to amino acid residues 517-527 of the enzyme and two incomplete digestion products that contain this labeled peptide moiety. The radioactivity associated with this peptide was released with threonine-523 during sequencing by the automated gas-phase Edman method. The light subunit contains 14 other threonine residues and a total of 19 serine residues; these were not labeled. Threonine-523 is situated in the enzyme in an environment that greatly increases its reactivity, indicating that other amino acid residues of the enzyme must also participate in the active-site chemistry of the enzyme

Pesticide residue assessment in three selected agricultural production systems in the Choluteca River Basin of Honduras

International Nuclear Information System (INIS)

Kammerbauer, J.; Moncada, J.

1999-01-01

There is a basic lack of information about the presence of pesticide residues in the environment in Central America. Over the period of February 1995 to June 1997, river, well, lagoon and spring water samples, as well as soil, fish tissue, lagoon bed sediments and some foodstuffs were taken from the greater Cholutecan River Basin of Honduras and analyzed for pesticide residues. These were collected at three separate sites (La Lima, Zamorano and Choluteca), each characterized by differing agricultural production systems. The main pesticide residues found in soil samples were dieldrin and p,p'-DDT, while river water samples were found to have detectable levels of heptachlor, endosulfan and chlorpyrifos, with lagoon and well water also being shown to contain heptachlor. These pesticides detected were in more than 20% of the samples assessed. In river water samples more pesticide residues at higher concentrations were found to be associated with areas of more intensive agricultural production. The fewest pesticides with lowest concentrations were found in the small subwatershed associated with traditional agricultural production. Although the pesticides found in the soils at the three sites were generally similar they tended to be higher in the southern part of the Cholutecan watershed, followed by the central zone, with the lowest concentrations being found in the more traditional production zone. In lagoon and well water samples more pesticides, but mostly in lower concentrations were detected at the traditional production site than at the others. Ten pesticide compounds were detected in fish tissue, mainly organochlorines, some of which were also found in lagoon sediments. In terms of food products, almost no pesticides were detected in vegetables, but the kidney adipose tissue taken from slaughtered cows was shown to have a tendency to contain some organochlorines. Spring water in the traditional agricultural production zone contained three organochlorine compounds

Production of chemically reactive radioactive ion beams through on-line separation

International Nuclear Information System (INIS)

Joinet, A.

2003-10-01

The ISOL (isotope separation on line) allows the production of secondary radioactive ion beams through spallation or fragmentation or fission reactions that take place in a thick target bombarded by a high intensity primary beam. The challenge is to increase the intensity and purity of the radioactive beam. The optimization of the system target/source requires the right choice of material for the target by taking into account the stability of the material, its reactivity and the ionization method used. The target is an essential part of the system because radioactive elements are generated in it and are released more or less quickly. Tests have been made in order to select the best fitted material for the release of S, Se, Te, Ge and Sn. Materials tested as target filling are: ZrO 2 , Nb, Ti, V,TiO 2 , CeO x , ThO 2 , C, ZrC 4 and VC). Other molecules such as: COSe, COS, SeS, COTe, GeS, SiS, SnS have been studied to ease the extraction of recoil nuclei (Se, S, Te, Ge and Sn) produced inside the target

Analysis of veterinary drug residue monitoring results for commercial livestock products in Taiwan between 2011 and 2015

Directory of Open Access Journals (Sweden)

Hsin-Chun Lee

2018-04-01

Full Text Available Antibiotics have been widely used in the treatment of livestock diseases. However, the emergence of issues related to drug resistance prompted governments to enact a series of laws regulating the use of antibiotics in livestock. Following control of the problem of drug resistant bacteria, public attention has shifted to the recurring incidence of human health and safety issues caused by residual veterinary drugs in livestock products. To guarantee the safety and hygiene of meat, milk, and eggs from food-producing animals, governments and relevant agencies established laws and regulations for the use of veterinary drugs. It is, therefore, necessary to monitor the content of residual drugs in livestock products at regular intervals to assess whether the regulations have resulted in the effective management of food product safety, and to prevent and manage sudden problems related to this issue. A 2011–2015 livestock product post-marketing monitoring program launched by the Taiwan Food and Drug Administration (TFDA inspected 1487 livestock products. Over the past 5 years, there were 34 samples identified that did not conform to the regulations; these samples included residue drugs such as β-agonists, chloramphenicols, β-lactam antibiotics, sulfa drugs, enrofloxacin, and lincomycin. Inspections of commercial livestock products with the consistent cooperation of agricultural authorities did not detect the drugs that were banned by the government, whereas the detection of other drugs decreased annually with an increase in the post-market monitoring sample size. In the future, the TFDA will continue to monitor the status of residual veterinary drugs in commercial livestock products, adjust the sampling of food products annually according to monitoring results, and closely cooperate with agricultural authorities on source management. Keywords: Agricultural authorities, Livestock products, Post-market monitoring, Veterinary drug residues

