WorldWideScience

Sample records for des effluents liquides

  1. Methanization of industrial liquid effluents; Methanisation des effluents industriels liquides

    Energy Technology Data Exchange (ETDEWEB)

    Frederic, S.; Lugardon, A. [Societe Naskeo Environnement, 92 - Levallois-Perret (France)

    2007-09-15

    In a first part, this work deals with the theoretical aspects of the methanization of the industrial effluents; the associated reactional processes are detailed. The second part presents the technological criteria for choosing the methanization process in terms of the characteristics of the effluent to be treated. Some of the methanization processes are presented with their respective advantages and disadvantages. At last, is described the implementation of an industrial methanization unit. The size and the main choices are detailed: the anaerobic reactor, the control, the valorization aspects of the biogas produced. Some examples of industrial developments illustrate the different used options. (O.M.)

  2. Impacts des effluents liquides industriels sur l'environnement urbain ...

    African Journals Online (AJOL)

    industrialisation l'un des maillons essentiels du développement, après le succès de l'agriculture. Mais la mise en oeuvre de cette politique pose parfois des problèmes d'environnement à Abidjan. La présente étude a pour objectif principal ...

  3. Recovery of sludge from the treatment of liquid radioactive effluents by co-precipitation with calcium carbonate: laboratory study; Recuperation des boues de traitement des effluents radioactifs liquides par coprecipitation avec le carbonate de calcium: etude de laboratoire

    Energy Technology Data Exchange (ETDEWEB)

    Patti, F.; Gailledreau, C.; Cohen, P.

    1961-02-24

    As during the treatment by co-precipitation with calcium carbonate of liquid radioactive residues, a partial decontamination can be obtained by simply agitating an already formed radioactive sludge with the effluent to be processed, the authors study whether it would be possible to first perform a co-precipitation with a lower dose of calcium carbonate and then to complete decontamination by agitating with an adequate quantity of sludge stored during preceding operations. The authors report the study of the influence of reactant quantity on the chemical treatment efficiency, of the evolution of the activity of a radioactive residual solution in contact with a precipitate, of the cleaner element, of a precipitate reuse, of the technological and economic aspects, and of another possibility of reduction of the precipitate volume [French] Dans le traitement par coprecipitation avec le carbonate de calcium des residus radioactifs liquides, une decontamination partielle peut etre obtenue en agitant simplement une boue radioactive deja formee avec l'effluent a traiter. En consequence, il pourrait etre possible d'effectuer d'abord une coprecipitation avec une dose plus faible de carbonate de calcium et de completer ensuite la decontamination en agitant le liquide avec une quantite convenable de boue stockee a partir d'operations precedentes. (auteurs)

  4. Liquid Effluent Retention Facility

    Data.gov (United States)

    Federal Laboratory Consortium — The Liquid Effluent Retention Facility (LERF) is located in the central part of the Hanford Site. LERF is permitted by the State of Washington and has three liquid...

  5. INEEL Liquid Effluent Inventory

    Energy Technology Data Exchange (ETDEWEB)

    Major, C.A.

    1997-06-01

    The INEEL contractors and their associated facilities are required to identify all liquid effluent discharges that may impact the environment at the INEEL. This liquid effluent information is then placed in the Liquid Effluent Inventory (LEI) database, which is maintained by the INEEL prime contractor. The purpose of the LEI is to identify and maintain a current listing of all liquid effluent discharge points and to identify which discharges are subject to federal, state, or local permitting or reporting requirements and DOE order requirements. Initial characterization, which represents most of the INEEL liquid effluents, has been performed, and additional characterization may be required in the future to meet regulations. LEI information is made available to persons responsible for or concerned with INEEL compliance with liquid effluent permitting or reporting requirements, such as the National Pollutant Discharge Elimination System, Wastewater Land Application, Storm Water Pollution Prevention, Spill Prevention Control and Countermeasures, and Industrial Wastewater Pretreatment. The State of Idaho Environmental Oversight and Monitoring Program also needs the information for tracking liquid effluent discharges at the INEEL. The information provides a baseline from which future liquid discharges can be identified, characterized, and regulated, if appropriate. The review covered new and removed buildings/structures, buildings/structures which most likely had new, relocated, or removed LEI discharge points, and at least 10% of the remaining discharge points.

  6. Continuously tritium monitoring of the pipe of liquid effluents at the Cea Cadarache; Controle en continu du tritium de la conduite des effluents liquides du CEA Cadarache

    Energy Technology Data Exchange (ETDEWEB)

    Pira, Y

    2004-07-01

    This report is oriented toward the radiation protection of environment that is an essential component of radiation protection. It is necessary to detect any solid, liquid or gaseous abnormal release and to find its origin. The present study bears on a detection instrument in continuously to find tritium in liquid effluents of the Cea Cadarache. After having study the functioning principle of this device, an evaluation of its performances has been realised ( back noise, yield, detection limit) and to a checking in real conditions of utilization. (N.C.)

  7. Liquid effluent at Dounreay

    International Nuclear Information System (INIS)

    Sinclair, N.R.

    1995-01-01

    This short paper reviews the liquid effluent treatment at the Dounreay site. The significant reductions in volume and activity discharged from the site to the environment have been achieved over the many years of operation, and some of the techniques are highlighted. The Regulator interaction and the effect on the environment is discussed, while some of the requirements of the Regulator are presented. (author)

  8. The main rules regarding the management of solid waste and liquid effluent contaminated during use at nuclear medicine departments; Les principales regles de gestion des dechets solides et des effluents liquides contamines dans les services de medecine nucleaire

    Energy Technology Data Exchange (ETDEWEB)

    Boudouin, E. [Autorite de Surete Nucleaire, Direction des rayonnements ionisants et de la sante, 75 - Paris (France)

    2011-02-15

    This article describes the key requirements applicable to the management of contaminated medical waste and effluent from hospitals and health care centres, and more especially from nuclear medicine departments that use radionuclides for the purposes of diagnosis (in vivo or in vitro) or in patient treatment. It also presents the key management regulations, making a distinction between contaminated solid waste and contaminated liquid waste from such nuclear medicine departments. (author)

  9. Waste Treatment Plant Liquid Effluent Treatability Evaluation

    International Nuclear Information System (INIS)

    LUECK, K.J.

    2001-01-01

    Bechtel National, Inc. (BNI) provided a forecast of the radioactive, dangerous liquid effluents expected to be generated by the Waste Treatment Plant (WTP). The forecast represents the liquid effluents generated from the processing of 25 distinct batches of tank waste through the WTP. The WTP liquid effluents will be stored, treated, and disposed of in the Liquid Effluent Retention Facility (LERF) and the Effluent Treatment Facility (ETF). Fluor Hanford, Inc. (FH) evaluated the treatability of the WTP liquid effluents in the LERFIETF. The evaluation was conducted by comparing the forecast to the LERFIETF treatability envelope, which provides information on the items that determine if a liquid effluent is acceptable for receipt and treatment at the LERFIETF. The WTP liquid effluent forecast is outside the current LERFlETF treatability envelope. There are several concerns that must be addressed before the WTP liquid effluents can be accepted at the LERFIETF

  10. Disposal of the radioactive effluents at the 'Commissariat a l'Energie Atomique'. Treatment leading to evacuation into a river; Probleme du rejet des residus radioactifs liquides au CEA. Traitements aboutissant a des rejets en riviere

    Energy Technology Data Exchange (ETDEWEB)

    Duhamel,; Menoux,; Candillon, [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    loaded water, 10) Impot elements other than Sr{sup 90} are also studied. (author) [French] Le probleme du traitement des residus radioactifs liquides au CEA est envisage sous l'angle du rejet ultime en riviere dans des conditions optima permettant de satisfaire aux Normes de la protection. 2) A Saclay, ou l'on ne dispose que d'un etang ou l'eau ne se renouvelle pas, les liquides epures sont envoyes par camion citerne a Fontenay-aux-Roses, ou ils sont deverses provisoirement - dans les egouts - en attendant qu'un point de rejet en Seine ait ete determine. 3) Au Bouchet, les eaux residuaires de l'Usine de traitement de minerais d'urano-thorianite devront etre traitees en deux temps de facon a separer le radium dans une premiere phase, ce qui facilitera l'epuration au cours de la deuxieme phase. 4) En vue des futurs rejets a Marcoule, une etude a ete conduite a Saclay, sur des effluents synthetiques - type Marcoule - ayant pour but de mettre au point des procedes d'elimination selective du Sr d'une part, du Cs d'autre part, par coprecipitation. 5) Dans le cas general du rejet ultime en riviere, les problemes suivants sont successivement envisages: - predilution entre les bassins de stockage des eaux epurees et le fleuve; - mode d'injection dans le fleuve; - dilution dans le fleuve (etude prealable par traceurs); - evolution de l'activite dans les eaux du fleuve (adsorption par les organismes inertes ou vivants, contamination des berges); - incidence sur le choix d'un site; - dilution isotopique. 6) Ce dernier probleme est specialement detaille. 7) La teneur de l'eau en un element donne conditionne la dilution isotopique de son isotope radioactif. L'analyse decelant une carence, il est possible d'y suppleer par des rejets d'isotope stable. 8) Cette methode conduit en certains cas a des analyses delicates (en particulier dans le cas du {sup 90}Sr), la teneur en isotope stable necessaire a une forte dilution isotopique restant faible (ce qui est d'ailleurs un avantage). 9

  11. Liquid Effluents Program mission analysis

    International Nuclear Information System (INIS)

    Lowe, S.S.

    1994-01-01

    Systems engineering is being used to identify work to cleanup the Hanford Site. The systems engineering process transforms an identified mission need into a set of performance parameters and a preferred system configuration. Mission analysis is the first step in the process. Mission analysis supports early decision-making by clearly defining the program objectives, and evaluating the feasibility and risks associated with achieving those objectives. The results of the mission analysis provide a consistent basis for subsequent systems engineering work. A mission analysis was performed earlier for the overall Hanford Site. This work was continued by a ''capstone'' team which developed a top-level functional analysis. Continuing in a top-down manner, systems engineering is now being applied at the program and project levels. A mission analysis was conducted for the Liquid Effluents Program. The results are described herein. This report identifies the initial conditions and acceptable final conditions, defines the programmatic and physical interfaces and sources of constraints, estimates the resources to carry out the mission, and establishes measures of success. The mission analysis reflects current program planning for the Liquid Effluents Program as described in Liquid Effluents FY 1995 Multi-Year Program Plan

  12. Legal provisions governing liquid effluents radiological monitoring

    International Nuclear Information System (INIS)

    Gans, I.; Ruehle, H.

    1985-01-01

    The KTA rule 1504 for radiological monitoring of liquid effluents from nuclear installations is explained. As there are no such rules published to date for establishments handling isotopes, some criteria are discussed which in the future ought to form part of a practical guide for liquid effluents monitoring in isotope handling installations. Monitoring measures described refer to liquid effluents from transfer containers, auxiliary cooling equipment, turbine buildings, main cooling installations, and waste air discharges from closed-circuit cooling systems. (DG) [de

  13. Suspended solids in liquid effluents

    International Nuclear Information System (INIS)

    McGrath, J.J.

    1988-06-01

    An international literature review and telephone mail survey was conducted with respect to technical and regulatory aspects of suspended solids in radioactive liquid wastes from nuclear power stations. Results of the survey are summarized and show that suspended solids are an important component of some waste streams. The data available, while limited, show these solids to be associated largely with corrosion products. The solids are highly variable in quantity, size and composition. Filtration is commonly applied for their removal from liquid effluents and is effective. Complex interactions with receiving waters can result in physical/chemical changes of released radionuclides and these phenomena have been seen as reason for not applying regulatory controls based on suspended solids content. 340 refs

  14. Liquid Effluent Retention Facility/Effluent Treatment Facility Hazards Assessment

    International Nuclear Information System (INIS)

    Simiele, G.A.

    1994-01-01

    This document establishes the technical basis in support of Emergency Planning activities for the Liquid Effluent Retention Facility and Effluent Treatment Facility the Hanford Site. The document represents an acceptable interpretation of the implementing guidance document for DOE ORDER 5500.3A. Through this document, the technical basis for the development of facility specific Emergency Action Levels and the Emergency Planning Zone is demonstrated

  15. Methanization of industrial liquid effluents

    International Nuclear Information System (INIS)

    Frederic, S.; Lugardon, A.

    2007-01-01

    In a first part, this work deals with the theoretical aspects of the methanization of the industrial effluents; the associated reactional processes are detailed. The second part presents the technological criteria for choosing the methanization process in terms of the characteristics of the effluent to be treated. Some of the methanization processes are presented with their respective advantages and disadvantages. At last, is described the implementation of an industrial methanization unit. The size and the main choices are detailed: the anaerobic reactor, the control, the valorization aspects of the biogas produced. Some examples of industrial developments illustrate the different used options. (O.M.)

  16. The treatment of effluents; Ameliorations apportees aux traitements des residus radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G; Rodier, J; Robien, E de; Fernandez, N [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-07-01

    resins are used in the sodium form; the regeneration is carried out using a sodium salt solution which, after decontamination by coprecipitation is used again. With this process it is possible to use a smaller volume of sludge. 2 - The use of a natural evaporator. This process uses atmospheric air which is not saturated with water vapour and which is at a normal temperature, in order to extract water from the aqueous effluents. (authors) [French] Depuis plusieurs annees, le Commissariat a l'Eneregie Atomique Francais s'est penche avec interet sur les problemes poses par les effluents radioactifs. Les hautes activites n'ayant pas encore recu de solution definitive, nous nous bornerons a traiter, dans cette communication, que des realisations et des recherches relatives aux effluents faiblement et moyennement actifs. Dans le domaine des realisations, diverses stations de traitement ont ete construites en France; nous en ferons une breve enumeration, tout en faisant ressortir les nouveautes les plus importantes. C'est ainsi que nous presenterons plus specialement les dernieres stations de traitement mises en oeuvre (Grenoble, Fontenay-aux-Roses, Cadarache). De I'ensemble de ces realisations nouvelles, nous traiterons d'une maniere un peu plus approfondie, les trois sujets suivants: 1 - Atelier de conditionnement par bitumage des boues provenant de la concentration des radio-nucleides. 2 - Atelier de traitement des dechets solides radioactifs et combustibles par incineration. 3 - Ensemble de concentration effluents liquides radioactifs par evaporation. Dans le domaine de la recherche, de nombreuses voies ont ete abordees; nous en ferons I'inventaire. Il s'agit, dans la plupart des cas, de la concentration des radio-nucleides en vue d'un stockage pratique et peu onereux, concentration associee a une decontamination efficace, et Ie meilleur marche possible, des liquides aqueux, en vue de leur rejet. Pour l'amelioration des traitements aboutissant a la concentration des radio

  17. Treatment of effluent at the Saclay Centre d'Etudes Nucleaires (1960); Le traitement des effluents du Centre d'Etudes Nucleaires de Saclay (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The Centre d'Etudes Nucleaires at Saclay possesses several installations from which liquid radioactive effluent is rejected, and it has thus been found necessary to construct a station for the purification of radioactive liquids and to settle various chemical, analytical and technological problems. This report describes, in the following order: - the disposal possibilities at the Centre d'Etudes Nucleaires, Saclay, - the effluents produced at the centre, - the set-up for collecting effluent, - treatment of the effluent, - results of these treatments. (author) [French] La presence, au Centre d'Etudes Nucleaires de Saclay, de plusieurs installations susceptibles de rejeter des effluents liquides radioactifs a necessite la construction d'une station d'epuration d'eaux radioactives et la mise au point de differents problemes chimiques, analytiques et technologiques. Dans ce rapport, nous exposerons successivement: - les possibilites de rejet du Centre d'Etudes Nucleaires de Saclay, - les effluents du centre, - le dispositif de collecte des effluents, - le traitement de ces effluents, - les resultats de ces traitements. (auteur)

  18. Liquid effluent processing group. Activity details 1963

    International Nuclear Information System (INIS)

    1964-08-01

    This report first gives a quantitative overview of volumes of effluents of high activity, medium activity and low activity which passed through the department for effluent processing. It also makes the distinction between the shape or type of container of these effluents. A table indicates their origin and another indicates their destination. The β and α decontamination rates are determined, and the assessment of stored aqueous and organic effluents on the 31 December 1963 is given. The next part proposes an assessment of laboratory activities: control operations (input controls, control of processed effluent before discarding), controls related to processing (processing types, radiochemical and chemical dosing performed on effluent mixes before processing). Tables indicate the characteristics of medium activity effluents collected in 1963, the results of high activity liquid analysis, and Beryllium dosing results. A summary of ALEA processing, a table of the characteristics of stored oils and solvents are given. The third part reports data related to transport activities, and various works performed in the Saclay plant to improve exploitation conditions and results

  19. Recycling liquid effluents in a ceramic industry

    International Nuclear Information System (INIS)

    Araujo Almeida, B.; Almeida, M.; Martins, S.; Alexandra Macarico, V.; Tomas da Fonseca, A.

    2016-01-01

    In this work is presented a study on the recycling of liquid effluents in a ceramic installation for sanitary industry. The effluents were characterized by X-ray diffraction and inductively coupled plasma to evaluate their compositions. It was also assessed the daily production rate. Several glaze-slurry mixtures were prepared and characterized according to procedures and equipment of the company's quality laboratory. The results show that for most of the properties, the tested mixtures exhibited acceptable performance. However, the pyro plasticity parameter is highly influenced by the glaze content and imposes the separation of glaze and slurry liquid effluents. In addition, it is necessary to invest on a storage plant, including tanks with constant stirring and a new pipeline structure to implement the reincorporation method on the slurry processing. (Author)

  20. Dosage of fission products in irradiated fuel treatment effluents (radio-chemical method); Dosage des produits de fission dans les effluents du traitement des combustibles irradies (methode radiochimique)

    Energy Technology Data Exchange (ETDEWEB)

    Auchapt, J [Commissariat a l' Energie Atomique, Marcoule (France). Centre d' Etudes Nucleaires

    1966-07-01

    The dosage methods presented here are applicable to relatively long-lived fission products present in the effluents resulting from irradiated fuel treatment processes (Sr - Cs - Ce - Zr - Nb - Ru - I). The methods are based on the same principle: - addition of a carrying-over agent - chemical separation over several purification stages, - determination of the chemical yield by calorimetry - counting of an aliquot liquid portion. (author) [French] Les methodes de dosage presentees concernent les produits de fission a vie relativement longue presents dans les effluents de traitement des combustibles irradies (Sr - Cs - Ce - Zr - Nb - Ru - I). Elles sont toutes basees sur le meme principe: - addition d'entraineur, - separation chimique en plusieurs stades de purification, - determination du rendement chimique par calorimetrie, - comptage d'une aliquote liquide. (auteur)

  1. Elimination of slightly radioactive liquid effluent by dilution. Its consequences (1960); Elimination par dilution d'effluents liquides faiblement radioactifs. Leurs consequences (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Bovard, P; Candillon, C [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    Nuclear centres often have to solve problems raised by the elimination of large volumes of slightly radioactive liquid effluent. As things stand at present, the method usually adopted consists in expelling this effluent into the main water system in order to dilute it to a maximum, and thus to lower its radioactive isotope concentration to below the norms imposed by the Public Health Service. This technique requires systematic checking of the water system and its dependences, and demands a thorough knowledge of adsorption and fixation processes. (author) [French] Les centres nucleaires ont frequemment a resoudre des problemes poses par l'elimination de volumes importants d'effluents liquides faiblement radioactifs. Dans l'etat actuel des choses, la solution la plus utilisee consiste a rejeter ces effluents dans le reseau hydrographique de maniere a les diluer au maximum et abaisser ainsi leurs teneurs en isotopes radioactifs au-dessous des normes imposees par la Sante Publique. Cette technique necessite un controle systematique du reseau et de ses dependances et demande une connaissance approfondie des processus d'adsorption et de fixation. (auteur)

  2. Alpha contaminated liquid effluent monitoring

    International Nuclear Information System (INIS)

    Aparo, M.; Mattia, B.; Bianchini, E.; Frazzoli, F.V.

    1987-01-01

    The present report takes into consideration the possibility to carry out an in-line control of activity in liquid streams of fuel cycle nuclear plants, epecially for waste streams. The instrument developed for this purpose, has been characterized by means of static and dinamic measurements with Pu and Am bearing solutions. The results so far obtained show that the minimum detectable Pu amount is about .01mg/l and that it is possible to apply such a technique as alarm system able to detect the overcoming of a present threshold of actinides concentrations. The report also presents an approach to the spectra deconvolution in order to determine the amount of single isotopes

  3. 200 Area Liquid Effluent Facilities -- Quality assurance program plan

    International Nuclear Information System (INIS)

    Fernandez, L.

    1995-01-01

    This Quality Assurance Program Plan (QAPP) describes the quality assurance and management controls used by the 200 Area Liquid Effluent Facilities (LEF) to perform its activities in accordance with DOE Order 5700.6C. The 200 Area LEF consists of the following facilities: Effluent Treatment Facility (ETF); Treated Effluent Disposal Facility (TEDF); Liquid Effluent Retention facility (LERF); and Truck Loading Facility -- (Project W291). The intent is to ensure that all activities such as collection of effluents, treatment, concentration of secondary wastes, verification, sampling and disposal of treated effluents and solids related with the LEF operations, conform to established requirements

  4. Disposal of the radioactive effluents at the 'Commissariat a l'Energie Atomique'. Treatment leading to evacuation into a river; Probleme du rejet des residus radioactifs liquides au CEA. Traitements aboutissant a des rejets en riviere

    Energy Technology Data Exchange (ETDEWEB)

    Duhamel; Menoux; Candillon [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    to find out in loaded water, 10) Impot elements other than Sr{sup 90} are also studied. (author) [French] Le probleme du traitement des residus radioactifs liquides au CEA est envisage sous l'angle du rejet ultime en riviere dans des conditions optima permettant de satisfaire aux Normes de la protection. 2) A Saclay, ou l'on ne dispose que d'un etang ou l'eau ne se renouvelle pas, les liquides epures sont envoyes par camion citerne a Fontenay-aux-Roses, ou ils sont deverses provisoirement - dans les egouts - en attendant qu'un point de rejet en Seine ait ete determine. 3) Au Bouchet, les eaux residuaires de l'Usine de traitement de minerais d'urano-thorianite devront etre traitees en deux temps de facon a separer le radium dans une premiere phase, ce qui facilitera l'epuration au cours de la deuxieme phase. 4) En vue des futurs rejets a Marcoule, une etude a ete conduite a Saclay, sur des effluents synthetiques - type Marcoule - ayant pour but de mettre au point des procedes d'elimination selective du Sr d'une part, du Cs d'autre part, par coprecipitation. 5) Dans le cas general du rejet ultime en riviere, les problemes suivants sont successivement envisages: - predilution entre les bassins de stockage des eaux epurees et le fleuve; - mode d'injection dans le fleuve; - dilution dans le fleuve (etude prealable par traceurs); - evolution de l'activite dans les eaux du fleuve (adsorption par les organismes inertes ou vivants, contamination des berges); - incidence sur le choix d'un site; - dilution isotopique. 6) Ce dernier probleme est specialement detaille. 7) La teneur de l'eau en un element donne conditionne la dilution isotopique de son isotope radioactif. L'analyse decelant une carence, il est possible d'y suppleer par des rejets d'isotope stable. 8) Cette methode conduit en certains cas a des analyses delicates (en particulier dans le cas du {sup 90}Sr), la teneur en isotope

  5. Removal of active species from liquid effluent

    International Nuclear Information System (INIS)

    Blake, N.J.; Ritchie, S.

    1992-01-01

    Experimental and theoretical assessments were made of recirculating liquid membrane technology applied to the removal of active species from liquid effluent. Caesium and strontium were extracted from neutral, aqueous liquor by di-(2-ethylhexyl) phosphate in odourless kerosine and subsequently stripped by nitric acid. Flowrates to the membrane modules influenced the extraction and stripping mass transfer coefficients (MTC) for caesium, but not strontium. The acid strength of the strip solution affected the stripping MTC. When both ions were co-processed, caesium transfer was retarded. Potassium cobalt ferrocyanide and polyantimonic acid were used as adsorbers for caesium and strontium respectively in the strip loop. Caesium was more quickly adsorbed than strontium. A scale-up assessment of a recirculating liquid membrane was performed and compared to SIXEP at Sellafield. (author)

  6. Liquid effluent retention facility dangerous waste permit application

    International Nuclear Information System (INIS)

    1991-06-01

    This appendix to the Liquid Effluent Retention Facility Dangerous Waste Permit Application contains pumps, piping, leak detection systems, geomembranes, leachate collection systems, earthworks and floating cover systems

  7. The effluent problem in a plutonium production centre; Probleme des effluents d'un centre de production de plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Galley, R; Cantel, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The first part of the report is devoted to generalities: the geographical situation of the Marcoule Centre, the sources of radio-active effluent, methods of treating this effluent. In the second part the authors gives a detailed description of the various installations in the Radio-active Effluent Treatment Station at the Marcoule Centre, and outline the conditions governing the rejection of treated effluent into the Rhone. A few lines are given to comparisons between the results obtained from the use of these installations up till may 1959 and the expected results published by the same authors at the Brussels Conference (1956). In conclusion the authors lay down some of the essential principles, applicable to the study of new installations. (author) [French] La premiere partie du rapport est consacree a quelques generalites: situation geographique du Centre de Marcoule, provenance des effluents radioactifs, methodes de traitement de ces effluents. Dans la seconde partie, les auteurs presentent une description detaillee des diverses installations de la Station de Traitement des Effluents radioactifs du Centre de Marcoule et precisent les conditions de rejet dans le Rhone des effluents radioactifs traites. Quelques lignes sont consacrees aux comparaisons entre les resultats de l'exploitation des installations jusqu'en mai 1959 et les previsions publiees par les memes auteurs a l'occasion de la Conference de Bruxelles (1956). En conclusion, les auteurs donnent quelques principes essentiels, applicables a l'etude de nouvelles installations. (auteur)

  8. Flow proportional sampling of low level liquid effluent

    International Nuclear Information System (INIS)

    Colley, D.; Jenkins, R.

    1989-01-01

    A flow proportional sampler for use on low level radioactive liquid effluent has been developed for installation on all CEGB nuclear power stations. The sampler, operates by drawing effluent continuously from the main effluent pipeline, through a sampler loop and returning it to the pipeline. The effluent in this loop is sampled by taking small, frequent aliquots using a linear acting shuttle valve. The frequency of operation of this valve is controlled by a flowmeter installed in the effluent line; sampling rate being directly proportional to effluent flowrate. (author)

  9. Structure of simple liquids; Structure des liquides simples

    Energy Technology Data Exchange (ETDEWEB)

    Blain, J F [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1969-07-01

    The results obtained by application to argon and sodium of the two important methods of studying the structure of liquids: scattering of X-rays and neutrons, are presented on one hand. On the other hand the principal models employed for reconstituting the structure of simple liquids are exposed: mathematical models, lattice models and their derived models, experimental models. (author) [French] On presente d'une part les resultats obtenus par application a l'argon et au sodium des deux principales methodes d'etude de la structure des liquides: la diffusion des rayons X et la diffusion des neutrons; d'autre part, les principaux modeles employes pour reconstituer la structure des liquides simples sont exposes: modeles mathematiques, modeles des reseaux et modeles derives, modeles experimentaux. (auteur)

  10. Liquid Effluent Monitoring Information System (LEMIS) System Construction

    International Nuclear Information System (INIS)

    Adams, R.T.

    1994-01-01

    The liquid effluent sampling program is part of the effort to minimize adverse environmental impact during the cleanup operation at the Hanford Site. Of the 33 Phase I and Phase II liquid effluents, all streams actively discharged to the soil column will be sampled. The Liquid Effluent Monitoring Information System (LEMIS) is being developed as the organized information repository facility in support of the liquid effluent monitoring requirements of the Tri-Party Agreement. It is necessary to provide an automated repository into which the results from liquid effluent sampling will be placed. This repository must provide for effective retention, review, and retrieval of selected sample data by authorized persons and organizations. This System Construction document is the aggregation of the DMR P+ methodology project management deliverables. Together they represent a description of the project and its plan through four Releases, corresponding to the definition and prioritization of requirements defined by the user

  11. Processing radioactive effluents with ion-exchanging resins: study of result extrapolation; Traitement des effluents radioactifs par resines echangeuses d'ions: etude de l'extrapolation des resultats

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G.

    1960-05-03

    As a previous study showed the ion-exchanging resins could be used in Saclay for the treatment of radioactive effluents, the author reports a study which aimed at investigating to which extent thus obtained results could be extrapolated to the case of higher industrial columns. The author reports experiments which aimed at determining extrapolation modes which could be used for columns of organic resin used for radioactive effluent decontamination. He notably studied whether the Hiester and Vermeulen extrapolation law could be applied. Experiments are performed at constant percolation flow rate, at varying flow rate, and at constant flow rate [French] Plusieurs etudes ont ete faites dans le but d'examiner les possibilites d'emploi des resines echangeuses d'ions pour le traitement des effluents radioactifs. Dans un rapport preliminaire, nous avons montre dans quelles limites un tel procede pouvait etre utilise au Centre d'Etudes Nucleaires de Saclay. Les essais ont ete effectues sur des petites colonnes de resine au laboratoire; il est apparu ensuite necessaire de prevoir dans quelle mesure les resultats ainsi obtenus peuvent etre extrapoles a des colonnes industrielles, de plus grande hauteur. Les experiences dont les resultats sont exposes dans ce rapport, ont pour but de determiner les modes d'extrapolation qui pourraient etre employes pour des colonnes de resine organique utilisees pour la decontamination d'effluents radioactifs. Nous avons en particulier recherche si la loi d'extrapolation de Hiester et Vermeulen qui donne de bons resultats dans le cas de fixation d'ions radioactifs en presence d'un ion macrocomposant sur des terres, pouvait etre appliquee. Les experiences, en nombre limite, ont montre que la loi d'extrapolation de Hiester et Vermeulen pouvait s'appliquer dans le cas de l'effluent considere quand les debits de percolation sont tres faibles; quand ils sont plus forts, les volumes de liquide percoles, a fixation egale, sont proportionnels aux

  12. WASTE TREATMENT PLANT (WTP) LIQUID EFFLUENT TREATABILITY EVALUATION

    International Nuclear Information System (INIS)

    LUECK, K.J.

    2004-01-01

    A forecast of the radioactive, dangerous liquid effluents expected to be produced by the Waste Treatment Plant (WTP) was provided by Bechtel National, Inc. (BNI 2004). The forecast represents the liquid effluents generated from the processing of Tank Farm waste through the end-of-mission for the WTP. The WTP forecast is provided in the Appendices. The WTP liquid effluents will be stored, treated, and disposed of in the Liquid Effluent Retention Facility (LERF) and the Effluent Treatment Facility (ETF). Both facilities are located in the 200 East Area and are operated by Fluor Hanford, Inc. (FH) for the US. Department of Energy (DOE). The treatability of the WTP liquid effluents in the LERF/ETF was evaluated. The evaluation was conducted by comparing the forecast to the LERF/ETF treatability envelope (Aromi 1997), which provides information on the items which determine if a liquid effluent is acceptable for receipt and treatment at the LERF/ETF. The format of the evaluation corresponds directly to the outline of the treatability envelope document. Except where noted, the maximum annual average concentrations over the range of the 27 year forecast was evaluated against the treatability envelope. This is an acceptable approach because the volume capacity in the LERF Basin will equalize the minimum and maximum peaks. Background information on the LERF/ETF design basis is provided in the treatability envelope document

  13. Étude des bactéries multirésistantes des effluents hospitaliers d'un ...

    African Journals Online (AJOL)

    SARAH

    30 sept. 2013 ... J. Appl. Biosci. 2013. Étude des bacteries multiresistantes des effluents hospitaliers de la ville d, Abidjan. 5459. Imipénème (10). IPM. 22. 17. Acinetobacter baumanii. Ticarcilline (75). TIC. 22. 22. Cefepime (30). FEP. 19. 19. Imipénème (10). IPM. 22. 17. Ciprofloxacine (5). CIP. 22. 19. Gentamicine (15). GM.

  14. Liquid effluent Sampling and Analysis Plan (SAP) implementation summary report

    International Nuclear Information System (INIS)

    Lueck, K.J.

    1995-01-01

    This report summarizes liquid effluent analytical data collected during the Sampling and Analysis Plan (SAP) Implementation Program, evaluates whether or not the sampling performed meets the requirements of the individual SAPs, compares the results to the WAC 173-200 Ground Water Quality Standards. Presented in the report are results from liquid effluent samples collected (1992-1994) from 18 of the 22 streams identified in the Consent Order (No. DE 91NM-177) requiring SAPs

  15. Waste analysis plan for the 200 area effluent treatment facility and liquid effluent retention facility

    International Nuclear Information System (INIS)

    Ballantyne, N.A.

    1995-01-01

    This waste analysis plan (WAP) has been prepared for startup of the 200 Area Effluent Treatment Facility (ETF) and operation of the Liquid Effluent Retention Facility (LERF), which are located on the Hanford Facility, Richland, Washington. This WAP documents the methods used to obtain and analyze representative samples of dangerous waste managed in these units, and of the nondangerous treated effluent that is discharged to the State-Approved Land Disposal System (SALDS). Groundwater Monitoring at the SALDS will be addressed in a separate plan

  16. Systems engineering implementation plan for the liquid effluents services program

    International Nuclear Information System (INIS)

    Lowe, S.S.

    1995-01-01

    A graded approach is being taken by the Liquid Effluents Services Program in implementing systems engineering because of the advanced state of the program. The approach is cost-effective and takes credit for related work already completed, yet retains the benefits of systems engineering. This plan describes how the Liquid Effluents Services Program will implement systems engineering so there is a common understanding. Systems engineering work to be performed and the products of that work are identified. The relation to the current planning process and integration with the sitewide systems engineering effort is described

  17. Order of the 10 january 2003 authorizing the national agency for the radioactive wastes management to follow the gaseous and liquid effluents release for the exploitation of the radioactive wastes storage center of the Manche; Arrete du 10 janvier 2003 autorisant l'Agence nationale pour la gestion des dechets radioactifs a poursuivre les rejets d'effluents gazeux et liquides pour l'exploitation du centre de stockage de dechets radioactifs de la Manche

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-01-01

    This document, took out from the Official Journal, is the law text relative to the order of the 10 january 2003 authorizing the national agency for the radioactive wastes management to follow the gaseous and liquid effluents release for the exploitation of the radioactive wastes storage center of the Manche. (A.L.B.)

  18. Towards a physical interpretation of third phase formation in liquid-liquid extraction. Application to the Diamex process for the treatment of high radioactive nuclear wastes; Vers une interpretation physique des phenomenes de troisieme phase en extraction liquide-liquide. Application au procede Diamex de traitement des effluents radioactifs de haute activite

    Energy Technology Data Exchange (ETDEWEB)

    Verdier-Erlinger, C

    1998-07-24

    Using SAXS, conductivity and phase behaviour determination we show that concentrated solutions of extractants are organised in reverse oligomeric aggregates which have many features in common with reverse micelles. The aggregation numbers of these reverse globular aggregates as well as their interaction potential are determined experimentally. The sticky sphere interaction is responsible for the de-mixing on the oil phase when in equilibrium with excess oil. Prediction of conductivity as well as formation condition for the third phase is possible using standard liquid theory applied to the reverse micelles. The attractive interaction, modeled with the sticky sphere model proposed by Baxter, is the balance of steric stabilisation introduced by the hydrophobic tails of the extracting molecule and the Van der Waals forces between the highly polarizable water core of the reverse molecule concentration, number of carbon atoms of aliphatic solvents, as well as proton and Neodymium cation concentration. It is shown that van der Waals interactions with a Hamaker constant of 2.5 kT explains the behaviour of DMDBTDMA in dodecane. (author) 184 refs.

  19. Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility

    Energy Technology Data Exchange (ETDEWEB)

    Coenenberg, J.G.

    1997-08-15

    The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, `operating` treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating

  20. Hanford Facility dangerous waste permit application, liquid effluent retention facility and 200 area effluent treatment facility

    International Nuclear Information System (INIS)

    Coenenberg, J.G.

    1997-01-01

    The Hanford Facility Dangerous Waste Permit Application is considered to 10 be a single application organized into a General Information Portion (document 11 number DOE/RL-91-28) and a Unit-Specific Portion. The scope of the 12 Unit-Specific Portion is limited to Part B permit application documentation 13 submitted for individual, 'operating' treatment, storage, and/or disposal 14 units, such as the Liquid Effluent Retention Facility and 200 Area Effluent 15 Treatment Facility (this document, DOE/RL-97-03). 16 17 Both the General Information and Unit-Specific portions of the Hanford 18 Facility Dangerous Waste Permit Application address the content of the Part B 19 permit application guidance prepared by the Washington State Department of 20 Ecology (Ecology 1987 and 1996) and the U.S. Environmental Protection Agency 21 (40 Code of Federal Regulations 270), with additional information needs 22 defined by the Hazardous and Solid Waste Amendments and revisions of 23 Washington Administrative Code 173-303. For ease of reference, the Washington 24 State Department of Ecology alpha-numeric section identifiers from the permit 25 application guidance documentation (Ecology 1996) follow, in brackets, the 26 chapter headings and subheadings. A checklist indicating where information is 27 contained in the Liquid Effluent Retention Facility and 200 Area Effluent 28 Treatment Facility permit application documentation, in relation to the 29 Washington State Department of Ecology guidance, is located in the Contents 30 Section. 31 32 Documentation contained in the General Information Portion is broader in 33 nature and could be used by multiple treatment, storage, and/or disposal units 34 (e.g., the glossary provided in the General Information Portion). Wherever 35 appropriate, the Liquid Effluent Retention Facility and 200 Area Effluent 36 Treatment Facility permit application documentation makes cross-reference to 37 the General Information Portion, rather than duplicating

  1. A risk-based approach to liquid effluent monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Hull, L.C.

    1995-10-01

    DOE Order 5400.1 identifies six objectives of a liquid effluent monitoring program. A strategy is proposed that meets these objective in one of two ways: (1) by showing that effluent concentrations are below concentration limits set by permits or are below concentrations that could cause environmental problems or (2) by showing that concentrations in effluent have not changed from a period when treatment processes were in control and there were no unplanned releases. The intensity of liquid effluent monitoring should be graded to the importance of the source being monitored. This can be accomplished by determining the risk posed by the source. A definition of risk is presented that defines risk in terms of the statistical probability of exceeding a release limit and the time available to recover from an exceedance of a release limit. Three examples are presented that show this approach to grading an effluent monitoring program can be implemented at the Idaho National Engineering Laboratory and will reduce monitoring requirements.

  2. A risk-based approach to liquid effluent monitoring

    International Nuclear Information System (INIS)

    Hull, L.C.

    1995-10-01

    DOE Order 5400.1 identifies six objectives of a liquid effluent monitoring program. A strategy is proposed that meets these objective in one of two ways: (1) by showing that effluent concentrations are below concentration limits set by permits or are below concentrations that could cause environmental problems or (2) by showing that concentrations in effluent have not changed from a period when treatment processes were in control and there were no unplanned releases. The intensity of liquid effluent monitoring should be graded to the importance of the source being monitored. This can be accomplished by determining the risk posed by the source. A definition of risk is presented that defines risk in terms of the statistical probability of exceeding a release limit and the time available to recover from an exceedance of a release limit. Three examples are presented that show this approach to grading an effluent monitoring program can be implemented at the Idaho National Engineering Laboratory and will reduce monitoring requirements

  3. Optimizing Liquid Effluent Monitoring at a Large Nuclear Complex

    International Nuclear Information System (INIS)

    Chou, Charissa J.; Johnson, V.G.; Barnett, Brent B.; Olson, Phillip M.

    2003-01-01

    Monitoring data for a centralized effluent treatment and disposal facility at the Hanford Site, a defense nuclear complex undergoing cleanup and decommissioning in southeast Washington State, was evaluated to optimize liquid effluent monitoring efficiency. Wastewater from several facilities is collected and discharged to the ground at a common disposal site. The discharged water infiltrates through 60 m of soil column to the groundwater, which eventually flows into the Columbia River, the second largest river in the contiguous United States. Protection of this important natural resource is the major objective of both cleanup and groundwater and effluent monitoring activities at the Hanford Site. Four years of effluent data were evaluated for this study. More frequent sampling was conducted during the first year of operation to assess temporal variability in analyte concentrations, to determine operational factors contributing to waste stream variability and to assess the probability of exceeding permit limits. Subsequently, the study was updated which included evaluation of the sampling and analysis regime. It was concluded that the probability of exceeding permit limits was one in a million under normal operating conditions, sampling frequency could be reduced, and several analytes could be eliminated, while indicators could be substituted for more expensive analyses. Findings were used by the state regulatory agency to modify monitoring requirements for a new discharge permit. The primary focus of this paper is on the statistical approaches and rationale that led to the successful permit modification and to a more cost-effective effluent monitoring program

  4. Analyse quantitative des effluents de pyrolyse en milieu ouvert et fermé Quantitative Analysis of Pyrolysis Effluents in an Open and Closed System

    Directory of Open Access Journals (Sweden)

    Behar F.