Screening of antibiotics and chemical analysis of penicillin residue in fresh milk and traditional dairy products in Oyo state, Nigeria

Directory of Open Access Journals (Sweden)

Isaac Olufemi Olatoye

2016-09-01

Full Text Available Background and Aim: There are global public health and economic concerns on chemical residues in food of animal origin. The use of antibiotics in dairy cattle for the treatment of diseases such as mastitis has contributed to the presence of residues in dairy products. Penicillin residues as low as 1 ppb can lead to allergic reactions and shift of resistance patterns in microbial population as well as interfere with the processing of several dairy products. Antibiotic monitoring is an essential quality control measure in safe milk production. This study was aimed at determining antibiotic residue contamination and the level of penicillin in dairy products from Fulani cattle herds in Oyo State. Materials and Methods: The presence of antibiotic residues in 328 samples of fresh milk, 180 local cheese (wara, and 90 fermented milk (nono from Southwest, Nigeria were determined using Premi® test kit (R-Biopharm AG, Germany followed by high-performance liquid chromatography analysis of penicillin-G residue. Results: Antibiotic residues were obtained in 40.8%, 24.4% and 62.3% fresh milk, wara and nono, respectively. Penicillin-G residue was also detected in 41.1% fresh milk, 40.2% nono and 24.4% wara at mean concentrations of 15.22±0.61, 8.24±0.50 and 7.6±0.60 μg/L with 39.3%, 36.7% and 21.1%, respectively, containing penicillin residue above recommended Codex maximum residue limit (MRL of 5 μg/L in dairy. There was no significant difference between the mean penicillin residues in all the dairy products in this study. Conclusion: The results are of food safety concern since the bulk of the samples and substantial quantities of dairy products in Oyo state contained violative levels of antibiotic residues including penicillin residues in concentrations above the MRL. This could be due to indiscriminate and unregulated administration of antibiotics to dairy cattle. Regulatory control of antibiotic use, rapid screening of milk and dairy farmers�

Radioactive Emissions from Fission-Based Medical Isotope Production and Their Effect on Global Nuclear Explosion Detection

International Nuclear Information System (INIS)

Bowyer, T.; Saey, P.

2015-01-01

The use of medical isotopes, such as Tc-99m, is widespread with over 30 million procedures being performed every year, but the fission-based production of isotopes used for medical procedures causes emissions into the environment. This paper will show that gaseous radioactive isotopes of xenon, such as Xe-133, are released in high quantities, because they have a high fission cross section and they are difficult to scrub from the processes used to produce the medical isotopes due to their largely unreactive nature. Unfortunately, the reasons that large amounts of radioactive xenon isotopes are emitted from isotope production are the same as those that make these isotopes the most useful isotopes for the detection of underground nuclear explosions. Relatively recently, the nuclear explosion monitoring community has established a provisional monitoring network for the Comprehensive Nuclear-Test-Ban Treaty (CTBT) that includes radioactive xenon monitoring as a major component. This community has discovered that emissions from medical isotope production present a more serious problem to nuclear explosion monitoring than thought when the network was first conceived. To address the growing problem, a group of scientists in both the monitoring and the isotope production communities have come together to attempt to find scientific and pragmatic ways to address the emissions problems, recognizing that medical isotope production should not be adversely affected, while monitoring for nuclear explosions should remain effective as isotope production grows, changes, and spreads globally. (author)

Method of conversion of caustic liquid radioactive wastes containing sodium nitrates into solid insoluble products

International Nuclear Information System (INIS)

Barney, G.S.; Brownell, L.E.