    2006-11-01

    Full Text Available Dans la première partie de l'article, nous décrivons une technique de pyrolyse en milieu ouvert qui permet de caractériser les matières organiques complexes comme le kérogène, le charbon, les asphaltènes de roche et d'huiles, les substances humiques et fulviques etc. Les effluents de pyrolyse sont récupérés et fractionnés quantitativement puis analysés par des techniques spécifiques comme la chromatographie en phase gazeuse et le couplage chromatographie/spectrométrie de masse. Dans la deuxième partie, est présentée une technique de pyrolyse en milieu fermé pour simuler au laboratoire l'évolution thermique des kérogènes, asphaltènes ou huiles. Nous nous sommes surtout attachés à dresser des bilans massiques et des bilans de l'hydrogène sur l'ensemble des produits de pyrolyse. Pour cela, nous avons distingué cinq classes de poids moléculaire croissant : C1, C2-C5, C6-C13, C14+ et coke. La récupération quantitative et la séparation de chacune des cinq fractions permet une analyse moléculaire détaillée de chacune d'elles. The first part of this article describes an open pyrolysis system in order to characterize complex organic matter such as kerogen, coal, rock and oil asphaltenes and humic substances, etc. Pyrolysis effluents are recovered, fractionated quantitatively by liquid chromatography, and then they are analyzed by specific techniques such as gas chromatography and chromatography/mass-spectrometry coupling. The second part describes a pyrolysis technique in a closed system, used for the laboratory simulation of the thermal evolution of kerogens, asphaltenes or oils. A special effort has been made to give the mass and hydrogen balances for all pyrolysis products. For this, five classes have been distinguised with increasing molecular weight: C1, C2-C5, C6-C13, C14+ and coke. The quantitative recovery and the separation of each of the five fractions is used to make a detailed molecular analysis of each of

  5. Diagnosis of water pollution caused by chemical effluents using hydro biological methods; Diagnostic de la pollution des eaux par les effluents chimiques au moyen des methodes hydrobiologiques

    Energy Technology Data Exchange (ETDEWEB)

    Simeon, C; Bonnefoy-Claudet, J [Commissariat a l' Energie Atomique, Pierrelatte (France). Centre d' Etudes Nucleaires

    1965-04-01

    Industrial plants which discharge chemical effluents into rivers are faced with a double problem. 1 - To avoid excessive pollution which leads to an important modification of the medium and to a poisoning of the aquatic fauna, and in particular to the killing of fish. These disadvantages are avoided by a treatment of the effluents, by calculating the minimum fatal doses and the limiting dilutions for fish, and by carrying out biological analyses and tests on the residual waters. 2 - To avoid provoking continuous, slow and insidious pollutions which are more difficult to detect and which would result in the gradual sterilization of receptive media. In order to estimate this possible influence, the authors have listed the aquatic fauna and flora found in the canal which was the object of the experiment, and have modified the Saprobies system due to Kolwickz. They have tried to detect the presence or absence of pollution by estimating the density of the phyto-plankton formed on submerged laminae (periphyton) and the specific variations in the alga of which these populations are made up. In this report are given details of the tests and of the first results obtained. (authors) [French] Les usines deversant dans les cours d'eaux des effluents chimiques se trouvent devant un double probleme. 1 - Eviter les pollutions aigues qui se traduisent par une modification importante du milieu et par l'empoisonnement de la faune aquatique et notamment la mort du poisson. On evite ces inconvenients en traitant les effluents, en calculant les doses minima mortelles et les dilutions limites pour le poisson, en surveillant les eaux residuaires par analyses et tests biologiques. 2 - Ne pas provoquer des pollutions chroniques, lentes, insidieuses, plus difficiles a mettre en evidence qui aboutiraient a la sterilisation progressive des milieux recepteurs. Pour apprecier cette influence eventuelle les auteurs ont inventorie la faune et la flore aquatique du canal, objet de l'experience et

  6. Diagnosis of water pollution caused by chemical effluents using hydro biological methods; Diagnostic de la pollution des eaux par les effluents chimiques au moyen des methodes hydrobiologiques

    Energy Technology Data Exchange (ETDEWEB)

    Simeon, C.; Bonnefoy-Claudet, J. [Commissariat a l' Energie Atomique, Pierrelatte (France). Centre d' Etudes Nucleaires

    1965-04-01

    Industrial plants which discharge chemical effluents into rivers are faced with a double problem. 1 - To avoid excessive pollution which leads to an important modification of the medium and to a poisoning of the aquatic fauna, and in particular to the killing of fish. These disadvantages are avoided by a treatment of the effluents, by calculating the minimum fatal doses and the limiting dilutions for fish, and by carrying out biological analyses and tests on the residual waters. 2 - To avoid provoking continuous, slow and insidious pollutions which are more difficult to detect and which would result in the gradual sterilization of receptive media. In order to estimate this possible influence, the authors have listed the aquatic fauna and flora found in the canal which was the object of the experiment, and have modified the Saprobies system due to Kolwickz. They have tried to detect the presence or absence of pollution by estimating the density of the phyto-plankton formed on submerged laminae (periphyton) and the specific variations in the alga of which these populations are made up. In this report are given details of the tests and of the first results obtained. (authors) [French] Les usines deversant dans les cours d'eaux des effluents chimiques se trouvent devant un double probleme. 1 - Eviter les pollutions aigues qui se traduisent par une modification importante du milieu et par l'empoisonnement de la faune aquatique et notamment la mort du poisson. On evite ces inconvenients en traitant les effluents, en calculant les doses minima mortelles et les dilutions limites pour le poisson, en surveillant les eaux residuaires par analyses et tests biologiques. 2 - Ne pas provoquer des pollutions chroniques, lentes, insidieuses, plus difficiles a mettre en evidence qui aboutiraient a la sterilisation progressive des milieux recepteurs. Pour apprecier cette influence eventuelle les auteurs ont inventorie la faune et la flore aquatique du canal, objet de l

  7. Inorganic ion exchangers. Application to liquid effluent processing

    International Nuclear Information System (INIS)

    Dozol, M.

    1983-10-01

    Main inorganic ion exchangers used for radioactive liquid effluents presented in this report are: synthetic and natural zeolites, in titanium oxides, titanates, niobates, tantalates, zirconates, some insoluble salts of zirconium, molybdenum and tin, heteropolyacids and polyantimonic acid. Properties of these ion exchangers are described: structure, adsoption, radiation effects and thermal stability, application to waste processing, radioactive waste storage uranium and cesium 137 recovery are evoked [fr

  8. Tritium liquid effluents from the Krsko NPP

    International Nuclear Information System (INIS)

    Savli, S.; Krizman, M.; Nemec, T.; Cindro, M.; Stritar, A.; Vokal Nemec, B.; Janzekovic, H.

    2007-01-01

    In the past, 12-months' fuel cycles in the Krsko NPP had not caused any problems regarding compliance with its Technical Specifications and license limits on liquid tritium releases (20 TBq/year, 8 TBq/three months). The first 18-months' fuel cycle, which was introduced in 2004, required fuel with higher enrichment, higher boron concentration in the primary coolant and more fuel rods with burnable poisons. In 2005, the NPP operated without refueling outage for the whole year and produced the highest amount of energy so far. Due to these facts and a few unplanned shutdowns and power reductions, production of tritium and releases increased strongly in 2005. As a result, the Krsko NPP hardly succeeded to stay within regulatory limits on tritium releases. However, the three-months' limit was exceeded in the first quarter of 2006. On the basis of conclusions acquired from the SNSA's study and practice of other European countries the SNSA considerably increased the annual limit of permitted liquid tritium releases (from 20 TBq to 45 TBq) and abolished the three-months' limit. At the same time, the SNSA reduced the limit of fission and activation products by halves. (author)

  9. A Study Of The Dilution Of Radio-Active Waste In The Rhone (1961); Etude de la dilution dans le rhone des effluents radioactifs du Centre de Marcoule (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J; Scheidhauer, J; Marichal, M; Court, R [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1961-07-01

    The discharge into the Rhone of liquid radio-active waste from the Marcoule Centre necessitates a large number of measurements, in particular chemical and radio-chemical analysis of the waste, itself and of the waters of the Rhone both above arid below the point of discharge. The results thus obtained during 1960 made it possible to evaluate the total amount of active waste discharged and its dilution in the receiving medium. A statistical study of the results of the analysis of the Rhone waters shows that a satisfactory dilution of the waste occurs rapidly; the experimental results obtained with an experimental discharge of rhodamine are thus confirmed. (authors) [French] Le rejet au Rhone des effluents radioactifs liquides produits sur le Centre de Marcoule donne lieu a un grand nombre de mesures et en particulier d'analyses chimiques et radio-chimiques des effluents eux-memes ainsi que des eaux du Rhone avant et apres rejet. Au cours de l'annee 1960, l'ensemble des resultats ainsi obtenus a permis de dresser un bilan des activites rejetees et de leur dispersion dans le milieu recepteur. Une etude statistique des resultats d'analyses des eaux du Rhone montre qu'une dilution satisfaisante des effluents s'effectue rapidement confirmant ainsi les resultats obtenus lors d'un rejet experimental de rhodamine. (auteurs)

  10. Bitumen coating of the radio-active sludges from the effluent treatment plant at the Marcoule centre. Review of the progress reports 1, 2, 3 and 4 (1963); Enrobage par le bitume des boues radioactives de la station de traitement des effluents du centre de Marcoule. Mise au point des etats d'avancement 1, 2, 3 et 4. (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J.; Lefillatre, G.; Scheidhauer, J. [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1963-07-01

    Besides the very high activity liquids containing fission products, the chemical treatment of irradiated fuels produces a large volume of aqueous effluents and solid waste of relatively low radioactivity. These weakly active products can be eliminated in the ground, in a hydrographic land system or in the sea. Techniques of evaporation, of resin concentration, and of coprecipitation give rise to inorganic sludges with a high water content. All these residues occupy a large volume and represent a far from negligible weight. In the case of the sludge, their relative fluidity necessitates a conditioning guaranteeing safe storage. The solution to the problem will consist in passing directly from a liquid or a suspension, to a solid whose structure is homogeneous and whose matter is inert with respect to the storage medium (soil, sea, etc. ). We have proposed to coat the radioactive products with bitumen. This article is designed to give a review of the studies undertaken on this method. It consists of a progress report rather than a final assessment. (authors) [French] En dehors des liquides de tres haute activite contenant des produits de fission, le traitement chimique des combustibles irradies produit un volume important d'effluents aqueux et de residus solides de radioactivite relativement faible. Ces produits, faiblement actifs, peuvent etre elimines dans le sol, dans un systeme hydrographique terrestre ou dans la mer. Les techniques d'evaporation, de concentration sur resine, de coprecipitation, permettent la decontamination prealable des liquides. La coprecipitation donne naissance a des boues minerales dont la teneur en eau est elevee. Tous ces residus occupent un volume important et representent un poids non negligeable. Dans le cas des boues, leur fluidite relative exige un conditionnement donnant toutes garanties de securite au stockage. La solution du probleme consistera a passer directement d'un liquide ou d'une suspension a un solide

  11. Bitumen coating of the radio-active sludges from the effluent treatment plant at the Marcoule centre. Review of the progress reports 1, 2, 3 and 4 (1963); Enrobage par le bitume des boues radioactives de la station de traitement des effluents du centre de Marcoule. Mise au point des etats d'avancement 1, 2, 3 et 4. (1963)

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J; Lefillatre, G; Scheidhauer, J [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1963-07-01

    Besides the very high activity liquids containing fission products, the chemical treatment of irradiated fuels produces a large volume of aqueous effluents and solid waste of relatively low radioactivity. These weakly active products can be eliminated in the ground, in a hydrographic land system or in the sea. Techniques of evaporation, of resin concentration, and of coprecipitation give rise to inorganic sludges with a high water content. All these residues occupy a large volume and represent a far from negligible weight. In the case of the sludge, their relative fluidity necessitates a conditioning guaranteeing safe storage. The solution to the problem will consist in passing directly from a liquid or a suspension, to a solid whose structure is homogeneous and whose matter is inert with respect to the storage medium (soil, sea, etc. ). We have proposed to coat the radioactive products with bitumen. This article is designed to give a review of the studies undertaken on this method. It consists of a progress report rather than a final assessment. (authors) [French] En dehors des liquides de tres haute activite contenant des produits de fission, le traitement chimique des combustibles irradies produit un volume important d'effluents aqueux et de residus solides de radioactivite relativement faible. Ces produits, faiblement actifs, peuvent etre elimines dans le sol, dans un systeme hydrographique terrestre ou dans la mer. Les techniques d'evaporation, de concentration sur resine, de coprecipitation, permettent la decontamination prealable des liquides. La coprecipitation donne naissance a des boues minerales dont la teneur en eau est elevee. Tous ces residus occupent un volume important et representent un poids non negligeable. Dans le cas des boues, leur fluidite relative exige un conditionnement donnant toutes garanties de securite au stockage. La solution du probleme consistera a passer directement d'un liquide ou d'une suspension a un solide dont la structure

  12. Removal of active species from liquid effluent

    International Nuclear Information System (INIS)

    Blake, N.J.; Ritchie, S.; Robinson, K.S.

    1990-08-01

    The extraction and stripping of a strontium feed solution at 1000ppm and pH 7 has been investigated using a recirculating liquid membrane system. Feed solution was circulated through the tube-side of a hollow fibre unit, contacting an extractant solution of 20% v/v di-(2-ethylhexyl) phosphate in odourless kerosine at the inner wall. The partition coefficient for this extraction was 56000. The extractant was then pumped to the shell-side of a second hollow fibre unit, containing the strip solution of nitric acid in the tube-side of the fibres. Strontium removal from the feed solution was virtually complete after one hour, but the stripping time scale was at least an order or magnitude longer. Flowrates of each phase did not appear to affect the overall mass transfer coefficients for extraction or stripping operations. The extraction coefficient based on the feed phase was estimated to be 3.9 x 10 -6 m s -1 . Stripping coefficients based on the strip phase were measured at 1.6 x 10 -9 and 2.2 x 10 -9 m s -1 for strip solutions of 0.1M and 1.0M nitric acid. These values compare reasonably well with published correlations. (author)

  13. Optimizing liquid effluent monitoring at a large nuclear complex.

    Science.gov (United States)

    Chou, Charissa J; Barnett, D Brent; Johnson, Vernon G; Olson, Phil M

    2003-12-01

    Effluent monitoring typically requires a large number of analytes and samples during the initial or startup phase of a facility. Once a baseline is established, the analyte list and sampling frequency may be reduced. Although there is a large body of literature relevant to the initial design, few, if any, published papers exist on updating established effluent monitoring programs. This paper statistically evaluates four years of baseline data to optimize the liquid effluent monitoring efficiency of a centralized waste treatment and disposal facility at a large defense nuclear complex. Specific objectives were to: (1) assess temporal variability in analyte concentrations, (2) determine operational factors contributing to waste stream variability, (3) assess the probability of exceeding permit limits, and (4) streamline the sampling and analysis regime. Results indicated that the probability of exceeding permit limits was one in a million under normal facility operating conditions, sampling frequency could be reduced, and several analytes could be eliminated. Furthermore, indicators such as gross alpha and gross beta measurements could be used in lieu of more expensive specific isotopic analyses (radium, cesium-137, and strontium-90) for routine monitoring. Study results were used by the state regulatory agency to modify monitoring requirements for a new discharge permit, resulting in an annual cost savings of US dollars 223,000. This case study demonstrates that statistical evaluation of effluent contaminant variability coupled with process knowledge can help plant managers and regulators streamline analyte lists and sampling frequencies based on detection history and environmental risk.

  14. Liquid Effluent Monitoring Program at the Pacific Northwest Laboratory

    International Nuclear Information System (INIS)

    Ballinger, M.Y.

    1995-05-01

    Pacific Northwest Laboratory (PNL) is conducting a program to monitor the waste water from PNL-operated research and development facilities on the Hanford Site. The purpose of the program is to collect data to assess administrative controls and to determine whether discharges to the process sewer meet sewer criteria. Samples have been collected on a regular basis from the major PNL facilities on the Hanford Site since March 1994. A broad range of analyses has been performed to determine the primary constituents in the liquid effluent. The sampling program is briefly summarized in the paper. Continuous monitoring of pH, conductivity, and flow also provides data on the liquid effluent streams. In addition to sampling and monitoring, the program is evaluating the dynamics of the waste stream with dye studies and is evaluating the use of newer technologies for potential deployment in future sampling/monitoring efforts. Information collected to date has been valuable in determining sources of constituents that may be higher than the Waste Acceptance Criteria (WAC) for the Treated Effluent Disposal Facility (TEDF). This facility treats the waste streams before discharge to the Columbia River

  15. Contribution to the study of maximum levels for liquid radioactive waste disposal into continental and sea water. Treatment of some typical samples; Contribution a l'etude des niveaux limites relatifs a des rejets d'effluents radioactifs liquides dans les eaux continentales et oceaniques. Traitement de quelques exemples types

    Energy Technology Data Exchange (ETDEWEB)

    Bittel, R; Mancel, J [Commissariat a l' Energie Atomique, 92 - Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires, departement de la protection sanitaire

    1968-10-01

    The most important carriers of radioactive contamination of man are the whole of foodstuffs and not only ingested water or inhaled air. That is the reason why, in accordance with the spirit of the recent recommendations of the ICRP, it is proposed to substitute the idea of maximum levels of contamination of water to the MPC. In the case of aquatic food chains (aquatic organisms and irrigated foodstuffs), the knowledge of the ingested quantities and of the concentration factors food/water permit to determinate these maximum levels, or to find out a linear relation between the maximum levels in the case of two primary carriers of contamination (continental and sea waters). The notion of critical food-consumption, critical radioelements and formula of waste disposal are considered in the same way, taking care to attach the greatest possible importance to local situations. (authors) [French] Les vecteurs essentiels de la contamination radioactive de l'homme sont les aliments dans leur ensemble, et non seulement l'eau ingeree ou l'air inhale. C'est pourquoi, en accord avec l'esprit des recentes recommandations de la C.I.P.R., il est propose de substituer aux CMA la notion de niveaux limites de contamination des eaux. Dans le cas des chaines alimentaires aquatiques (organismes aquatiques et aliments irrigues), la connaissance des quantites ingerees et celle des facteurs de concentration aliments/eau permettent de determiner ces niveaux limites dans le cas de deux vecteurs primaires de contamination (eaux continentales et eaux oceaniques). Les notions de regime alimentaire critique, de radioelement critique et de formule de rejets sont envisagees, dans le meme esprit, avec le souci de tenir compte le plus possible des situations locales. (auteurs)

  16. Seminar on long term research into liquid effluent treatment,

    International Nuclear Information System (INIS)

    Hooper, E.W.

    1987-02-01

    A one-day Seminar on Long Term Research into Liquid Waste Treatment was held at Harwell on 30th January 1986. The Seminar was sponsored by the Department of the Environment and was attended by ninety-five delegates representing industry, universities, DoE, CEGB and the AEA. The purpose of the meeting was to provide an opportunity for people working in the field of liquid effluent treatment to obtain up-to-date information on the nature and status of research being carried out in the United Kingdom. Nine presentations on research activity described work being undertaken on ultrafiltration and associated techniques, electrical processes and ion exchange. The presenters were from BNF plc, CEGB, Imperial College, University of Salford, University of Reading and from Harwell. (author)

  17. Computer software configuration management plan for 200 East/West Liquid Effluent Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Graf, F.A. Jr.

    1995-02-27

    This computer software management configuration plan covers the control of the software for the monitor and control system that operates the Effluent Treatment Facility and its associated truck load in station and some key aspects of the Liquid Effluent Retention Facility that stores condensate to be processed. Also controlled is the Treated Effluent Disposal System`s pumping stations and monitors waste generator flows in this system as well as the Phase Two Effluent Collection System.

  18. Computer software configuration management plan for 200 East/West Liquid Effluent Facilities

    International Nuclear Information System (INIS)

    Graf, F.A. Jr.

    1995-01-01

    This computer software management configuration plan covers the control of the software for the monitor and control system that operates the Effluent Treatment Facility and its associated truck load in station and some key aspects of the Liquid Effluent Retention Facility that stores condensate to be processed. Also controlled is the Treated Effluent Disposal System's pumping stations and monitors waste generator flows in this system as well as the Phase Two Effluent Collection System

  19. 200 area liquid effluent facility quality assurance program plan. Revision 1

    International Nuclear Information System (INIS)

    Sullivan, N.J.

    1995-01-01

    Direct revision of Supporting Document WHC-SD-LEF-QAPP-001, Rev. 0. 200 Area Liquid Effluent Facilities Quality Assurance Program Plan. Incorporates changes to references in tables. Revises test to incorporate WHC-SD-LEF-CSCM-001, Computer Software Configuration Management Plan for 200 East/West Liquid Effluent Facilities

  20. Environmental system applied to radioactive liquid effluent release

    International Nuclear Information System (INIS)

    Nisti, Marcelo Bessa

    2009-01-01

    The current environmental administration considers the productive activity as an environmental system, defined as a group of processes, interactions, parameters and factors involved in the production. This mastering dissertation evaluated the release of the liquid radioactive effluents at Instituto de Pesquisas Energeticas e Nucleares (IPEN), under a systemic environmental study. The study evaluated the source term at IPEN in the period from 2004 to 2008, making use of gamma-ray and alpha spectrometry, instrumental neutron activation analysis, liquid phase scintillation and atomic absorption spectrometry. The employed methodologies were verified using samples from the Intercomparison National Program - PNI/IRD and Reference Materials. The facilities that contributed the most in these releases were the Radiopharmaceutical Center (CR) and the Research Reactor Center (CRPq) with an average of 11,4% and 87,4%, respectively, relative to the present radioactive activity. The sewer system releases were within the radioactive protection regulations, showing the effectiveness of IPEN's Radioactive Effluents Monitoring Program. The concentration of the stable elements Ag, Cd, Cr, Fe, Mn, Ni, Pb and Zn was determined in the liquid effluent in ali the samples from the storage tanks TR1 and CR in the period from 2004 to 2008 and in some of the samples of other IPEN's facilities in the period from 2004 to 2007. Among the analyzed effluents, two samples were higher than the stable elements discharge standards established in the state of Sao Paulo, one sample was higher than the required value of the element cadmium and the other higher than required value of the element zinco The storage tank TR1 discharge flow was estimated in 10,9 ± 0,9 m3 h -1 . The dilution factor at discharge point E1 was estimated using a radiotracers the isotopes 3 H, 137 CS, 60 Co, 54 Mn and 65 Zn, which are commonly released into IPEN's sewer system. The executed radiotracer study was carried out

  1. Tests of the use of cation exchange organic resins for the decontamination of radioactive aqueous effluents; Essais d'emploi des resines organiques echangeuses de cations pour la decontamination des effluents aqueux radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Bourdrez, Jean; Girault, Jacques; Wormser, Gerald

    1962-12-14

    The authors report tests performed in laboratory and results obtained during an investigation of the use of synthetic ion exchangers for the decontamination of radioactive effluents of moderate activity level and with a non neglectable salt loading. Resins are used under sodium form and regenerated after each fixing operation. Once decontaminated and free of its disturbing ions, the regenerating agent (NaCl) is used for several operations. The authors present the used resins, the treated effluents, describe the tests, and discuss the obtained results [French] Dans ce rapport nous faisons le point des essais et resultats obtenus au laboratoire au cours d'une etude concernant l'utilisation des echangeurs d'ions synthetiques pour la decontamination des effluents radioactifs de niveau d'activite moyenne et de charge en sels non negligeable. Les resines sont employees sous forme sodique et regenerees apres chaque operation de fixation. Le regenerant decontamine et debarrasse de ses ions genants est utilise pour plusieurs operations d'elution. Les seuls residus a stocker proviennent d'une part eventuellement d'un pretraitement de l'effluent, d'autre part, dans tous les cas des precipites consecutifs a la purification de l'eluant dont le traitement chimique est plus aise et donne lieu a des boues beaucoup moins volumineuses qu'une coprecipitation effectuee sur la totalite de l'effluent. (auteurs)

  2. LIQUID EFFLUENT RETENTION FACILITY (LERF) BASIN 42 STUDIES

    International Nuclear Information System (INIS)

    DUNCAN JB

    2004-01-01

    This report documents laboratory results obtained under test plan RPP-21533 for samples submitted by the Effluent Treatment Facility (ETF) from the Liquid Effluent Retention Facility (LERF) Basin 42 (Reference 1). The LERF Basin 42 contains process condensate (PC) from the 242-A Evaporator and landfill leachate. The ETF processes one PC campaign approximately every 12 to 18 months. A typical PC campaign volume can range from 1.5 to 2.5 million gallons. During the September 2003 ETF Basin 42 processing campaign, a recurring problem with 'gelatinous buildup' on the outlet filters from 60A-TK-I (surge tank) was observed (Figure 1). This buildup appeared on the filters after the contents of the surge tank were adjusted to a pH of between 5 and 6 using sulfuric acid. Biological activity in the PC feed was suspected to be the cause of the gelatinous material. Due to this buildup, the filters (10 (micro)m CUNO) required daily change out to maintain process throughput

  3. Disposal of Low-Activity Liquid Effluents by Dilution

    Energy Technology Data Exchange (ETDEWEB)

    Bovard, P.; Candillon, C. [Atomic Energy Commission, Saclay (France)

    1960-07-01

    Nuclear centres are frequently faced with problems of disposal of sizeable quantities of low-activity liquid effluents. Under present conditions the most practicable solution seems to be to discharge them into a natural or artificial water system, so as to dilute them as much as possible and thus reduce their radioactive isotope content below the public health levels. This technique is employed by all nuclear centres in France, which use the following convenient outlets: Saclay: the artificial ponds made by Louis XIV to feed the great Versailles fountains; Fontenay-aux-Roses: the Paris sewer system; Grenoble: the river Isere; Marcoule: the river Rhone. Until 1957 the amount of waste was negligible. It is still very slight at the first three centres, only a few dozen millicuries a month. At Marcoule the activity of the effluents is somewhat greater, but the Rhone's rate of flow ensures a very low final content of radioactive elements. The increasing discharge of wastes into river systems calls for a close watch on changes in radioactivity in the environment (i.e. in air, water and soil), and especially on areas in which radioactive isotopes may accumulate. We have therefore made laboratory studies of the mechanics of radioactivity concentration, in order to improve our sampling methods and ascertain the movement of wastes.

  4. Biological treatment of the liquid effluents of a paper industry

    International Nuclear Information System (INIS)

    Mejia, Juan Felipe; Ramirez, Gladys Eugenia; Arias Zabala, Mario

    2001-01-01

    The objective of this paper is to determine the effect of the microorganisms Candida utilis and Candida tropicalis in the reduction of the chemical oxygen demand (COD) of the liquid effluents of a producing factory of paper kraft type, by means of fermentations made to pH of 5 and a 30 centigrade degrees during 6 days. The biological processing is preceded by a physicochemical process of directed acidulation to reduce pH of the effluent (liquor black) from its initial value, of approximately 13, to 5, in order to it is adapted for the growth of yeast. In this process, which forms precipitated, that is necessary to eliminate by centrifugation and filtration to facilitate the growth of the microorganisms, with is obtained one first removal of the COD of the order of 70 %. With the biological processing obtains for both yeasts a percentage of removal of 45 -50% of the COD surplus. The total removal of the COD, that is to say, obtained with the pre-cure and the fermentation it is of the order of 84% for the yeast. Additionally the possibility studied of implementing some complementary procedures to the biological processing, with a view to obtaining greater growth of yeast in the black liquor and thus obtaining additional reductions in the OCD of the same one

  5. LIQUID EFFLUENT RETENTION FACILITY (LERF) BASIN 42 STUDIES

    Energy Technology Data Exchange (ETDEWEB)

    DUNCAN JB

    2004-10-29

    This report documents laboratory results obtained under test plan RPP-21533 for samples submitted by the Effluent Treatment Facility (ETF) from the Liquid Effluent Retention Facility (LERF) Basin 42 (Reference 1). The LERF Basin 42 contains process condensate (PC) from the 242-A Evaporator and landfill leachate. The ETF processes one PC campaign approximately every 12 to 18 months. A typical PC campaign volume can range from 1.5 to 2.5 million gallons. During the September 2003 ETF Basin 42 processing campaign, a recurring problem with 'gelatinous buildup' on the outlet filters from 60A-TK-I (surge tank) was observed (Figure 1). This buildup appeared on the filters after the contents of the surge tank were adjusted to a pH of between 5 and 6 using sulfuric acid. Biological activity in the PC feed was suspected to be the cause of the gelatinous material. Due to this buildup, the filters (10 {micro}m CUNO) required daily change out to maintain process throughput.

  6. Dry washing: the solution for contaminated liquid effluent releases

    International Nuclear Information System (INIS)

    L'homme, D.; Trambouze, P.

    1998-01-01

    The release of wash water used for contaminated garments poses an ever-increasing problem on nuclear sites. Even though the radioactivity is low, it mixes with organic compounds, thus polluting a large quantity of liquid effluents. In many cases, several thousands of m 3 /year per nuclear site are produced, which at times represents more than 30% of the volume of total releases. The conventional dry cleaning process is not a viable option, given that repeated washing cause clothes to fade and the odors are rot removed completely. In order to eliminate releases, STMI has developed, after several years of research with the Technological University of Compiegne, France, a solvent dry washing process for garments used in the nuclear industry. (author)

  7. Monitoring of released radioactive gaseous and liquid effluent at Rokkasho Reprocessing Plant

    International Nuclear Information System (INIS)

    Oka, M.; Keta, S.; Nagai, S.; Kano, M.; Ishihara, N.; Moriyama, T.; Ogaki, K.; Noda, K.

    2009-01-01

    Rokkasho Reprocessing Plant (RRP) Rokkasho Reprocessing Plant started its active tests with spent fuel at the end of March 2006. When spent fuels are sheared and dissolved, radioactive gaseous effluent and radioactive liquid effluent such as krypton-85, tritium, etc. are released into the environment. In order to limit the public dose as low as reasonably achievable in an efficient way, RRP removes radioactive material by evaporation, rinsing, filtering, etc., and then releases it through the main stack and the sea discharge pipeline that allow to make dispersion and dilution very efficiently. Also, concerning the radioactive gaseous and liquid effluent to be released into the environment, the target values of annual release have been defined in the Safety Rule based on the estimated annual release evaluated at the safety review of RRP. By monitoring the radioactive material in gaseous exhaust and liquid effluent RRP controls it not to exceed the target values. RRP reprocessed 430 tUpr of spent fuel during Active Test (March 2006 to October 2008). In this report, we report about: The outline of gaseous and liquid effluent monitoring. The amount of radioactive gaseous and liquid effluent during the active test. The performance of removal of radioactive materials in gaseous and liquid effluents. The impact on the public from radioactive effluents during the active test. (author)

  8. Dispersion of effluents in the atmosphere; Dispersion des effluents dans l`atmosphere

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-12-31

    This conference day was organized by the `convection` section of the French association of thermal engineers with the support of the environment and energy mastery agency (ADEME). This book of proceedings contains 10 papers entitled: `physical modeling of atmospheric dispersion in wind tunnels. Some industrial examples`; `modeling of the noxious effects of a fire on the environment of an industrial site: importance of thermal engineering related hypotheses`; `atmospheric diffusion of a noxious cloud: fast evaluation method of safety areas around refrigerating installations that use ammonia`; `modeling of atmospheric flows in urban areas in order to study the dispersion of pollutants`; `use of a dispersion parameter to characterize the evolution of a diffusion process downstream of a linear source of passive contaminant placed inside a turbulent boundary layer`; `elements of reflexion around the development of an analytical methodology applied to the elaboration of measurement strategies of air quality in ambient and outdoor atmospheres around industrial sites`; `state-of-the-art about treatment techniques for VOC-rich gaseous effluents`; `characteristics of the time variation of the atmospheric pollution in the Paris region and visualization of its space distribution`; `mass-spectrometry for the measurement of atmospheric pollutants`; `volume variations in natural convection turbulence`. (J.S.)

  9. Dispersion of effluents in the atmosphere; Dispersion des effluents dans l`atmosphere

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-12-31

    This conference day was organized by the `convection` section of the French association of thermal engineers with the support of the environment and energy mastery agency (ADEME). This book of proceedings contains 10 papers entitled: `physical modeling of atmospheric dispersion in wind tunnels. Some industrial examples`; `modeling of the noxious effects of a fire on the environment of an industrial site: importance of thermal engineering related hypotheses`; `atmospheric diffusion of a noxious cloud: fast evaluation method of safety areas around refrigerating installations that use ammonia`; `modeling of atmospheric flows in urban areas in order to study the dispersion of pollutants`; `use of a dispersion parameter to characterize the evolution of a diffusion process downstream of a linear source of passive contaminant placed inside a turbulent boundary layer`; `elements of reflexion around the development of an analytical methodology applied to the elaboration of measurement strategies of air quality in ambient and outdoor atmospheres around industrial sites`; `state-of-the-art about treatment techniques for VOC-rich gaseous effluents`; `characteristics of the time variation of the atmospheric pollution in the Paris region and visualization of its space distribution`; `mass-spectrometry for the measurement of atmospheric pollutants`; `volume variations in natural convection turbulence`. (J.S.)

  10. Liquid Effluent Monitoring Information System test plans releases 2.0 and 3.0

    International Nuclear Information System (INIS)

    Guettler, D.A.

    1995-01-01

    The Liquid Effluent Monitoring Information System (LEMIS) is being developed as the organized information repository facility in support of the liquid effluent monitoring requirements of the Tri-Party Agreement. It is necessary to provide an automated repository into which the results from liquid effluent sampling will be placed. This repository must provide for effective retention, review, and retrieval of selected sample data by authorized persons and organizations. This System Architecture document is the aggregation of the DMR P+ methodology project management deliverables. Together they represent a description of the project and its plan through four Releases, corresponding to the definition and prioritization of requirements defined by the user

  11. Liquid Effluent Monitoring Information System (LEMIS) test plans release 1.0

    International Nuclear Information System (INIS)

    Adams, R.T.

    1994-01-01

    The Liquid Effluent Monitoring Information System (LEMIS) is being developed as the organized information repository facility in support of the liquid effluent monitoring requirements of the Tri-Party Agreement. It is necessary to provide an automated repository into which the results from liquid effluent sampling will be placed. This repository must provide for effective retention, review, and retrieval of selected sample data by authorized persons and organizations. This System Architecture document is the aggregation of the DMR P+ methodology project management deliverables. Together they represent a description of the project and its plan through four Releases, corresponding to the definition and prioritization of requirements defined by the user

  12. Liquid Effluent Monitoring Information System test plans release 1.2

    International Nuclear Information System (INIS)

    Adams, R.T.

    1994-01-01

    The Liquid Effluent Monitoring Information System (LEMIS) is being developed as the organized information repository facility in support of the liquid effluent monitoring requirements of the Tri-Party Agreement. It is necessary to provide an automated repository into which the results from liquid effluent sampling will be placed. This repository must provide for effective retention, review, and retrieval of selected sample data by authorized persons and organizations. This System Architecture document is the aggregation of the DMR P+ methodology project management deliverables. Together they represent a description of the project and its plan through four Releases, corresponding to the definition and prioritization of requirements defined by the user

  13. Liquid Effluent Monitoring Information System (LEMIS) test plans release 1.1

    International Nuclear Information System (INIS)

    Adams, R.T.

    1994-01-01

    The Liquid Effluent Monitoring Information System (LEMIS) is being developed as the organized information repository facility in support of the liquid effluent monitoring requirements of the Tri-Party Agreement. It is necessary to provide an automated repository into which the results from liquid effluent sampling will be placed. This repository must provide for effective retention, review, and retrieval of selected sample data by authorized persons and organizations. This System Architecture document is the aggregation of the DMR P+ methodology project management deliverables. Together they represent a description of the project and its plan through four Releases, corresponding to the definition and prioritization of requirements defined by the user

  14. The management plan of liquid effluent in Korean advanced light water reactor

    International Nuclear Information System (INIS)

    Kim, S. H.; Lim, H. S.; Jeong, D. W.; Jeong, D. Y.

    2001-01-01

    Non-radioactive liquid effluent in Korean Advanced Light Water Reactor is transferred and treated in centralized waste treatment facility after the radioactivity in effluent is checked within power block. The liquid effluent from centralized waste treatment facility will be discharged by way of discharge canal in order to be in the sufficient condition. As a result of investigating the radiation monitoring design in accordance with 20 provisions by Korean Regulatory Authority, each effluent radiation monitoring with 20 provisions by Korean Regulatory Authority, each effluent radiation monitoring design satisfies the regulatory guideline. In relation to sampling and analyses, most systems satisfy the regulatory guideline except for some effluents from turbine building. And, though sampling and analyses are performed after radioactivity is monitored at each system in turbine building, these exceptions in turbine building effluents are expected to cause no significant problems because radioactivity is monitored by direct or indirect methods prior to release from turbine building. Integrated monitoring on liquid effluent from the centralized waste water treatment facility is not necessary because radiation monitoring, sampling and analyses on each system within power block are performed, and operational effectiveness compared with cost according to adding the radiation monitoring equipment is too low. So, whether the radiation monitoring in this effluent is reflected on design or not is planned to be determined through discussion with regulatory authority

  15. Screening for crude oil degrading bacteria in liquid organic waste (effluent samples)

    International Nuclear Information System (INIS)

    Akpe, A.R.

    2014-01-01

    The screening for crude oil degrading bacteria in some liquid organic wastes (cassava mill effluents, rubber effluents and oil palm mill effluents) was carried out. Hydrocarbon utilising bacteria were isolated on mineral salt agar using vapour phase technique. The samples yielded 20 bacterial isolates from 13 different genera. Cassava mill effluent and rubber effluent had the highest number (7), while oil palm effluent had the least number (6) of bacterial isolates. The isolates that had the highest occurrence (occurring in all samples) were Pseudomonas aeruginosa and Escherichia coli. Of these 13 genera 9 were gram negative, while only 4 were gram positive. The total heterotrophic bacterial (THB) count and total hydrocarbon utilisers (THU) from all the effluent samples ranged from 3.0 * 10/sup 4/ to 6.0* 10/sup 7/ cfu/mL and 2.3 *10/sup 2/ to 4.2*10/sup 3/ cfu/mL, respectively. The counts of hydrocarbon utilisers were obviously lower than the heterotrophic counts, although the differences in counts were found to be statistically non-significant (P > 0.05). Rubber effluents and oil palm mill effluents had the highest number of hydrocarbon utilisers with three isolates each. The active hydrocarbon utilisers encountered in this study included Serratia marscescens, Bacillus cereus, P. aeruginosa, Enterobacter aerogenes and Bacillus subtilis. Presence of nutrients and crude oil degrading bacteria in these effluents suggests that these effluents can be used to enhance bioremediation through their use as biostimulation and bioaugmentation agents. (author)

  16. Liquid effluent retention facility final-status groundwater monitoring plan

    International Nuclear Information System (INIS)

    Sweeney, M.D.; Chou, C.J.; Bjornstad, B.N.

    1997-09-01

    The following sections describe the groundwater-monitoring program for the Liquid Effluent Retention Facility (LERF). The LERF is regulated under the Resource Conservation and Recovery Act of 1976 (RCRA). The LERF is included in the open-quotes Dangerous Waste Portion of the Resource Conservation and Recovery Act Permit for the Treatment, Storage, and Disposal of Dangerous Waste, Permit WA890008967close quotes, (referred to herein as the Permit) (Ecology 1994) and is subject to final-status requirements for groundwater monitoring (WAC 173-303-645). This document describes a RCRA/WAC groundwater detection-monitoring program for groundwater in the uppermost aquifer system at the LERF. This plan describes the LERF monitoring network, constituent list, sampling schedule, statistical methods, and sampling and analysis protocols that will be employed for the LERF. This plan will be used to meet the groundwater monitoring requirements from the time the LERF becomes part of the Permit and through the post-closure care period, until certification of final closure

  17. Treatment option evaluation for liquid effluent secondary streams on the Hanford Site

    International Nuclear Information System (INIS)

    Holter, G.M.; Triplett, M.B.; Fow, C.L.; White, M.K.