1975-01-01

A proposal is made to convert caustic, liquid, radioactive wastes containing sodium nitrate into a solid product by reaction with powdered aluminium silicate at temperatures between 30 0 and 100 0 C, which is practically insoluble (10 -7 to 10 -10 g/cm 2 -day) and is thermally stable. A cancrinite is formed which binds the radioactive salts in the cage-like structure of its crystal lattice. The method is also suitable for liquid wastes from the Purex method as well as for wastes containing fission products of Cs 137 and Sr 90 in concentrations of 0.37 M to 0.01 M. Numerous detailed examples explain the invention. (UW/LH) [de

Radioactive material handling for radiopharmaceutical production

International Nuclear Information System (INIS)

Anwar Abd Rahman; Rosli Darmawan; Mohd Khairi Mohd Said; Mohd Arif Hamzah; Mohd Fadil Ismail; Mohd Nor Atan; Mohd Azam Safawi Omar; Zulkifli Hashim; Wan Anuar Wan Awang

2005-01-01

Construction of clean room at Block 21 had changed the flow of radioactive material Moly-99 into the hotcell. The existing flow which use the transport cask cannot be used in order to prevent the clean room from contamination. Therefore, the new technique which consist of robotic, pneumatic and transfer box system had been introduced to transfer the radioactive source into the hotcell without going through the clean room.This technique that has been introduced provides safety where the radiation workers control the transfer process by using remote system. (Author)

Utilization of tropical crop residues and agroindustrial by-products in animal nutrition. Constraints and perspectives

International Nuclear Information System (INIS)

Preston, T.R.; Parra, R.

1983-01-01

The importance of by-products and crop residues as animal feeds is increasing steadily. This is a consequence of the increasing demand for cereal grains as both human and animal (chiefly poultry) food, and the increasing demand for energy coupled with decreasing availability of fossil fuels. The effects of these two trends are that primary use of land for livestock production (usually grazing systems) will steadily diminish; at the same time, sources of biomass will increase in importance as renewable energy sources, and greater emphasis will be placed on draught animal power. Most by-products and crop residues are fibrous and therefore of only low to moderate nutritive value, or have special physical and chemical characteristics making them difficult to incorporate in conventional ''balanced'' rations. Such feed raw materials may need special processing and/or special forms of supplementation if they are to be used efficiently. It is hypothesized that industrial by-products and crop residues will be more efficiently utilized if they are incorporated in diversified and integrated production systems, i.e. (a) livestock production is integrated with production of cash crops both for food and fuel; (b) different livestock species are utilized in the same enterprise in a complementary way; (c) livestock feeding is based on crop residues (energy) supplemented with protein-rich forages and aquatic plants; and (d) animal wastes are recycled and used for food, fertilizer and fuel. This strategy is particularly suitable for the conditions in (i) tropical countries, whose climate favours high crop/biomass yields per unit area and ease of fermentation of organic wastes, and (ii) family farms, for which diversification means greater opportunity for self-sufficiency and increased possibilities for use of family resources. (author)

Long lived isotopes in the Chernobyl radioactive cloud at Cracow

International Nuclear Information System (INIS)

Mietelski, J.W.; Broda, R.; Sieniawski, J.

1988-01-01

The analysis of the residual gamma radioactivity in the air filters exposed during the passage of the Chernobyl radioactive cloud over Cracow area gave data on variation in time of the relative contribution of long lived radioisotopes. Conclusions on transport properties of some elements are deduced from the obtained results. 10 refs., 5 figs. (author)

Impact of toxic heavy metals and pesticide residues in herbal products

Directory of Open Access Journals (Sweden)

Nema S. Shaban

2016-03-01

Full Text Available Medicinal plants have a long history of use in therapy throughout the world and still make an important part of traditional medicine. The World Health Organization (WHO estimates that 65%–80% of the world's populations depend on the herbal products as their primary form of health care. This review is conducted to provide a general idea about chemical contaminants such as heavy metals and pesticide residues as major common contaminants of the herbal medicine, which impose serious health risks to human health. Additionally, we aim to provide different analytical methods for analysis of heavy metals and pesticide residues in the herbal medicine.

Carbaryl residues in maize and processed products

International Nuclear Information System (INIS)

Qureshi, M.J.; Sattar, A. Jr.; Naqvi, M.H.