    1988-08-01

    This study, conducted by the Pacific Northwest Laboratory (PNL) for Westinghouse Hanford Company (WHC), examines the range of secondary waste types and volumes likely to result from treatment of contaminated liquid effluents. Alternatives for treatment of these effluents were considered, taking into account the implementation of the ''best-available technology'' as assumed in current and ongoing engineering studies for treating the various liquid effluent waste streams. These treatment alternatives, and potential variations in the operating schedules for Hanford Site facilities generating contaminated liquid effluents, were evaluated to project an estimated range for the volume of each of the various secondary waste streams that are likely to be generated. The conclusions and recommendations were developed, based on these estimates. 23 refs., 34 figs., 16 tabs

  18. Decontamination of irradiated-fuel processing waste using manganese dioxide hydrate; Decontamination des effluents de traitement des combustibles irradies par le bioxyde de manganese hydrate

    Energy Technology Data Exchange (ETDEWEB)

    Auchapt, J M; Gaudier, J F [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

    1969-07-01

    The 'manganese dioxide' process is designed to replace the 'calcium carbonate' treatment for low and medium activity wastes. The objective to attain during the research for a new process was the diminution of the volume of the sludge without decreasing the decontamination factor of the wastes. The new process involves addition in series of twice over 100 ppm of Mn{sup 2+} in the waste which has previously been made basic and oxidizing; the precipitate formed in situ is separated after each addition. The process has the advantage of increasing the decontamination of strontium. The treatment can be used in a plant including two decantation units and has given effective results when applied in such a plant. (author) [French] Le procede au ''bioxyde de manganese'' est destine a remplacer le traitement ''carbonate de calcium'' dans les effluents de moyenne activite. L'objectif poursuivi lors de la recherche d'un procede nouveau etait de diminuer le volume des boues sans diminuer le facteur de decontamination des effluents. Le nouveau traitement consiste a effectuer en cascade sur les effluents rendus basiques et oxydants une double precipitation de 100 ppm de Mn{sup 2+} avec separation intermediaire du precipite. Il presente en outre l'avantage d'ameliorer la decontamination en strontium. Le traitement est utilisable dans la chaine des deux decanteurs et a donne satisfaction lors de son exploitation industrielle. Le volume des boues seches a ete reduit d'un facteur 3 a 4 par rapport au traitement carbonate. (auteur)

  19. Annual report on the effluent control of low level liquid water in Tokai Works. FY2004

    International Nuclear Information System (INIS)

    Takeishi, Minoru; Miyagawa, Naoto; Watanabe, Hitoshi

    2005-08-01

    This report was written about the effluent control of low level liquid waste in JNC Tokai Works Fiscal Year 2004, from 1st April 2004 to 31th March 2005. In this period, the quantities and concentrations of radioactivity in liquid waste from Tokai Works were under the discharge limits of 'Safety Regulations for the Tokai Reprocessing Plant' and regulations of government. (author)

  20. Proposed radioactive liquid effluent monitoring requirements at the Savannah River Site

    International Nuclear Information System (INIS)

    Jannik, G.T.; Carlton, W.H.; Blunt, B.C.

    1994-01-01

    Clear regulatory guidance exists for structuring a radiological air monitoring program, however, there is no parallel guidance for radiological liquid monitoring. For Department of Energy (DOE) facilities, there are no existing applicable federal regulations, DOE orders, or DOE guidance documents that specify at what levels continuous monitoring, continuous sampling, or periodic confirmatory measurements of radioactive liquid effluents must be made. In order to bridge this gap and to technically justify and document liquid effluent monitoring decisions at DOE's Savannah River Site, Westinghouse Savannah River Company has proposed that a graded, dose-based approach be established, in conjunction with limits on facility radionuclide inventories, to determine the monitoring and sampling criteria to be applied at each potential liquid radioactive effluent point. The graded approach would be similar to--and a conservative extension of--the existing, agreed-upon SRS/EPA-IV airborne effluent monitoring approach documented in WSRC's NESHAP Quality Assurance Project Plan. The limits on facility radionuclide inventories are based on--and are a conservative extension of--the 10 CFR 834, 10 CFR 20, and SCR 61-63 annual limits on discharges to sanitary sewers. Used in conjunction with each other, the recommended source category criteria levels and facility radionuclide inventories would allow for the best utilization of resources and provide consistent, technically justifiable determinations of radioactive liquid effluent monitoring requirements

  1. Improved technique for in situ measurement of radioactivity in liquid effluents

    International Nuclear Information System (INIS)

    Balasundar, S.; Jose, M.T.; Ravi, T.; Sundaram, V.M.; Raghunath, V.M.

    1993-01-01

    As a pre-requisite for handling and disposal of radioactive liquid effluents, they should be categorized according to their chemical nature and the type and level of radioactivity. A continuous monitoring of these effluents is necessary to assess the discharged activity and to detect any unusually large increase in the activity level. It may also be required to assess the beta, gamma specific activities in the effluents independently instead of just combined beta-gamma activity as is generally done. (author). 1 ref., 2 tabs

  2. Procédés de traitements des effluents de cave adaptés au secteur des vins biologiques : état des lieux et perspectives

    Directory of Open Access Journals (Sweden)

    Rochard Joël

    2017-01-01

    Full Text Available Au-delà des itinéraires viticoles et œnologiques, la viticulture biologique doit également s'intéresser aux difflérents aspects de la viticulture durable concernant notamment le traitement des effluents de cave, avec une approche écologique. Parallèlement à la performance d'épuration, le traitement des effluents doit intégrer difflérentes orientations écologiques : faible consommation d'énergie et limitation des déchets (boues de plus en plus difflicile à gérer par voie agronomique. En complément, en liaison avec le concept d'éco-oenotourisme, une intégration harmonieuse de dispositif peut être envisagée, qui associe à la fois une limitation des nuisances olfactives et sonores, une valorisation paysagère et de la biodiversité ainsi qu'éventuellement une réutilisation des eaux traitées pour l'irrigation. Les techniques de lits ou massifs plantés ont prouvé leur efflicacité dans le domaine de l'épuration des effluents d'origine domestique. Leur application aux effluents de cave qui fait l'objet de difflérentes recherches depuis plusieurs années, permet de valoriser l'environnement esthétique et écologique de la cave. L'objectif de la communication et de présenter le principe de l'épuration par lit planté de roseaux avec les difflérentes mises en œuvre envisageable au niveau des caves.

  3. Chemical analysis of radioactive liquid wastes. Volumetric dosage of sulfates in the presence of phosphates, 'nitrochromazo' being used as an indicator; Analyse chimique des effluents radioactifs - dosage volumetrique des sulfates en presence de phosphates a l'aide du 'nitrochromazo' comme indicateur

    Energy Technology Data Exchange (ETDEWEB)

    Testemale, G; Girault, J [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1969-07-01

    A simple titration technique of SO{sub 4} ions in the presence of PO{sub 4} ions has been perfected. The pH of the medium is stated to 1,7-2,0 the colour of the indicator changes from violet to blue. The method is quick, accurate and can be fitted to biological studies or in the industry of fertilizes. The synthesis method of nitrochromazo (acid 2, 7 bis (4 nitro 2 sulfobenzene 1 azo) 1-8 hydroxynaphthalene 3-6 disulfonic) is described. (authors) [French] Une technique simple de titrage des ions SO{sub 4} en presence d'ions PO{sub 4} a ete mise au point. Le pH du milieu est fixe a 1,7-2,0, le virage de l'indicateur s'effectue du violet au bleu. La methode est rapide, precise et peut etre adaptee a des travaux de biologie ou dans l'industrie des engrais. La methode de synthese du 'Nitrochromazo' (acide 2, 7 bis (4 nitro 2 sulfobenzene 1 azo) 1-8 dihydroxynapthtalene 3-6 disulfonique) est decrite. (auteurs)

  4. Determination of statin drugs in hospital effluent with dispersive liquid-liquid microextraction and quantification by liquid chromatography.

    Science.gov (United States)

    Martins, Ayrton F; Frank, Carla da S; Altissimo, Joseline; de Oliveira, Júlia A; da Silva, Daiane S; Reichert, Jaqueline F; Souza, Darliana M

    2017-08-24

    Statins are classified as being amongst the most prescribed agents for treating hypercholesterolaemia and preventing vascular diseases. In this study, a rapid and effective liquid chromatography method, assisted by diode array detection, was designed and validated for the simultaneous quantification of atorvastatin (ATO) and simvastatin (SIM) in hospital effluent samples. The solid phase extraction (SPE) of the analytes was optimized regarding sorbent material and pH, and the dispersive liquid-liquid microextraction (DLLME), in terms of pH, ionic strength, type and volume of extractor/dispersor solvents. The performance of both extraction procedures was evaluated in terms of linearity, quantification limits, accuracy (recovery %), precision and matrix effects for each analyte. The methods proved to be linear in the concentration range considered; the quantification limits were 0.45 µg L -1 for ATO and 0.75 µg L -1 for SIM; the matrix effect was almost absent in both methods and the average recoveries remained between 81.5-90.0%; and the RSD values were <20%. The validated methods were applied to the quantification of the statins in real samples of hospital effluent; the concentrations ranged from 18.8 µg L -1 to 35.3 µg L -1 for ATO, and from 30.3 µg L -1 to 38.5 µg L -1 for SIM. Since the calculated risk quotient was ≤192, the occurrence of ATO and SIM in hospital effluent poses a potential serious risk to human health and the aquatic ecosystem.

  5. Radiological characterization of liquid effluent hold up tank for generating data base for future decommissioning

    International Nuclear Information System (INIS)

    Sapkal, Jyotsna A.; Singh, Pratap; Verma, Amit; Yadav, R.K.B.; Thakare, S.V.

    2018-01-01

    Operations at Radiological laboratory facilities are involved in fabrication of high activity radioactive sources like 60 Co, 192 1r and 137 Cs, handling of long lived radionuclides like 137 Cs/ 90 Sr, radiochemical processing and production of short-lived radioisotopes for medical diagnosis and treatment of patients. Typical liquid waste management feature at any Radiological Laboratory facility primarily consists of effluent tanks which store the liquid effluent wastes generated during radiochemical processing and fabrication of reactor produced radioisotopes. The liquid waste generated from various laboratories are collected to low level sump tanks from where it is transferred to hold up tanks. The liquid waste is transferred to centralized effluent treatment plant, analysis and characterization of the same is carried out. This paper explains the characterization study of samples drawn from the liquid effluent tank which would be helpful for planning for decontamination as well as for decommissioning and in management of radioactive wastes. In this study the crud deposited at the bottom of tank was collected for gamma spectrometry analysis. Radiation field was measured, at the bottom of the tank for correlating the activity present and the radiation field

  6. Application of reverse osmosis to the treatment of liquid effluents produced by nuclear power plants

    International Nuclear Information System (INIS)

    Huet, Y.; Poulat, B.; Menjeaud, C.

    1989-01-01

    Radioactive liquid effluents generated during the operation of PWR nuclear power units are currently treated by two independent systems. The effluents from the reactor coolant system are recycled, unlike the others, which, after treatment, are released into the river or ocean that provides cooling water for the unit. The objective of the treatment of nonrecycled effluents is to separate from them as much of the radioactive particles that they contain as possible, so as to release into the environment a maximum volume of nonradioactive waste, and to be left with only a minimum volume of concentrated waste, containing most of the initial radioactivity, which must be loaded into casks for storage. Membrane-based filtration techniques, because they have excellent separation performances, can logically be used for this decontamination of the liquid effluents. Having developed its own reverse osmosis membrane, a possible application in a nuclear power plant, i.e., integration of a reverse osmosis unit into a radioactive liquid effluent treatment system is presented. (author)

  7. Assessment of Radioactive Liquid Effluents Release at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Bessa Nisti, Marcelo; Godoy dos Santos, Adir Janete

    2008-01-01

    A continuous effluent monitoring program has been established at IPEN's plant in order to allow an environmental impact assessment due to radioactive liquid effluent discharge to sanitary system. Representative samples of radioactive liquid effluents are analyzed by using high resolution gamma spectroscopy and instrumental neutron activation analysis, facing to Brazilian radioprotection regulatory rules. The results are consolidating yearly in the Institute source-term. In this paper, results of the source-term are presented, concerning to years 2004, 2005 and 2006. The total activity discharged was 8.5xl0 8 Bq, 5.7x10 8 Bq and 2.7xl0 8 Bq, respectively. As the release is strongly dependent on the total amount of the effluent and on the dilution factor, special attention is needed in order to obtain the correct value of that last one. The estimated inside plant dilution factor, considering the recent facilities and the reshaping of the sewerage system was 80, 180 and 130, for period of 2004, 2005 and 2006 discharged liquid radioactive effluent

  8. Liquid effluent FY 1996 program plan WBS 1.2.2.1. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The Liquid Effluents Program supports the three Hanford Site mission components: (1) Clean up the site, (2) provide scientific and technological excellence to meet global needs, and (3) Partner in the economic diversification of the region. Nine Hanford Site objectives have been established for the Hanford Site programs to accomplish all three components of this mission.

  9. Liquid effluent FY 1996 program plan WBS 1.2.2.1. Revision 1

    International Nuclear Information System (INIS)

    1995-09-01

    The Liquid Effluents Program supports the three Hanford Site mission components: (1) Clean up the site, (2) provide scientific and technological excellence to meet global needs, and (3) Partner in the economic diversification of the region. Nine Hanford Site objectives have been established for the Hanford Site programs to accomplish all three components of this mission

  10. Fertilizer potential of liquid and solid effluent from thermophilic anaerobic digestion of poultry waste.

    Science.gov (United States)

    Liedl, B E; Bombardiere, J; Chaffield, J M

    2006-01-01

    Thermophilic anaerobic treatment of poultry litter produces an effluent stream of digested materials that can be separated into solid and liquid fractions for use as a crop fertilizer. The majority of the phosphorus is partitioned into the solid fraction while the majority of the nitrogen is present in the liquid fraction in the form of ammonium. These materials were tested over six years as an alternative fertilizer for the production of vegetable, fruit, and grassland crops. Application of the solids as a field crop fertilizer for vegetables and blueberries resulted in lower yields than the other fertilizer treatments, but an increase in soil phosphorus over a four-year period. Application of the digested liquids on grass and vegetable plots resulted in similar or superior yields to plots treated with commercially available nitrogen fertilizers. Hydroponic production of lettuce using liquid effluent was comparable to a commercial hydroponic fertilizer regime; however, the effluent treatment for hydroponic tomato production required supplementation and conversion of ammonium to nitrate. While not a total fertilizer solution, our research shows the effectiveness of digested effluent as part of a nutrient management program which could turn a livestock residuals problem into a crop nutrient resource.

  11. Revision of by-laws about effluents of EdF's nuclear power plants; Revision des arretes de rejets des centrales nucleaires d'EDF

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-07-01

    In France, in application of the clean water law from January 3, 1992 and since the decree 95-540 from May 4, 1995, each basic nuclear facility receives a single permission which covers both its water takes and its radioactive and non-radioactive effluents. This decree, initially dedicated to new facilities has been enlarged to all existing installations for which the prefectorial by-laws have reached their date-line. Thus, up to now, five inter-ministerial by-laws have renewed the permissions of water takes and effluents evacuation of the power plants of Saint-Laurent-des-Eaux (Loir-et-Cher), Flamanville (Manche), Paluel (Seine-Maritime), Belleville (Cher) and Saint-Alban (Isere). These by-laws foresee an important abatement of the effluents and concern more particularly the tritium, {sup 14}C, the iodine isotopes and also some other non-radioactive chemical compounds. This document is a compilation of all revised by-laws about effluents and concerning the nuclear power plants listed above. (J.S.)

  12. Risk-Based Radioactive Liquid Effluent Monitoring Requirements at the U. S. Department of Energy's Savannah River Site

    International Nuclear Information System (INIS)

    Jannik, G.T.

    2001-01-01

    For Department of Energy (DOE) facilities, clear regulatory guidance exists for structuring radiological air emissions monitoring programs. However, there are no parallel regulations for radiological liquid effluent monitoring programs. In order to bridge this gap and to technically justify liquid effluent monitoring decisions at DOE's Savannah River Site, a graded, risk-basked approach has been established to determine the monitoring and sampling criteria to be applied at each liquid discharge point

  13. Elimination of slightly radioactive liquid effluent by dilution. Its consequences (1960)

    International Nuclear Information System (INIS)

    Bovard, P.; Candillon, C.

    1960-01-01

    Nuclear centres often have to solve problems raised by the elimination of large volumes of slightly radioactive liquid effluent. As things stand at present, the method usually adopted consists in expelling this effluent into the main water system in order to dilute it to a maximum, and thus to lower its radioactive isotope concentration to below the norms imposed by the Public Health Service. This technique requires systematic checking of the water system and its dependences, and demands a thorough knowledge of adsorption and fixation processes. (author) [fr

  14. The treatment of liquid effluents of reprocessing plants by a chemical process: French experience

    International Nuclear Information System (INIS)

    Fernandez, N.; Taillard, D.

    1977-01-01

    The goal of radioactive effluent processing is to obtain a liquid with a residual activity level allowing disposal and a minimum amount of slurries. Insolubilization methods used in France are described to eliminate fission products in reprocessing plants effluents i.e. strontium, cesium, ruthenium and antimony; others radioelements are generally carried away with others precipitates. Evolution of the process is expressed in terms of reprocessing needs and improvements. Decontamination factors better than 100 are now possible with concentration factors between 30 and 50 [fr

  15. 242-A Evaporator/Liquid Effluent Retention Facility data quality objectives

    International Nuclear Information System (INIS)

    Von Bargen, B.H.

    1994-01-01

    The purpose of data quality objectives (DQO) is to determine the most cost effective methods of gathering the essential data necessary to make decisions to support successful operation of the facility. The essential data is defined by such information as sample amount, sample location, required analyses, and how sampling and analyses are performed. Successful operation is defined as meeting the campaign objectives while operating within established requirements. This DQO document addresses that portion of the system from 242-A Evaporator candidate feed tanks through discharge of process condensate to the Liquid Effluent Retention of Facility (LERF). Later revisions will incorporate and integrate the entire system, including the Effluent Treatment Facility (ETF)

  16. 242-A Evaporator/Liquid Effluent Retention Facility data quality objectives

    Energy Technology Data Exchange (ETDEWEB)

    Von Bargen, B.H.

    1994-09-29

    The purpose of data quality objectives (DQO) is to determine the most cost effective methods of gathering the essential data necessary to make decisions to support successful operation of the facility. The essential data is defined by such information as sample amount, sample location, required analyses, and how sampling and analyses are performed. Successful operation is defined as meeting the campaign objectives while operating within established requirements. This DQO document addresses that portion of the system from 242-A Evaporator candidate feed tanks through discharge of process condensate to the Liquid Effluent Retention of Facility (LERF). Later revisions will incorporate and integrate the entire system, including the Effluent Treatment Facility (ETF).

  17. Effet sur la compétitivité des réglementations relatives à la gestion des effluents

    DEFF Research Database (Denmark)

    Andersen, Mikael Skou

    2004-01-01

    Grâce à un regard approfondi sur le secteur laitier dans les pays de l'OCDE, cette étude permet de mieux analyser l'impact des subventions à l'agriculture et des politiques de l'environnement sur l'environnement et sur la compétitivité internationale des produits laitiers. Ce chapitre étudie les ...

  18. Electro-coagulation applied to the treatment of industrial effluents; Electrocoagulation appliquee en traitement des effluents industriels

    Energy Technology Data Exchange (ETDEWEB)

    Laplace, C.; Leboucher, G.; Coste, M. [Anjou Recherche, Vivendi Water, 78 - Maisons-Laffitte (France)

    2001-07-01

    The electro-coagulation is a water treatment technic in electrolysis cell with double anode. In substitution to the coagulant reagent often used in water de-pollution, it realizes also the coloring decomposition, the DCO abatement and sometimes improving the sludges processing. The technic presents meanwhile some limitations as its poor treatment capacity and the necessity of a high effluent conductivity. An example of application shows that this technic is economically competitive. (A.L.B.)

  19. Processing and monitoring liquid, radioactive effluents from the Wiederaufarbeitungsanlage Karlsruhe

    International Nuclear Information System (INIS)

    Hoehlein, G.; Huppert, K.L.; Winter, M.

    1977-01-01

    The Wiederaufarbeitungsanlage Karlsruhe (WAK) serves as a demonstration plant for the processing of highly-irradiated uranous oxide. The high active waste concentrates find interim storage at the WAK until they are solidified at a later stage. In contrast to this, the slightly- and the medium-active liquid wastes are transported to the decontamination facility of the Nuclear Research Centre Karlsruhe, where they are immediately processed. These liquid wastes contain about 1 per thousand of the activity inventary of the fuel elements processed. Monitoring of the radioactive waste water of the WAK is carried out by the Nuclear Research Centre's department radiation protection and safety. (orig.) [de

  20. Study of radiation processes for purifying liquid effluent and the design of pilot plants

    International Nuclear Information System (INIS)

    Kon'kov, N.G.; Buslaeva, S.P.; Osipov, V.B.; Panin, Yu.A.; Solodikhina, L.D.; Upadyshev, L.B.; Karpukhin, V.F.; Fajngol'd, Z.L.

    1975-01-01

    The possibilities of purifying liquid effluent containing dyestuffs and various organic and biological pollutants with an accelerated electron beam of energy up to 0.7 MeV are examined. A laboratory plant has been erected for the stationary, continuous irradiation - with bubbling of air - of artificial and natural industrial effluent containing organic pollutants in concentrations of up to 2g/litre and the 5 SKh dye in concentrations of up to 220 mg/litre. The results are discussed of the experimental irradiation of artificial mixtures consisting of distilled water, organic pollutants and dyestuffs, and also of natural industrial effluents from an enterprise where antibiotics are produced and from textile mills. The results of the studies indicate that the physicochemical characteristics of effluents are improved. On the basis of these studies pilot plants with electron accelerators are being designed for a daily throughput of 15 000 m 3 of effluent from the production of antibiotics. The electron accelerators are of the transformer type (EhLV-1) with an energy of up to 0.7 MeV and a power of up to 40 kW. In addition, units with a daily throughput of 200 m 3 are being designed for the breakdown of cyanides in effluent by 60 Co. Such a unit consists of three reactors with centro-axial irradiators and solid cast-iron biological shielding. The dose-rate can be measured over a wide range, thanks to the use of spherical source holders. The sources have a total activity of 62 kCi. Calculations of the cost of the radiation treatment of effluent demonstrate the economic feasibility of the method

  1. Bromide as chemical tracer to measure the liquid effluent flow at IPEN-CNEN/SP

    International Nuclear Information System (INIS)

    Silva, Douglas B.; Faustino, Mainara G.; Monteiro, Lucilena R.; Cotrim, Marycel E.B.; Pires, Maria Aparecida F.

    2013-01-01

    Due to recent changes in CONAMA Resolution 357, which occurred through the publication of Resolution 430, on May 13, 2011 that now set standards about the effluent release, IPEN-CNEN/SP initiated several actions to improve the Environmental Monitoring Program (PMA-Q) of stable chemical compounds. Besides various parameters (physical and chemical) established by CONAMA, the submission of an annual pollution inventory report became necessary. The liquid effluent flow measurement is required to implement this inventory. Thereby, this paper describes a study that uses bromide as a chemical tracer. This paper presents the results of 6 tracer releases in IPEN wastewater collection network between 2011 and 2012. Two tracer releases designs were performed: single pulse and continuous releases performed with 1 to 6 hours duration, done by using one single piston pump manufactured by DIONEX. After the release, one fraction of the effluent was collected every 15 minutes at IPEN effluent monitoring station. The tracer concentration in the effluent was analyzed by ion chromatography and flow was calculated considering the dilution in the system and pump flow set up for the release. The flow values were measured in 6 events were determined and evaluated as per Brazilian regulation requirements. Experimental designs to be implemented during 2013 monitoring were also discussed in this paper, contributing to legal compliance and to improve IPEN's Environmental Monitoring Program for stable chemical compounds (PMA-Q). (author)

  2. Rancho Seco liquid effluent pathway aquatic and terrestrial dietary survey report

    International Nuclear Information System (INIS)

    Eagle, R.J.; Wong, K.M.; Noshkin, V.E.

    1984-01-01

    This report is a detailed summary of a survey conducted to identify all environmental pathways that may lead to any potential radiological dose to individuals utilizing aquatic and terrestrial components possibly contaminated with radionuclides contained in the liquid effluents that have been routinely discharged since 1980 to Clay Creek from the Rancho Seco Nuclear Generating Station. All land users and identified residents who obtain food from the creeks or use the creek water for irrigation or recreation were interviewed. Site specific usage parameters for the consumption of different food products and for direct exposure to individuals at downstream locations were identified and are discussed in this report. These usage parameters will be used with appropriate radionuclide concentration data to estimate radiological dose to man from the identified liquid effluent pathways

  3. The treatment of liquid effluents from the nuclear industry

    International Nuclear Information System (INIS)

    Carley-Macauly, K.W.

    1983-01-01

    This paper reviews the sources, and principles of management, of radioactive liquid wastes in the nuclear industry. The selection of processes for their treatment is based on consideration of the solution chemistry and of the total system for active waste disposal which must ensure that the activity or radiation dose arriving in the biosphere is kept within acceptable limits. Treatment processes aim primarily at concentration of the active species into a small volume, as by evaporation, selective ion exchange or precipitation. These well established methods have counterparts or developments among the more novel means of separation, such as membrane processes. (author)

  4. Analysis of adaptability of radioactive liquid effluent discharge under normal condition of inland nuclear power plant

    International Nuclear Information System (INIS)

    Xu Yueping; Zhang Bing; Chen Yang; Zhu Lingqing; Tao Yunliang; Shangguan Zhihong

    2011-01-01

    The discharge of radioactive liquid effluent from inland nuclear power plant under normal operation is an important part to be considered in environmental impact assessment. Requirements of newly revised and upcoming standards GB 6249 and GB 14587 are introduced in this paper. Through an example of an inland NPP siting in the preliminary feasibility study phase, the adaptability to the relevant regulations in the site selection is analyzed. Also, the concerned problems in the design of AP1000 units are addressed. (authors)

  5. Functional design criteria for project W-252, phase II liquid effluent treatment and disposal. Revision 2

    International Nuclear Information System (INIS)

    Hatch, C.E.

    1995-05-01

    This document is the Functional Design Criteria for Project W-252. Project W-252 provides the scope to provide BAT/AKART (best available technology...) to 200 Liquid Effluent Phase II streams (B-Plant). This revision (Rev. 2) incorporates a major descoping of the project. The descoping was done to reflect a combination of budget cutting measures allowed by a less stringent regulatory posture toward the Phase II streams

  6. Extraction of metals from liquid effluent using modified inorganic ion exchangers

    International Nuclear Information System (INIS)

    Hudson, M.J.

    1993-01-01

    Inorganic ion exchangers such as goethite, titanium (IV) oxide; silica and zeolites have been modified to examine the extraction of ruthenium; technetium and cobalt from liquid effluent. In addition, tin (IV) hydrogenphosphate and antimony hydrogenphosphate have been also examined in the modified and unmodified forms. It has been shown that some of the above reagents are able to remove the required metal ions from aqueous solution at the trace and mg L -1 levels. (author)

  7. Continuously tritium monitoring of the pipe of liquid effluents at the Cea Cadarache

    International Nuclear Information System (INIS)

    Pira, Y.

    2004-01-01

    This report is oriented toward the radiation protection of environment that is an essential component of radiation protection. It is necessary to detect any solid, liquid or gaseous abnormal release and to find its origin. The present study bears on a detection instrument in continuously to find tritium in liquid effluents of the Cea Cadarache. After having study the functioning principle of this device, an evaluation of its performances has been realised ( back noise, yield, detection limit) and to a checking in real conditions of utilization. (N.C.)

  8. The use of supported liquid membranes in the treatment of mining effluents

    International Nuclear Information System (INIS)

    Hebden, D.; Smit, J.J.

    1984-01-01

    The acid barren effluents from uranium extraction plants contain a number of dissolved metals although these are often only in trace concentrations. Whilst recovery of these minerals for economic gain has been considered in the past, the removal of some of these minerals is now even more desirable in view of environmental considerations. It is in this application that the supported liquid membrane system finds a model application, with its ability to treat large volumes of unclarified waters, with minimal solvent losses, and selectivity of ion removal. This paper presents current research into this supported liquid membrane application and reviews techniques and costs, in the light of present knowledge. (author)

  9. Monitoring of low-level radioactive liquid effluent in Tokai reprocessing plant

    International Nuclear Information System (INIS)

    Mizutani, Tomoko; Koarashi, Jun; Takeishi, Minoru

    2009-01-01

    The Tokai reprocessing plant (TRP), the first reprocessing plant in Japan, has discharged low-level liquid wastes to the Pacific Ocean since the start of its operation in 1977. We have performed liquid effluent monitoring to realize an appropriate radioactive discharge control. Comparing simple and rapid analytical methods with labor-intensive radiochemical analyses demonstrated that the gross-alpha and gross-beta activities agreed well with the total activities of plutonium isotopes ( 238 Pu and 239+240 Pu) and major beta emitters (e.g., 90 Sr and 137 Cs), respectively. The records of the radioactive liquid discharge from the TRP showed that the normalized discharges of all nuclides, except for 3 H, were three or four orders of magnitude lower than those from the Sellafield and La Hague reprocessing plants. This was probably due to the installation of multistage evaporators in the liquid waste treatment process in 1980. The annual public doses for a hypothetical person were estimated to be less than 0.2 μSv y -1 from the aquatic pathway. Plutonium radioactivity ratios ( 238 Pu/ 239+240 Pu) of liquid effluents were determined to be 1.3-3.7, while those of the seabed sediment samples collected around the discharge point were 0.003-0.059, indicating no remarkable accumulation of plutonium in the regional aquatic environment. Thus, we concluded that there were no significant radiological effects on the public and the aquatic environment during the past 30-year operation of the TRP. (author)

  10. New decontamination processes for liquid effluents and solid materials

    International Nuclear Information System (INIS)

    Faure, S.

    2008-01-01

    New decontamination processes are being studied in order to protect workers and to reduce strongly the quantity of secondary wastes produced. 2 decontamination processes for liquid nuclear wastes are under studies. First, the coprecipitation process whose improvement is based on a better control of the 2 coupled mechanisms involved in the process: the formation of adsorbent particles and the uptake of radionuclides. Secondly, the column process whose development focuses on new materials that can be used to absorb cesium in a reversible way. 3 new decontamination processes for solid materials are being developed. First, processes using drying gels are under investigation in order to treat materials like lead, aluminium, iron and stainless steel. Real decontamination of hot cells by drying gel process has been performed and a decontamination factor between 16 and 25 has been obtained on stainless steels. Secondly, new foam decontamination processes have been developed, they are based on the use of new foams stabilized by biodegradable non-ionic surfactants: alkyl-poly-glucosides and viscofiers or nano-particles. The aim is to increase the foam lifetime. Thirdly, new surfactants in solution decontamination processes have been studied, the aim is to decontaminate through degreasing by using acidic surfactants. The idea is to combine emulsification and wetting power. (A.C.)

  11. Treatment of Radioactive Effluents at the Saclay Nuclear Research Centre; Traitement des Effluents Radioactifs au Centre d'Etudes Nucleaires de Saclay; 041e 0414 ; Tratamiento de los Efluentes Radiactivos en el Centro de Energia Nuclear de Saclay

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G. [Service de Controle des Radiations et de Genie Radioactif, Commissariat a l' Energie Atomique, Saclay (France)

    1960-07-01

    The Report Gives The Account Of Four Years' Experience In Operating The Treatment Plant For Effluents From The Saclay Nuclear Research Centre. It Contains Data Relating To The Origin, Volume And Treatment Of Waste. (author) [French] Ce rapport presente un bilan d'exploitation de l'installation de traitement des effluents du Centre d'etudes nucleaires de Saclay depuis quatre ans. On donne des chiffres concernant l'origine des residus, leur volume, leur traitement. (author) [Spanish] El autor hace un balance de explotacion de la instalacion de tratamiento de efluentes del centro de Saclay desde hace cuatro anos, dando las cifras correspondientes al origen de los residuos, a su volumen y a su tratamiento. (author) [Russian] V jetom dokumente podvoditsja itog chetyrehletnej jekspluatacii ustanovki po obrabotke zhidkih othotov v Centre jadernyh issledovanij v Sakle. V doklade privodjatsja dannye o proishozhdenii othodov, jh ob'eme i obrabotke. (author)

  12. Best Available Technology (BAT) guidance for radiological liquid effluents at US Department of Energy Facilities

    International Nuclear Information System (INIS)

    Wallo, A. III; Peterson, H.T. Jr.; Ikenberry, T.A.; Baker, R.E.

    1993-01-01

    The US Department of Energy (DOE), in DOE Order 5400.5 (1990), directs operators of DOE facilities to apply the Best Available Technology (BAT) to control radiological liquid effluents from these facilities when specific conditions are present. DOE has published interim guidance to assist facility operators in knowing when a BAT analysis is needed and how such an analysis should be performed and documented. The purpose of the guidance is to provide a uniform basis in determining BAT throughout DOE and to assist in evaluating BAT determinations during programmatic audits. The BAT analysis process involves characterizing the effluent source; identifying and selecting candidate control technologies; evaluating the potential environmental, operational, resource, and economic impacts of the control technologies; developing an evaluation matrix for comparing the technologies; selecting the BAT; and documenting the evaluation process. The BAT analysis process provides a basis for consistent evaluation of liquid effluent releases, yet allows an individual site or facility the flexibility to address site-specific issues or concerns in the most appropriate manner

  13. Control of effluents and environmental surveillance of the CEA centres. 1997 status; Controle des rejets et surveillance de l'environnement des centres CEA. Bilan 1997

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-06-01

    The environmental quality in the vicinity of CEA facilities is a major concern of the safety policy of the CEA. The aim of this document is to inform the public about the gaseous and liquids radioactive effluents released by the CEA centres under the permission of the ministry. It provides a status of the effluents and of the radioactivity levels measured near the CEA centres in 1997, using air, water, vegetation and milk samples. A comparison is made with the measurements performed during the 1993-1996 period. The data presented comes from the regulatory registers transmitted to the agency for the protection against ionizing radiations (OPRI) which belongs to the ministry of health. (J.S.)

  14. A system for destroying mixed and hazardous wastes with no gas or liquid effluents

    International Nuclear Information System (INIS)

    Camp, D.W.; Upadhye, R.S.

    1992-04-01

    We developed a conceptual design for a processing system in which the organic components of hazardous or mixed waste would be destroyed, while discharging virtually no gaseous or liquid effluents. Only solid products would be produced. For mixed waste feeds these could then be transported and disposed as low level waste. This system would oxidize the organics using any one of several destruction processes adapted to replace air with a mixture of O 2 and recycled CO 2 . Net production Of CO 2 , HC1, and H 2 O in the dosed recycle system would be scrubbed or reacted to solid products such as CaCO 3 , NaCl, and concrete. This no-effluent design may improve community acceptance of a waste destruction system

  15. Control system of liquid effluents generated in treatment with I-131

    International Nuclear Information System (INIS)

    Garcia M, T.; Ruiz C, M. A.; Angeles C, A.; Ramirez S, R.

    2015-09-01

    In recent years, nuclear medicine has developed greatly in our country and around the world. Techniques for both medical diagnosis and therapy have increased the use of radiopharmaceuticals, notably the I-131. In Mexico there are around 150 nuclear medicine establishments authorized by the Comision Nacional de Seguridad Nuclear y Salvaguardias. Most of these establishments do not have an appropriate facility for the treatment of radioactive liquid effluents, to ensure compliance with the concentration limits established in the regulations. The Instituto Nacional de Investigaciones Nucleares (ININ) developed and implemented successfully, a control system of radioactive effluents (named SACEL) from a nuclear medicine facility. This system ensures an effective compliance with regulations and also better management and control of these radioactive effluents. Calculations and design of SACEL were made with respect to I-131, because is one of the most commonly used in radiotherapy and medical diagnostics, besides its half-life is greater in relation to other radionuclides. SACEL is comprised of four storage tanks and decay and a fifth tank for measuring the concentration of I-131 and later discharge to the drain; these tanks are connected to an automated system that controls the effluents passage. The calculation to determine the volume of the tanks was carried out according to the demand that has the hospital, to the maximum activity being poured in effluents and time required to decay. In this paper the design and installation of SACEL system, in addition to functioning as a facility that enables the Hospital meet the required standards is presented. Dose calculations performed with MCNPX and the methodology used in the calibration of the detection system is also presented. (Author)

  16. Raman spectra of ordinary and deuterated liquid ammonias; Spectres Raman des ammoniacs ordinaire et deuteries liquides

    Energy Technology Data Exchange (ETDEWEB)

    Ceccaldi, M; Leicknam, J P [Commissariat a l' Energie Atomique, 91 - Saclay (France). Centre d' Etudes Nucleaires, direction des materiaux et des combustibles nucleaires, departement de physico-chimie, service des isotopes stables, service de spectrometrie de masse

    1968-12-01

    The three deuterated ammonia molecules, as well as ordinary ammonia, have been examined in the liquid state by Raman spectroscopy using a high-pressure cell described elsewhere. This work thus completes the infrared spectrometry studies. We have examined the NH and ND valency absorption regions. The polarization measurements and isotope effect considerations make it possible to confirm most of the attributions recently proposed for interpreting the infrared spectra of the four isotopic molecules: the apparent disagreement between the NH{sub 3} and ND{sub 3} spectra obtained in this region by infrared and Raman spectroscopy is discussed: by the first technique the number of bands in the spectra corresponds well to the theoretically expected number, and the relative intensities conform more or less to expectations; the Raman spectra however have a strong supplementary band in the same region, produced by a Fermi resonance; it is possible to explain, from theoretical considerations, why this resonance appears so easily in the Raman spectrum, whereas it is detected in the infrared only by a very detailed analysis of the effects of solvents on the ammonia. (authors) [French] Les trois ammoniacs deuteries, ainsi que l'ammoniac ordinaire, sont examines a l'etat liquide par spectrometrie Raman, a l'aide d'une cuve haute pression decrite par ailleurs. Ce travail complete donc les etudes effectuees par spectrometrie infra-rouge. Nous avons examine les regions d'absorption de valence NH et ND. Les mesures de polarisation et des considerations sur les effets isotopiques permettent de confirmer la plupart des attributions proposees recemment pour interpreter les spectres infra-rouges des quatre molecules isotopiques: on discute egalement l'apparent desaccord entre les spectres de NH{sub 3} et de ND{sub 3} obtenus dans cette region par infra-rouge et Raman: par la premiere technique le nombre de bandes relevees sur les spectres correspond bien au nombre theoriquement attendu et

  17. Chemical processing of liquid effluents in reprocessing plants: experience gained in France

    International Nuclear Information System (INIS)

    Fernandez, N.; Pottier, P.; Taillard, D.

    1977-01-01

    The radionuclides present in radioactive liquid effluents are precipitated for two purposes, viz: 1) to reduce the radioactivity to a level at which the liquids may be discharged; 2) to concentrate the radioactive compounds in the smallest possible volume for storage. The scientific principles of the radionuclide precipitation process are reviewed in the first part, which covers the solubility product, adsorption onto the surface of the precipitates, co-precipitation by isomorphism, ion-exchange on precipitates, etc. The paper goes on to discuss flocculation techniques, flocculation monitoring (zeta potential etc.) and methods of separating the solid and liquid phases. The specific methods for precipitating the main radionuclides are then described, with special reference to Sr, Cs, Ru, Co and Sb. The synergism of certain methods of precipitation is also discussed. The main part of the paper concerns the application of chemical processes for purifying low and medium active effluents in the Marcoule and La Hague centres. Particular emphasis is placed on the development of the processes used and the improvement of performance. Lastly, the paper discusses the possibilities offered in final treatment in such a way as to determine the limits to the effectiveness of the chemical processes. (orig.) [de

  18. Sizewell nuclear power station: investigation of radiation exposure pathways from liquid effluents. Local habits survey 1981

    International Nuclear Information System (INIS)

    Leonard, D.R.P.; Smith, B.D.

    1982-01-01

    A habits and consumption survey to review radiation exposure pathways due to liquid effluents released from the CEGB Sizewell site is described. It is relevant to both the Sizewell A and proposed Sizewell B nuclear power stations. The main objectives are to provide input data to a radiological assessment by means of identifying critical groups and to provide data for guidance in a review of environmental monitoring programmes. The way in which data for the different pathways should be combined in order to aid the subsequent radiological assessment is discussed. Recommendations are made for adjustments to the present monitoring programmes. (U.K.)

  19. Toxicity regulation of radioactive liquid waste effluent from CANDU stations - lessons from Ontario's MISA program

    International Nuclear Information System (INIS)

    Rodgers, D.W.