1981-01-01

Carbaryl residues in two local maize varieties were determined using a colorimetric method. No significant differences were observed for residues of the two varieties which ranged between 12.0 to 13.75 mg/kg in the crude oil, and averaged 1.04 and 0.67 mg/kg in the flour and cake respectively. In whole maize plants, carbaryl residues declined to approximately 2 mg/kg 35 days after treatment. Cooking in aqueous, oil or aqueous-oil media led to 63-83% loss of carbaryl residues, after 30 minutes. (author)

Analyzing key constraints to biogas production from crop residues and manure in the EU—A spatially explicit model

Science.gov (United States)

Persson, U. Martin

2017-01-01

This paper presents a spatially explicit method for making regional estimates of the potential for biogas production from crop residues and manure, accounting for key technical, biochemical, environmental and economic constraints. Methods for making such estimates are important as biofuels from agricultural residues are receiving increasing policy support from the EU and major biogas producers, such as Germany and Italy, in response to concerns over unintended negative environmental and social impacts of conventional biofuels. This analysis comprises a spatially explicit estimate of crop residue and manure production for the EU at 250 m resolution, and a biogas production model accounting for local constraints such as the sustainable removal of residues, transportation of substrates, and the substrates’ biochemical suitability for anaerobic digestion. In our base scenario, the EU biogas production potential from crop residues and manure is about 0.7 EJ/year, nearly double the current EU production of biogas from agricultural substrates, most of which does not come from residues or manure. An extensive sensitivity analysis of the model shows that the potential could easily be 50% higher or lower, depending on the stringency of economic, technical and biochemical constraints. We find that the potential is particularly sensitive to constraints on the substrate mixtures’ carbon-to-nitrogen ratio and dry matter concentration. Hence, the potential to produce biogas from crop residues and manure in the EU depends to large extent on the possibility to overcome the challenges associated with these substrates, either by complementing them with suitable co-substrates (e.g. household waste and energy crops), or through further development of biogas technology (e.g. pretreatment of substrates and recirculation of effluent). PMID:28141827

Analyzing key constraints to biogas production from crop residues and manure in the EU-A spatially explicit model.

Science.gov (United States)

Einarsson, Rasmus; Persson, U Martin

2017-01-01

This paper presents a spatially explicit method for making regional estimates of the potential for biogas production from crop residues and manure, accounting for key technical, biochemical, environmental and economic constraints. Methods for making such estimates are important as biofuels from agricultural residues are receiving increasing policy support from the EU and major biogas producers, such as Germany and Italy, in response to concerns over unintended negative environmental and social impacts of conventional biofuels. This analysis comprises a spatially explicit estimate of crop residue and manure production for the EU at 250 m resolution, and a biogas production model accounting for local constraints such as the sustainable removal of residues, transportation of substrates, and the substrates' biochemical suitability for anaerobic digestion. In our base scenario, the EU biogas production potential from crop residues and manure is about 0.7 EJ/year, nearly double the current EU production of biogas from agricultural substrates, most of which does not come from residues or manure. An extensive sensitivity analysis of the model shows that the potential could easily be 50% higher or lower, depending on the stringency of economic, technical and biochemical constraints. We find that the potential is particularly sensitive to constraints on the substrate mixtures' carbon-to-nitrogen ratio and dry matter concentration. Hence, the potential to produce biogas from crop residues and manure in the EU depends to large extent on the possibility to overcome the challenges associated with these substrates, either by complementing them with suitable co-substrates (e.g. household waste and energy crops), or through further development of biogas technology (e.g. pretreatment of substrates and recirculation of effluent).

Analyzing key constraints to biogas production from crop residues and manure in the EU-A spatially explicit model.

Directory of Open Access Journals (Sweden)

Rasmus Einarsson

Full Text Available This paper presents a spatially explicit method for making regional estimates of the potential for biogas production from crop residues and manure, accounting for key technical, biochemical, environmental and economic constraints. Methods for making such estimates are important as biofuels from agricultural residues are receiving increasing policy support from the EU and major biogas producers, such as Germany and Italy, in response to concerns over unintended negative environmental and social impacts of conventional biofuels. This analysis comprises a spatially explicit estimate of crop residue and manure production for the EU at 250 m resolution, and a biogas production model accounting for local constraints such as the sustainable removal of residues, transportation of substrates, and the substrates' biochemical suitability for anaerobic digestion. In our base scenario, the EU biogas production potential from crop residues and manure is about 0.7 EJ/year, nearly double the current EU production of biogas from agricultural substrates, most of which does not come from residues or manure. An extensive sensitivity analysis of the model shows that the potential could easily be 50% higher or lower, depending on the stringency of economic, technical and biochemical constraints. We find that the potential is particularly sensitive to constraints on the substrate mixtures' carbon-to-nitrogen ratio and dry matter concentration. Hence, the potential to produce biogas from crop residues and manure in the EU depends to large extent on the possibility to overcome the challenges associated with these substrates, either by complementing them with suitable co-substrates (e.g. household waste and energy crops, or through further development of biogas technology (e.g. pretreatment of substrates and recirculation of effluent.

Biodegradation of the alkaline cellulose degradation products generated during radioactive waste disposal.

Science.gov (United States)

Rout, Simon P; Radford, Jessica; Laws, Andrew P; Sweeney, Francis; Elmekawy, Ahmed; Gillie, Lisa J; Humphreys, Paul N

2014-01-01

The anoxic, alkaline hydrolysis of cellulosic materials generates a range of cellulose degradation products (CDP) including α and β forms of isosaccharinic acid (ISA) and is expected to occur in radioactive waste disposal sites receiving intermediate level radioactive wastes. The generation of ISA's is of particular relevance to the disposal of these wastes since they are able to form complexes with radioelements such as Pu enhancing their migration. This study demonstrates that microbial communities present in near-surface anoxic sediments are able to degrade CDP including both forms of ISA via iron reduction, sulphate reduction and methanogenesis, without any prior exposure to these substrates. No significant difference (n = 6, p = 0.118) in α and β ISA degradation rates were seen under either iron reducing, sulphate reducing or methanogenic conditions, giving an overall mean degradation rate of 4.7 × 10(-2) hr(-1) (SE ± 2.9 × 10(-3)). These results suggest that a radioactive waste disposal site is likely to be colonised by organisms able to degrade CDP and associated ISA's during the construction and operational phase of the facility.

Treatment and immobilization of intermediate-level radioactive wastes

International Nuclear Information System (INIS)

Lerch, R.E.; Greenhalgh, W.O.; Partridge, J.A.; Richardson, G.L.

1979-01-01

A new program underway at the Hanford Engineering Development Laboratory (HEDL) to develop and demonstrate treatment and immobilization technologies for intermediate-level wastes (ILW) generated in the nuclear fuel cycle is discussed. ILW are defined as those liquid and solid radioactive wastes, other than high-level wastes and fuel cladding hulls, that in packaged form have radiation dose readings greater than 200 millirem/hr at the packaged surface and 10 millirem/hr at three feet from the surface. The IAEA value of 10 4 Ci/m 3 for ILW defines the upper limit. For comparative purposes, reference is also made to certain aspects of low-level radioactive wastes (LLW). Initial work has defined the sources, quantities and types of wastes which comprise ILW. Because of the wide differences in composition (e.g., acids, salt solutions, resins and zeolites, HEPA filters, etc.) the wastes may require different treatments, particularly those wastes containing volatile contaminants. The various types of ILW have been grouped into categories amenable to similar treatment. Laboratory studies are underway to define treatment technologies for liquid ILW which contain volatile contaminants and to define immobilization parameters for the residues resulting from treatment of ILW. Immobilization agents initially being evaluated for the various residues include cement, urea-formaldehyde, and bitumen although other immobilization agents will be studied. The program also includes development of acceptable test procedures for the final immobilized products as well as development of proposed criteria for storage, transportation, and disposal of the immobilized ILW

Incorporation of carbohydrate residues into peroxidase isoenzymes in horseradish roots.

Science.gov (United States)

Lew, J Y; Shannon, L M

1973-11-01

Sliced root tissue of the horseradish plant (Armoracia rusticana), when incubated with mannose-U-(14)C, incorporated radioactivity into peroxidase isoenzymes. Over 90% of the radioactivity in the highly purified peroxidase isoenzymes was present in the neutral sugar residues of the molecule, i.e. fucose, arabinose, xylose, mannose. When the root slices were incubated simultaneously with leucine-4,5-(3)H and mannose-U-(14)C, cycloheximide strongly inhibited leucine incorporation into the peptide portion of peroxidase isoenzymes but had little effect on the incorporation of (14)C into the neutral sugars. These results indicated that synthesis of the peptide portion of peroxidase was completed before the monosaccharide residues were attached to the molecule. This temporal relationship between the synthesis of protein and the attachment of carbohydrate residues in the plant glycoprotein, horseradish peroxidase, appears to be similar to that reported for glycoprotein biosynthesis in many mammalian systems.