    2009-01-01

    Toxicity testing became an issue for Ontario's CANDU stations, when it was required under Ontario's MISA regulations for the Electricity Generation Sector. In initial tests, radioactive liquid waste (RLW) effluent was intermittently toxic to both rainbow trout and Daphnia. Significant differences in RLW toxicity were apparent among stations and contributing streams. Specific treatment systems were designed for three stations, with the fourth electing to use existing treatment systems. Stations now use a combination of chemical analysis and treatment to regulate RLW toxicity. Studies of Ontario CANDU stations provide a basis for minimizing costs and environmental effects of new nuclear stations. (author)

  20. Metal concentration of liquid effluents and surroundings of a pharmaceutical industry

    Directory of Open Access Journals (Sweden)

    E.I. Adeyeye

    2007-04-01

    Full Text Available Major and trace metals (Mg, Na, K, Ca, Fe, Zn, Cu, Sn, Al, Pb, As, Cr, Cd, Mn and Ti in liquid effluents, soil sediments and plant parts (roots and leaves from Tisco Nigeria Limited, Akure, were determined in both open effluent channel and closed direct tank. The plant in the open effluent channel was Pennisetum purpureum while the one around the direct tank was Chloris pilosa. The correlation coefficient (Cc of the metals in the open channel gave the values: soil sediments/water (0.61, roots/leaves (0.709; and (0.34, (0.91, respectively, in direct tank. F-test values showed that 67 % of the metals were significantly different (p < 0.05 among the samples. The soil sediments would serve as reservoir for all the metals determined. This was also the case for both plant roots with species variation. The plant leaves showed evidence of bioaccumulation of some metals. The high levels of Pb, As and Cd in the samples call for concern as environmental contaminants.

  1. Determination of 232Th, 230Th and 228Th in liquid effluents from uranium mining

    International Nuclear Information System (INIS)

    Godoy, Jose Marcus de Oliveira

    1979-10-01

    A liquid scintillator αlpha spectrometer was built for the determination of Th- 228 , Th- 230 and Th- 232 in liquid effluents from Uranium mines and mills. The resolution of the αlpha spectrometer was found to be 200-300 KeV, when the scintillator was 8% T0P0, 0,77% scintimix-4 (91% PP0 and 9% Dimetil-P0P0P) and 10% of naphthalene in toluene. Aliquat-336 in xylene (30% v/v) was used to separate the thorium isotopes from other interfering radionuclides (U- 238 , U- 234 , Ra- 226 , Po- 210 ). Under the extraction experimental conditions, the detection limits were 1,2 pCi/1 for Th- 232 , 1,2 pCi/1 for Th- 230 and 0,9 pCi/1 for Th- 228 , for 1000 minutes of counting time. (author)

  2. The determination of Pu-241 by liquid scintillation counting in liquid effluents of the Karlsruhe Nuclear Research Center

    International Nuclear Information System (INIS)

    Godoy, J.M.; Schuettelkopf, H.; Pimpl, M.

    1983-04-01

    A procedure was developed to measure Pu-241 by liquid scintillation counting. Sample preparation was performed by electroplating of plutonium on stainless steel planchets. To correct the selfabsorption, the linear dependence of counting efficiency in the liquid scintillation counter from the resolution in the alpha spectrometer was used. Pu-238, Pu-239+240 and Pu-241 were measured in the liquid effluents of the Karlsruhe Nuclear Research Center (KfK). The concentrations in monthly mixed samples ranged from 0.07 until 46 nCi Pu-238/m 3 , from 0.13 until 2.1 nCi Pu-239+240/m 3 and from 25 until 190 nCi Pu-241/m 3 . Between 5.4% and 41% of the plutonium content of the KfK waste water are released to the River Old Rhine. The values for the activity ratio Pu-238/Pu-239+240 are between 0.39 and 1.1 and for Pu-241/Pu-239+240 are between 11 and 300. The mean value for Pu-241/Pu-239+240 is 61. The dose exposure of the environmental population of the Karlsruhe Nuclear Research Center caused by released Pu-241 is negligible low. (orig./HP) [de

  3. Methods of reducing liquid effluent from the OSU TRIGA MKII Reactor

    International Nuclear Information System (INIS)

    Higginbotham, J.F.; Dodd, B.; Pratt, D.S.; Smith, S.; Anderson, T.V.

    1992-01-01

    In 1991, the OSU Radiation Center implemented a program to minimize the liquid effluent generated by the reactor facility. The goal of program is to become a 'zero' release facility with regards to routine liquid discharges. Only two liquid waste streams exist for the OSU reactor facility: discharges resulting from changing resin in the deminerializer and decontamination of equipment, primarily sample loading tubes. This paper describes a system which allows remote resin exchange to performed with the collection of all flush water. This water is then recycled for use as makeup for the primary water system. The service life of the resin is maximized by using a steam distillation unit as the source of makeup water to the deminerializer system instead of water coming directly from the City of Corvallis water supply. The second source of liquid waste water comes from the decontamination of the plastic loading tubes used to encapsulate samples. This process originally involved placing the tubes in a dishwasher and sending the discharge to a hold up tank. If the radionuclide concentrations in the tank were below the maximum permissible concentrations of 10CFR20 then it was released to the sanitary sewerage. This process was replaced in 1991 with a system which involved manual washing and rinsing of the tubes with the liquids being absorbed for disposal as solid waste. This paper will also describe the system which is being built to replace this process. It will use the dishwasher unit again but the liquid discharge will collected for absorption and disposal as solid waste. (author)

  4. Treatment of liquid effluent from uranium mines and mills. Report of a co-ordinated research project 1996-2000

    International Nuclear Information System (INIS)

    2004-10-01

    Treatment and control of liquid effluents produced during uranium mining and milling operations is an integral part of environmental project management. Research has continued to add to the large body of science that has been built up around the treatment of radioactive and non-radioactive effluents to minimize their long-term environmental impact. The objective of the meetings on which this publication is based was to exchange information on active effluent treatment technologies that have application during operations and passive treatment techniques such as constructed wetlands and use of micro-organisms that are applicable during project reclamation and long-term care and maintenance. Papers describe effluent treatment case histories from active uranium mining and processing operations as well as effluent treatment research on both active and passive systems that have potential application under a wide range of operating and post-operational conditions including new information on high-density sludge from effluent neutralization (Australia), aerated manganese hydroxide for removal of radium (China), nanofiltration and macropore resins to treat mine water (Australia and China), in situ microbial treatment and permeable reactive walls for treatment of contaminated groundwater (Germany), construction of wetlands to treat mine water runoff (Australia and Germany), biogenic granules to remove 226 Ra from mill effluent (India), self-remediation of acidic in situ leach aquifers (Kazakhstan) and sorption characteristics of soil for self-remediation of contaminated groundwater (Hungary). These and other topics presented in this publication will be of interest to technical personnel who deal with day-to-day practical aspects of liquid effluent control and treatment at uranium production facilities worldwide

  5. Etude comparative d'efficacité de prétraitement des effluents d'une ...

    African Journals Online (AJOL)

    INSPIRON

    1 litre d'eau à traiter avec un coagulant commercial (sulfate d'aluminium) à des doses croissantes (0 à 1.2 g/litre d'eau à traiter) et jumelées séparément à une concentration unique et constante d'adjuvant de floculation. (polyélectrolyte SP6) de 1 mg/l. Le temps global d'un essai est de 50 minutes. Il correspond à 5 minutes ...

  6. Derived release limits (DRL's) for airborne and liquid effluents from the Chalk River Nuclear Laboratories during normal operations

    International Nuclear Information System (INIS)

    Palmer, J.F.

    1981-02-01

    Derived release limits (DRL's), based on regulatory dose limits, have been calculated for routine discharges of radioactivity in airborne and liquid effluents from the Chalk River Nuclear Laboratories. Three types of sources of airborne effluents were considered: the NRX/NRU stack, the 61 m stack connected to the 99 Mo production facility, and a roof vent typical of those installed on several buildings on the site. Sources of liquid effluents to the Ottawa River were treated as a single source from the site as a whole. Various exposure pathways to workers on the site and to members of the public outside the site boundary were considered in the calculations. The DRL's represent upper limits for routine emissions of radioactivity from the Chalk River Nuclear Laboratories to the surrounding environment. Actual releases are regulated by Administrative Levels, set lower than the DRL's, and are confirmed by monitoring. (author)

  7. Monitoring of the radioactive liquid effluents discharged from IPEN-CNEN/SP. Optimization of the procedures adopted

    International Nuclear Information System (INIS)

    Seki, C.R.

    1990-01-01

    The main purpose of a radioactive liquid effluents monitoring of a nuclear installation is to determine the amount of radioactivity discharged to the environment, as well as, to verify if this activity is below the authorized discharge limits established by the competent authority. Although this control has been established on a routine basis since the beginning of operation of the nuclear installations available at IPEN, the growing of such facilities in the last years has implied in an increase in the number of samples to be analyzed. The aim of this work is, therefore, to optimize the procedures adopted in the Environmental Monitoring Division of IPEN-CNEN/SP for the activity measurement of the liquid effluents discharged to the environment. Since these effluents are discharged to Pinheiros river, which presents a high dilution factor, a study is also carried out in order to verify if the activity present can be measured by the equipment available. (author)

  8. Decontamination of irradiated fuel processing waste using lead paraperiodate; Decontamination des effluents de traitement des combustibles irradies par le paraperiodate de plomb

    Energy Technology Data Exchange (ETDEWEB)

    Auchapt, J M [Commissariat a l' Energie Atomique, Chusclan (France). Centre de Production de Plutonium de Marcoule

    1967-07-01

    The process is designed to eliminate ruthenium. It consists in an oxidation using para-periodic acid whose excess, acting then as a carrying-over agent, is precipitated in the form of a lead salt at a pH of 5 or 6. This process makes it possible to precipitate 80 to 98 per cent of the ruthenium which is not removed by the conventional precipitation techniques which follow it. If the waste is a reducing agent, it is pre-oxidized using ozone or potassium permanganate. The process was developed at Marcoule in 1963 and has since 1965 been applied industrially; its cost price is of the same order of magnitude as conventional processes and its results are satisfactory. (author) [French] Le procede est destine a l'elimination du ruthenium. Il consiste en une oxydation par l'acide par paraperiodique dont l'exces, jouant alors le role d'entraineur, est precipite sous forme de sel de plomb a pH 5 ou 6. Ce traitement permet de precipiter 80 a 98 pour cent du ruthenium rebelle aux traitements de precipitation classique, qui doivent le suivre. Si l'effluent est reducteur il est preoxyde a l'ozone ou au permanganate de potassium. Mis au point a Marcoule en 1963, il est depuis 1965 exploite industriellement, son prix de revient est du meme ordre de grandeur que celui des traitements habituels et les resultats ont donne satisfaction. (auteur)

  9. Fission product determination in irradiated fuel processing waste (electrophoresis); Dosage des produits de fission dans les effluents de traitement des combustibles irradies (electrophorese)

    Energy Technology Data Exchange (ETDEWEB)

    Auchapt, J M; Tret, J [Commissariat a l' Energie Atomique, Centre de Marcoule, 30 - Bagnols-sur-Ceze (France). Centre de Production de Plutonium de Marcoule. Services d' Extraction du Plutonium

    1966-07-01

    This dosage method concerns fission products present in the waste produced from the processing of cooled irradiated fuels. - Sr, Cs, Ce, Y, Ru by quantitative analysis; - Zr, Nb by qualitative analysis. It includes electrophoresis on paper strips one meter long which is then analysed between two window-less Geiger counters. For an activity of 10{sup -2} {mu}Ci of any cation in a 10 {mu}l spot, the standard error {sigma} if 3 to 4 per cent. complete analysis lasts about 5 hours. (authors) [French] Cette methode de dosage concerne les produits de fission presents dans les effluents de traitement des combustibles irradies refroidis: - Sr, Cs, Ce, Y, Ru en analyse quantitative; - Zr, Nb en analyse qualitative. Elle comporte une electrophorese sur bande de papier de un metre de longueur suivie d'un depouillement entre deux compteurs Geiger sans fenetre. Pour une activite de 10{sup -2} {mu}Ci d'un cation quelconque dans une tache de 10 {mu}l l'erreur standard {sigma} est de 3 a 4 pour cent. L'analyse complete demande environ 5 heures. (auteurs)

  10. Decree No 74-1181 of 31 December 1974 concerning liquid radioactive effluent releases from nuclear installations

    International Nuclear Information System (INIS)

    1975-01-01

    This Decree prescribes the licensing procedure for the release of liquid wastes from nuclear installations as well as the technical supervision of such operations. It does not apply to the transport of radioactive effluents which is governed by the regulations on the transport of dangerous goods. (NEA) [fr

  11. Biotransformation of chromium (VI) in liquid effluents by resistant bacteria isolated from the Matanza-Riachuelo basin, in Argentina.

    Science.gov (United States)

    González, Ana Julieta; Caimán, Carolina; Gorino, Natalia; Fortunato, María Susana; Radice, Marcela; Gómez, Carlos; Mujica, Carolina; Marquina, Lorena; Gallego, Alfredo; Korol, Sonia Edith

    2017-10-10

    The aims of this investigation were to evaluate the bacterial resistance to zinc, copper, chromium (VI) and lead in surface water streams from Buenos Aires, Argentina; to select a chromium-resistant strain able to remove the metal in batch process and to evaluate the potential of this strain to remove chromium (VI) in liquid effluents. Bacterial resistance to the metals was evaluated by determining the minimal inhibitory concentration. The kinetic of chromium (VI) removal by one of the resistant strains was studied in nutrient broth with 50 and 100 mg L -1 of the metal, as well as an effluent from an electroplating industry. High resistance to all the metals under study was observed in the bacterial communities of the Matanza-Riachuelo basin. A chromium-resistant strain was isolated and identified as Microbacterium sp. It was able to remove 50 and 100 mg L -1 of Cr (VI) in 36 and 66 h respectively, with efficiency higher than 99%. Experiments with liquid effluents showed the ability of the strain to transform 150 mg L -1 of the metal in 84 h, with efficiency higher than 99%. These results show the potential of this native strain for the treatment of liquid effluents that contain chromium (VI).

  12. Estimation of low level gross alpha activities in the radioactive effluent using liquid scintillation counting technique

    International Nuclear Information System (INIS)

    Bhade, Sonali P.D.; Johnson, Bella E.; Singh, Sanjay; Babu, D.A.R.

    2012-01-01

    A technique has been developed for simultaneous measurement of gross alpha and gross beta activity concentration in low level liquid effluent samples in presence of higher activity concentrations of tritium. For this purpose, alpha beta discriminating Pulse Shape Analysis Liquid Scintillation Counting (LSC) technique was used. Main advantages of this technique are easy sample preparation, rapid measurement and higher sensitivity. The calibration methodology for Quantulus1220 LSC based on PSA technique using 241 Am and 90 Sr/ 90 Y as alpha and beta standards respectively was described in detail. LSC technique was validated by measuring alpha and beta activity concentrations in test samples with known amount of 241 Am and 90 Sr/ 90 Y activities spiked in distilled water. The results obtained by LSC technique were compared with conventional planchet counting methods such as ZnS(Ag) and end window GM detectors. The gross alpha and gross beta activity concentrations in spiked samples, obtained by LSC technique were found to be within ±5% of the reference values. (author)

  13. Alternatives to disposal of Hanford Site liquid effluents to the soil column

    International Nuclear Information System (INIS)

    Meinhardt, C.C.; Flyckt, D.L.; Wirsing, R.M.; Winterhalder, J.A.

    1987-04-01

    Alternative systems were selected for 28 effluent streams, based on the use of available technology and ability to eliminate the contaminated effluent or reduce contaminant levels to meet specified effluent disposal criteria and standards derived from DOE Orders and environmental statutes. This study determined that technically feasible alternative waste disposal systems are available. 6 refs., 2 figs., 2 tabs

  14. Examination of vegetation around a nuclear plant emitting gaseous fluorides in order to detect fluorine pollution; Utilisation des vegetaux pour detecter la pollution fluoree autour d'une usine susceptible d'emettre des effluents gazeux fluores

    Energy Technology Data Exchange (ETDEWEB)

    Teulon, Francoise; Bonnaventure, J. P. [Commissariat a l' energie atomique et aux energies alternatives - CEA, Centre de Pierrelatte, Section de Protection contre les Radiations (France)

    1971-08-15

    Fluorine pollution (chronic or occasional) around a plant rejecting gaseous fluoride effluents can be detected from vegetation samples by chemical analysis. Systematic monitoring allows the effects and gravity of the pollution to be estimated. The analytical method used consists of a double distillation (in phosphoric acid and perchloric acid) followed by a spectro-colorimetric analysis (alizarine-complexon-lanthane). This method of control allows both the efficiency of the trapping installations and also the appearance of effluents at unexpected places to be checked, In the event of an accident it is possible to determine the advisability of prohibiting the consumption of locally grown produce by humans or fodder by cattle. Research conducted in order to determine the relation between visible, damage to certain vegetables (tomatoes, haricot beans and sorghum) and their fluorine contents demonstrated that such a relation appears above all at the level of the leaves; chemical analysis may thus be used to confirm or reject information obtained on the basis of visual evidence [French] La detection d'une pollution fluoree (chronique ou accidentelle) autour d'une usine susceptible d'emettre des effluents gazeux fluores peut etre avantageusement realisee par un reseau de prelevements vegetaux suivis de dosages chimiques. Une surveillance systematique permet une evaluation des consequences et du degre de gravite de la pollution. La methode d'analyse consiste en une double distillation (dans l'acide phosphorique et l'acide perchlorique) suivie d'une spectrocolorimetrie (alizarine-complexon-lanthane). Ce mode de controle permet non seulement de verifier si les installations de piegeage sont efficaces mais egalement de localiser des points d'emission imprevus. En cas d'accident, on peut egalement juger de l'opportunite d'interdire la consommation des legumes par les habitants ou du fourrage par le betail des environs. Enfin, des etudes experimentales ont ete realisees pour

  15. Approach to the problem of liquid effluents in petrochemical plants; Abordagem do problema efluentes liquidos em plantas petroquimicas

    Energy Technology Data Exchange (ETDEWEB)

    Rios, Cordelia Alves [PROMON Engenharia SA, Rio de Janeiro, RJ (Brazil)

    1993-12-31

    It represents the typical example of petrochemical company that uses the responsible care. The company looks for solve the liquid effluent problems of its units at a complete view. First of all, they made a complete report of the environmental scenario through the operational conditions (it included the collect system, effluent treatment, etc.) and their connection with the environmental problems. In the following step was made the necessary changes to establish the effluents pollute level below the allowable levels and to avoid soil contamination. The company has made the modifications at the following systems:a closed system to collect and reprocess process drains; collect, transfer and retention of contaminated storm water; a stripper column and a solid removal system to treat contaminated water. (author) 2 figs.

  16. Approach to the problem of liquid effluents in petrochemical plants; Abordagem do problema efluentes liquidos em plantas petroquimicas

    Energy Technology Data Exchange (ETDEWEB)

    Rios, Cordelia Alves [PROMON Engenharia SA, Rio de Janeiro, RJ (Brazil)

    1992-12-31

    It represents the typical example of petrochemical company that uses the responsible care. The company looks for solve the liquid effluent problems of its units at a complete view. First of all, they made a complete report of the environmental scenario through the operational conditions (it included the collect system, effluent treatment, etc.) and their connection with the environmental problems. In the following step was made the necessary changes to establish the effluents pollute level below the allowable levels and to avoid soil contamination. The company has made the modifications at the following systems:a closed system to collect and reprocess process drains; collect, transfer and retention of contaminated storm water; a stripper column and a solid removal system to treat contaminated water. (author) 2 figs.