Benchmark calculations on residue production within the EURISOL DS project; Part I: thin targets

CERN Document Server

David, J.C; Boudard, A; Doré, D; Leray, S; Rapp, B; Ridikas, D; Thiollière, N

Report on benchmark calculations on residue production in thin targets. Calculations were performed using MCNPX 2.5.0 coupled to a selection of reaction models. The results were compared to nuclide production cross-sections measured in GSI in inverse kinematics

Evaluation of radioactive inventory of nuclear ship MUTSU

International Nuclear Information System (INIS)

Adachi, M.

1995-01-01

The operation of the Nuclear Ship MUTSU was terminated in January 1992. Radioactivities and dose rates on the surfaces of reactor components were measured in order to estimate the residual radioactive inventory in the MUTSU. The predicted radioactive inventory due to neutron activation was calculated by using a computer code systems. The results show good correlation between predicted and measured values radioactivities in the core baffle plate. The radioactive inventory was estimated to be 8.4 x 10 14 Bq as of 1.5 years from the final shutdown of reactor operation. The contamination in reactor components was estimated from the contamination level measured in the Japan Power Demonstration Reactor (JPDR), from which the dose rates in the reactor room were calculated. The radioactive inventory due to contamination was estimated at 3.4 x 10 10 Bq. Some difference was found between these calculations and measurements. (Author)

Induced radioactivity in the target station and decay tunnel from a 4MW proton beam

CERN Document Server

Agosteo, S; Otto, T; Silari, Marco

2003-01-01

An important aspect of a future CERN Neutrino Factory is the material activation arising from a 2.2 GeV, 4 MW proton beam striking a mercury target. A first estimation of the hadronic inelastic interactions and the production of residual nuclei in the target, the magnetic horn, the decay tunnel, the surrounding rock and a downstream dump has been performed by the Monte Carlo hadronic cascade code FLUKA. The aim is both to assess the dose equivalent rate to be expected during maintenance work and to evaluate the amount of residual radioactivity, which will have to be disposed of after the facility has ceased operation. This paper discusses the first results of such calculations.

Monitoring of radioactive ferrous scarp and products, current practices and regulatory problems in North-Eastern Italy

International Nuclear Information System (INIS)

Barbina, V.; Bianco, L.

1997-01-01

Radioactive scrap metal is a major source of concern among the steel industries of northeastern Italy, since most of the scrap supply comes from east-European countries and may originate from dismantled nuclear installations or dismissed radioactive devices. In this respect reliable monitoring procedures and consistent regulations are essential to face the many economic, legal and safety problems involved in the control and management of radioactive scrap and products. The authors describe the monitoring methods developed in more than two years practice at the steel works Ferriere Nord, Osoppo UD, Italy, as a realistic compromise between reliability, radiation protection and cost. They also discuss the drawbacks sometimes due to the lack of coherent monitoring protocols and exemption levels in Italian regulations, which leave some ways out for the uncontrolled recycling of radioactive metal scrap. (author)

Study of the spallation residues in the reaction Au (800 MeV/nucleon) + p

International Nuclear Information System (INIS)

Mustapha, Brahim

1999-01-01

As a neutron source, the spallation reaction is of importance for different fields of research and for a possible hybrid reactor. The study of spallation residues, their cross sections and their energetic properties, is necessary for such applications and for a better understanding of this process. Several studies of spallation products were done using spectroscopic methods. Only radioactive nuclides were detected. Aiming at a more precise measurement, covering the whole range of spallation residues, this study was done using the reverse kinematics method. A liquid hydrogen target was irradiated by an 800 MeV/nucleon gold beam. The produced nuclei were detected in flight before any radioactive decay with about 10% precision. Independent cross section were then obtained. Velocity distributions were completely reconstructed. In their present forms, the theoretical calculations based upon the two-step model, 'intra-nuclear cascade' + 'evaporation', are unable to reproduce the whole set of experimental aspects. An inter-comparison using different INC/EVA combinations permitted to identify the more significant points in these calculations. The important behaviour of this codes were examined. Due to compensation effects between both steps, cascade and evaporation, this study did not lead to a definite conclusion. (author)

Status of ecosystems in radioactive waste reservoirs of the Mayak Production Association in 2009.

Science.gov (United States)

Pryakhin, Evgeny A; Tryapitsina, Galina A; Deryabina, Larisa V; Atamanyuk, Natalia I; Stukalov, Pavel M; Ivanov, Ivan A; Kostyuchenko, Vladimir A; Akleyev, Alexander V

2012-07-01

Liquid radioactive waste from the Mayak Production Association (Chelyabinsk Region, Russia) is contained in industrial reservoirs (R-11, R-10, R-4, R-17, and R-9) that have different levels of radioactive contamination, increased from R-11 to R-17. A study of the ecosystems in these reservoirs was performed in 2009 to determine if there was any association with the level of contamination. No significant change in the status of biota was found in the reservoir with the lowest radionuclide concentrations (R-11) in comparison to other reservoirs in the region with a similar geography that are unaffected by radioactive contamination. In reservoir R-10, changes in the zoobenthos indices were registered. In reservoir R-4, changes in the zoobenthos and zooplankton communities were registered. In reservoir R-17, there was no ichthyofauna, but strong changes in the phytoplankton, zooplankton, and zoobenthos communities were registered. In reservoir R-9, under the conditions of the heaviest radioactive contamination of water ecosystems in the biosphere, there was no ichthyofauna, and phytoplankton and zooplankton consisted of almost a monoculture of cyanobacteriae and rotifers.

Development of an ASTM standard glass durability test, the Product Consistency Test (PCT), for high level radioactive waste glass

International Nuclear Information System (INIS)

Jantzen, C.M.; Bibler, N.E.; Beam, D.C.; Ramsey, W.G.

1994-01-01

The nation's first, and the world's largest, facility to immobilize high-level nuclear waste in durable borosilicate glass has started operation at the Savannah River Site (SRS) in Aiken, South Carolina. The product specifications on the glass wasteform produced in the Defense Waste Processing Facility (DWPF) required extensive characterization of the glass product before actual production began and for continued characterization during production. To aid in this characterization, a glass durability (leach) test was needed that was easily reproducible, could be performed remotely on highly radioactive samples, and could yield results rapidly. Several standard leach tests were examined with a variety of test configurations. Using existing tests as a starting point, the DWPF Product Consistency Test (PCT was developed in which crushed glass samples are exposed to 90 ± 2 degree C deionized water for seven days. Based on extensive testing, including a seven-laboratory round robin and confirmatory testing with radioactive samples, the PCT is very reproducible, yields reliable results rapidly, and can be performed in shielded cell facilities with radioactive samples

Radioactive characteristics of spent fuels and reprocessing products in thorium fueled alternative cycles

International Nuclear Information System (INIS)

Maeda, Mitsuru

1978-09-01

In order to provide one fundamental material for the evaluation of Th cycle, compositions of the spent fuels were calculated with the ORIGEN code on following fuel cycles: (1) PWR fueled with Th- enriched U, (2) PWR fueled with Th-denatured U, (3) CANDU fueled with Th-enriched U and (4) HTGR fueled with Th-enriched U. Using these data, product specifications on radioactivity for their reprocessing were calculated, based on a criterion that radioactivities due to foreign elements do not exceed those inherent in nuclear fuel elements, due to 232 U in bred U or 228 Th in recovered Th, respectively. Conclusions are as the following: (1) Because of very high contents of 232 U and 228 Th in the Th cycle fuels from water moderated reactors, especially from PWR, required decontamination factors for their reprocessing will be smaller by a factor of 10 3 to 10 4 , compared with those from U-Pu fueled LWR cycle. (2) These less stringent product specifications on the radioactivity of bred U and recovered Th will justify introduction of some low decontaminating process, with additional advantage of increased proliferation resistance. (3) Decontamination factors required for HTGR fuel will be 10 to 30 times higher than for the other fuels, because of less 232 U and 228 Th generation, and higher burn-up in the fuel. (author)