  17. Radiation treatment of gaseous and liquid effluents for contaminant removal. Proceedings of a technical meeting

    International Nuclear Information System (INIS)

    2005-12-01

    The Technical Meeting on Radiation Processing of Gaseous and Liquid Effluents conducted in Sofia, Bulgaria, 7-10 September 2004, discussed and evaluated issues related to the status and future trends in radiation application for environmental protection. Five experts from Bulgaria, India, the Republic of Korea, Poland, and the United States of America were invited to provide their experiences in this field. Twenty cost-free participants and observers - from Bulgaria, India, Lithuania, Poland and Ukraine -joined the meeting, and 15 papers in total were presented. Research and development in radiation processing of gaseous and liquid effluents is undertaken in three fields: electron beam flue gas treatment (SO x and NO x removal), wastewater purification and sewage sludge sterilization. Wastewater or sludge treatment and flue gas purification all differ from technological points of view, but they are common services and applications of environmental radiation technology applications, based mostly on electron accelerators. The technical meeting discussed new development in the field of radiation applications in environmental service, especially the status and prospects of radiation processing of gaseous and liquid effluents. Progress in the field of electron accelerators and gamma sources is crucial for routine application of the technology. Cost reduction and improvement of technical reliability are substantial especially for high power of accelerators and high activity of the sources needed for environmental applications. Environmental applications were carefully reviewed in accordance with the existing regulations and state of the art knowledge. The comparison with conventional commercial technologies was addressed as well. In flue gas treatment, applicability of the technology using different fossil fuels (coal, lignite, oil, etc.) was reviewed. The elaborated materials cover the technical and economical evaluation of the technologies. The possible applications of

  18. Liquid state behaviour of semi-conducting materials; Comportement a l'etat liquide des materiaux semiconducteurs

    Energy Technology Data Exchange (ETDEWEB)

    Vandevyver, M. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1968-07-01

    This work is a review of the present state of knowledge concerning the behaviour in the liquid state of materials having semi-conducting properties in the solid state. In the case of many materials it is observed that a 'short-distance order' persists (with modifications) at temperatures above the melting point; this phenomenon is responsible for the semi-conducting properties of certain liquids. A decrease in the mobility of the carriers is generally observed on fusion, whereas the width of the forbidden zone increases: {delta}E{sub g} = {delta}E{sub g1} + {delta}E{sub g2}; {delta}E{sub g1} which is related to the expansion of the crystal is usually positive whereas {delta}E{sub g2} which is related to a change in the short-distance order is negative. According to the relative importance of these two phenomena, {delta}E{sub g} is either positive or negative, involving an increase or a decrease in the semiconducting nature of the material at its melting point. Various examples are presented, in particular that of selenium-tellurium solutions. The experimental study of the electrical properties of liquids comes up against major difficulties (the Hall effect in particular). It is shown nevertheless that the theoretical studies explain semi-quantitatively the known experimental results. (author) [French] Cette etude fait le point sur l'etat actuel des connaissances relatives au comportement a l'etat liquide des materiaux presentant a l'etat solide des proprietes semiconductrices. Dans de nombreux materiaux on observe la persistance (avec modification), d'un 'ordre a courte distance' a des temperatures superieures a celles de la fusion; ceci est a l'origine des proprietes semiconductrices de certains liquides. A la fusion on observe generalement une diminution de la mobilite des porteurs tandis que la largeur de la bande interdite subit un accroissement: {delta}E{sub g} = {delta}E{sub g1} + {delta}E{sub g2}; {delta}E{sub g1

  19. Calculation of releases of radioactive materials in gaseous and liquid effluents from boiling water reactors (BWR-GALE Code)

    International Nuclear Information System (INIS)

    Bangart, R.L.; Bell, L.G.; Boegli, J.S.; Burke, W.C.; Lee, J.Y.; Minns, J.L.; Stoddart, P.G.; Weller, R.A.; Collins, J.T.

    1978-12-01

    The calculational procedures described in the report reflect current NRC staff practice. The methods described will be used in the evaluation of applications for construction permits and operating licenses docketed after January 1, 1979, until this NUREG is revised as a result of additional staff review. The BWR-GALE (Boiling Water Reactor Gaseous and Liquid Effluents) Code is a computerized mathematical model for calculating the release of radioactive material in gaseous and liquid effluents from boiling water reactors (BWRs). The calculations are based on data generated from operating reactors, field tests, laboratory tests, and plant-specific design considerations incorporated to reduce the quantity of radioactive materials that may be released to the environment

  20. Derived release limits for radionuclides in airborne and liquid effluents for the Whiteshell Nuclear Research Establishment and errata

    International Nuclear Information System (INIS)

    Lemire, A.E.

    1989-08-01

    Radionuclides released to the environment may cause external and internal radiation exposure to man via a number of potential pathways. The resulting radiation dose due to such releases from any operating facility must be kept below dose limits specified in the regulations issued by the Atomic Energy Control Board of Canada. At the Whiteshell Nuclear Research Establishment (WNRE), there is one primary source of liquid effluent to the Winnipeg River via the process water outfall. There are five sources of gaseous effluents: the WR-1 stack; the incinerator stack in the waste management area; the active laboratories building (including the hot cells); the Active-Liquid Waste Treatment Centre; and the compactor-baler in the Waste Management Area. This report presents the methodology and models used to calculate the maximum permissible release rates of radionuclides for each of these sources

  1. The main rules regarding the management of solid waste and liquid effluent contaminated during use at nuclear medicine departments

    International Nuclear Information System (INIS)

    Boudouin, E.

    2011-01-01

    This article describes the key requirements applicable to the management of contaminated medical waste and effluent from hospitals and health care centres, and more especially from nuclear medicine departments that use radionuclides for the purposes of diagnosis (in vivo or in vitro) or in patient treatment. It also presents the key management regulations, making a distinction between contaminated solid waste and contaminated liquid waste from such nuclear medicine departments. (author)

  2. Method for the simultaneous determination of monoaromatic and polycyclic aromatic hydrocarbons in industrial effluents using dispersive liquid-liquid microextraction with gas chromatography-mass spectrometry.

    Science.gov (United States)

    Makoś, Patrycja; Fernandes, André; Boczkaj, Grzegorz

    2018-02-23

    We present a new method for simultaneous determination of 22 monoaromatic and polycyclic aromatic hydrocarbons in postoxidative effluents from the production of petroleum bitumen using dispersive liquid-liquid microextraction coupled to gas chromatography and mass spectrometry. The eight extraction parameters including the type and volume of extraction and disperser solvent, pH, salting out effect, extraction, and centrifugation time were optimized. The low detection limit ranging from 0.36 to 28 μg/L, limit of quantitation (1.1-84 μg/L), good reproducibility, and wide linear ranges, as well as the recoveries ranging from 71.74 to 114.67% revealed that the new method allows the determination of aromatic hydrocarbons at low concentration levels in industrial effluents having a very complex composition. The developed method was applied to the determination of content of mono- and polycyclic aromatic hydrocarbons in samples of raw postoxidative effluents in which 15 compounds were identified at concentrations ranging from 1.21 to 1017.0 μg/L as well as in effluents after chemical treatment. © 2018 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

  3. Systematic study of the use of electrical fields for improving heat exchange in boiling liquids; Etude systematique de l'utilisation de champs electriques pour l'amelioration des echanges thermiques dans des liquides bouillants

    Energy Technology Data Exchange (ETDEWEB)

    Bochirol, L; Bonjour, E; Lagnier, R; Verdier, J; Weil, L [Commissariat a l' Energie Atomique, Grenoble (France).Centre d' Etudes Nucleaires

    1961-07-01

    We have studied, at the boiling point, for liquids with various electrical properties (hexane, benzene, trichloroethylene, demineralized water, acetone, methyl-ethyl-ketone, etc...) the effect of the application of electric fields on the exchange coefficients and on the maximum dissipative powers before calefaction. We have given the mechanism of the significant improvements obtained (multiplication by a factor of 2 to 10): - in the natural convection zone by showing the role played by the dielectric properties of the liquids under study; - in the zone of nuclear boiling by analysis of the forces acting on the boiling nuclei. Finally we give some experimental results concerning measurements made under pressure until local boiling occurred: they show the possibility of some interesting applications of the method. (author) [French] On a etudie, a l'ebullition, sur des liquides de caracteristiques electriques diverses (hexane, benzene, trichlorethylene, eau demineralisee, acetone, methylethylcetone, etc...) les effets de l'application de champs electriques sur les coefficients d'echanges et les puissances maximales dissipables avant calefaction. On a precise le mecanisme des ameliorations importantes obtenues (multiplication par un facteur 2 a 10): - dans la zone de convection naturelle en mettant en evidence le role des caracteristiques dielectriques des liquides etudies; - dans la zone d'ebullition nucleaire par analyse des forces mises en jeu sur les noyaux d'ebullition. On donne enfin des resultats experimentaux sur des mesures effectuees sous pression jusqu'a l'ebullition locale: ils illustrent des possibilites d'applications interessantes du procede. (auteur)

  4. Automated system of control of radioactive liquid effluents of patients submitted to therapy in hospitals of nuclear medicine (SACEL)

    International Nuclear Information System (INIS)

    Ruiz C, M.A.; Rivero G, T.; Celis del Angel, L.; Sainz M, E.; Molina, G.

    2006-01-01

    Different hospitals of nuclear medicine require of the technical attendance for the design, construction and instrumentation of an effluents retention system coming from the room dedicated to the medical application of iodine 131, with the one object of giving execution to the normative requirements of radiological protection, settled down in the General Regulation of Radiological Safety (RGSR) emitted by the CNSNS in November, 1988 and in the corresponding official standards. An automatic system of flow measurement, the activity concentration of the effluents to the drainage, the discharges control and the automated report it will allow the execution of the national regulations, also the elimination of unhealthy activities as the taking of samples, analysis of those same and the corresponding paperwork, its will allow that the SACEL is capable of to carry out registrations that are to consult in an automated way. The changes in the demands of the National Commission of Nuclear Safety and Safeguards in relation to the liberation of radioactive material in hospitals by medical treatments, it has created the necessity to develop a system that quantifies and dose the liquid effluents of people under thyroid treatment with iodine-131 to the drainage. The Automated System of Control of radioactive liquids effluents generated in Hospitals of Nuclear Medicine (SACEL) developed in the National Institute of Nuclear Research, it fulfills this regulation, besides improving the work conditions for the medical and technical personnel of the hospital in that are installed, since this system has the advantage of to be totally automated and to require of a minimum of attendance. The SACEL is an electro-hydraulic system of effluents control, based in the alternate operation of two decay deposits of the activity of the material contaminated with iodine-131. The system allows to take a registration of those volumes and liberated dose, besides being able to be monitoring in remote

  5. An assessment of the quality of liquid effluents from opaque beer ...

    African Journals Online (AJOL)

    driniev

    2005-01-01

    Jan 1, 2005 ... The effluent treatment plants in both plants were not only inadequate but also ... Keywords: industrial effluents, opaque beer-brewery, pollution load, quality, quantity ... to hydraulic overloading and corrosion of the sewer pipe system ... The two breweries studied in this paper produce African traditional.

  6. Comparison of different liquid anaerobic digestion effluents as inocula and nitrogen sources for solid-state batch anaerobic digestion of corn stover

    International Nuclear Information System (INIS)

    Xu Fuqing; Shi Jian; Lv Wen; Yu Zhongtang; Li Yebo

    2013-01-01

    Highlights: ► Compared methane production of solid AD inoculated with different effluents. ► Food waste effluent (FWE) had the largest population of acetoclastic methanogens. ► Solid AD inoculated with FWE produced the highest methane yield at F/E ratio of 4. ► Dairy waste effluent (DWE) was rich of cellulolytic and xylanolytic bacteria. ► Solid AD inoculated with DWE produced the highest methane yield at F/E ratio of 2. - Abstract: Effluents from three liquid anaerobic digesters, fed with municipal sewage sludge, food waste, or dairy waste, were evaluated as inocula and nitrogen sources for solid-state batch anaerobic digestion of corn stover in mesophilic reactors. Three feedstock-to-effluent (F/E) ratios (i.e., 2, 4, and 6) were tested for each effluent. At an F/E ratio of 2, the reactor inoculated by dairy waste effluent achieved the highest methane yield of 238.5 L/kgVS feed , while at an F/E ratio of 4, the reactor inoculated by food waste effluent achieved the highest methane yield of 199.6 L/kgVS feed . The microbial population and chemical composition of the three effluents were substantially different. Food waste effluent had the largest population of acetoclastic methanogens, while dairy waste effluent had the largest populations of cellulolytic and xylanolytic bacteria. Dairy waste also had the highest C/N ratio of 8.5 and the highest alkalinity of 19.3 g CaCO 3 /kg. The performance of solid-state batch anaerobic digestion reactors was closely related to the microbial status in the liquid anaerobic digestion effluents.

  7. Comparison of different liquid anaerobic digestion effluents as inocula and nitrogen sources for solid-state batch anaerobic digestion of corn stover

    Energy Technology Data Exchange (ETDEWEB)

    Xu Fuqing; Shi Jian [Department of Food, Agricultural and Biological Engineering, Ohio State University, Ohio Agricultural Research and Development Center, 1680 Madison Ave., Wooster, OH 44691 (United States); Lv Wen; Yu Zhongtang [Department of Animal Sciences, Ohio State University, Columbus, OH 43210 (United States); Li Yebo, E-mail: li.851@osu.edu [Department of Food, Agricultural and Biological Engineering, Ohio State University, Ohio Agricultural Research and Development Center, 1680 Madison Ave., Wooster, OH 44691 (United States)

    2013-01-15

    Highlights: Black-Right-Pointing-Pointer Compared methane production of solid AD inoculated with different effluents. Black-Right-Pointing-Pointer Food waste effluent (FWE) had the largest population of acetoclastic methanogens. Black-Right-Pointing-Pointer Solid AD inoculated with FWE produced the highest methane yield at F/E ratio of 4. Black-Right-Pointing-Pointer Dairy waste effluent (DWE) was rich of cellulolytic and xylanolytic bacteria. Black-Right-Pointing-Pointer Solid AD inoculated with DWE produced the highest methane yield at F/E ratio of 2. - Abstract: Effluents from three liquid anaerobic digesters, fed with municipal sewage sludge, food waste, or dairy waste, were evaluated as inocula and nitrogen sources for solid-state batch anaerobic digestion of corn stover in mesophilic reactors. Three feedstock-to-effluent (F/E) ratios (i.e., 2, 4, and 6) were tested for each effluent. At an F/E ratio of 2, the reactor inoculated by dairy waste effluent achieved the highest methane yield of 238.5 L/kgVS{sub feed}, while at an F/E ratio of 4, the reactor inoculated by food waste effluent achieved the highest methane yield of 199.6 L/kgVS{sub feed}. The microbial population and chemical composition of the three effluents were substantially different. Food waste effluent had the largest population of acetoclastic methanogens, while dairy waste effluent had the largest populations of cellulolytic and xylanolytic bacteria. Dairy waste also had the highest C/N ratio of 8.5 and the highest alkalinity of 19.3 g CaCO{sub 3}/kg. The performance of solid-state batch anaerobic digestion reactors was closely related to the microbial status in the liquid anaerobic digestion effluents.

  8. Criticality safety issues arising from the treatment of liquid effluent streams from the reprocessing of thermal oxide fuel

    International Nuclear Information System (INIS)

    Thorne, P.R.; Farrington, L.M.

    1991-01-01

    The BNFL THORP plant will reprocess irradiated oxide fuel from thermal reactors to recover plutonium dioxide and uranium trioxide in a pure form. A consequence of the reprocessing is that several liquid effluent streams are produced which can contain residual fissile material. Generally, the treatment of these effluent streams is carried out in large vessels which are not geometrically favourable with regard to nuclear safety. This is possible because the concentration of fissile material in solution is far less than the safely subcritical infinite sea concentrations. The situation is complicated by the presence of precipitated solids in some vessels and crud layers in others. Experimental measurements have been used to characterise these solids in order to extend the usual safe limits, and to provide an acceptable operating regime. Based on the experimental characterisation of the solids, the neutronics computer codes WIMS and MONK have been used to determine the optimum possible conditions existing, and to determine the safe fissile mass limits for these systems. The limits which are derived have been used to provide alarm and trip levels for instrumentation which has been employed in a novel way. It has been shown that the plant can be operated successfully and remains acceptably safe taking into account the presence of solids in the liquid effluent streams. (author)

  9. Method for the determination of carboxylic acids in industrial effluents using dispersive liquid-liquid microextraction with injection port derivatization gas chromatography-mass spectrometry.

    Science.gov (United States)

    Makoś, Patrycja; Fernandes, Andre; Boczkaj, Grzegorz

    2017-09-29

    The paper presents a new method for the determination of 15 carboxylic acids in samples of postoxidative effluents from the production of petroleum bitumens using ion-pair dispersive liquid-liquid microextraction and gas chromatography coupled to mass spectrometry with injection port derivatization. Several parameters related to the extraction and derivatization efficiency were optimized. Under optimized experimental conditions, the obtained limit of detection and quantification ranged from 0.0069 to 1.12μg/mL and 0.014 to 2.24μg/mL, respectively. The precision (RSD ranged 1.29-6.42%) and recovery (69.43-125.79%) were satisfactory. Nine carboxylic acids at concentrations ranging from 0.10μg/mL to 15.06μg/mL were determined in the raw wastewater and in samples of effluents treated by various oxidation methods. The studies revealed a substantial increase of concentration of benzoic acids, in samples of wastewater after treatment, which confirms the need of carboxylic acids monitoring during industrial effluent treatment processes. Copyright © 2017 Elsevier B.V. All rights reserved.

  10. Study of sample-detector assemblies for application to in-situ measurement of radioactivity in liquid effluents

    International Nuclear Information System (INIS)

    Pendharkar, K.A.; Narayanan Kutty, K.; Krishnamony, S.

    1991-01-01

    This paper describes the experimental investigations carried out on four different types of sample-detector assemblies with a view to determining their detection limits and relative merits for application to in-situ measurement of radioactivity in liquid effluents. The four systems studied were: (1) gamma detection using 11 cm x 8 cm NaI (Tl) scintillation detector inserted in the cavity of a specially designed stainless steel chamber of capacity 15 liters, (2) gamma detection using a metal-walled G.M. counter in a similar manner, (3) beta detection using twin thin-walled G.M. counters immersed in liquid, and (4) end window G.M. counter positioned above the liquid surface in a shallow tray. The design features of an in-line monitor employing a 11 cm x 8 cm NaI (Tl) detector used for the routine monitoring of beta gamma activity concentrations in the low level effluents of the Tarapur Fuel Processing Plant are described. (author). 1 tab

  11. Soil plutonium and cesium in stream channels and banks of Los Alamos liquid effluent-receiving areas

    International Nuclear Information System (INIS)

    Nyhan, J.W.; White, G.C.; Trujillo, G.

    1982-01-01

    Stream channel sediments and adjacent bank soils found in three intermittent streams used for treated liquid effluent disposal at Los Alamos, New Mexico were sampled to determine the distribution of 238 Pu, sup(239,240)Pu and 137 Cs. Radionuclide concentrations and inventories were determined as functions of distance downstream from the waste outfall and from the center of the stream channel, soil sampling depth, stream channel-bank physiography, and the waste use history of each disposal area. Radionuclide concentrations in channel sediments were inversely related to distances up to 10 km downstream from the outfalls. For sites receiving appreciable waste effluent additions, contaminant concentrations in bank soils decreased with perpendicular distances greater than 0.38 m from the stream channel, and with stream bank sampling depths greater than 20-40 cm. Concentrations and total inventories of radionuclides in stream bank soils generally decreased as stream bank height increased. Inventory estimates of radionuclides in channel sediments exhibited coefficients of variation that ranged 0.41-2.6, reflecting the large variation in radionuclide concentrations at each site. Several interesting temporal relationships of these radionuclides in intermittent streams were gleaned from the varying waste use histories of the three effluent-receiving areas. Eleven years after liquid wastes were added to one canyon, the major radionuclide inventories were found in the stream bank soils, unlike most of the other currently-used receiving areas. A period of time greater than 6 yr seems to be required before the plutonium in liquid wastes currently added to the canyon is approximately equilibrated with the plutonium in the bank soils. These observations are discussed relative to waste management practices in these southwestern intermittent streams. (author)

  12. Soil plutonium and cesium in stream channels and banks of Los Alamos liquid effluent-receiving areas.

    Science.gov (United States)

    Nyhan, J W; White, G C; Trujillo, G

    1982-10-01

    Stream channel sediments and adjacent bank soils found in three intermittent streams used for treated liquid effluent disposal at Los Alamos, New Mexico were sampled to determine the distribution of 238Pu, 239,240Pu and 137Cs. Radionuclide concentrations and inventories were determined as functions of distance downstream from the waste outfall and from the center of the stream channel, soil sampling depth, stream channel-bank physiography, and the waste use history of each disposal area. Radionuclide concentrations in channel sediments were inversely related to distances up to 10 km downstream from the outfalls. For sites receiving appreciable waste effluent additions, contaminant concentrations in bank soils decreased with perpendicular distances greater than 0.38 m from the stream channel, and with stream bank sampling depths greater than 20-40 cm. Concentrations and total inventories of radionuclides in stream bank soils generally decreased as stream bank height increased. Inventory estimates of radionuclides in channel sediments exhibited coefficients of variation that ranged 0.41-2.6, reflecting the large variation in radionuclide concentrations at each site. Several interesting temporal relationships of these radionuclides in intermittent streams were gleaned from the varying waste use histories of the three effluent-receiving areas. Eleven yr after liquid wastes were added to one canyon, the major radionuclide inventories were found in the stream bank soils, unlike most of the other currently-used receiving areas. A period of time greater than 6 yr seems to be required before the plutonium in liquid wastes currently added to the canyon is approximately equilibrated with the plutonium in the bank soils. These observations are discussed relative to waste management practices in these southwestern intermittent streams.

  13. Scattering of Neutrons by Liquid Bromine; Diffusion des neutrons par le brome liquide; R; Dispersion de neutrones por bromo liquido

    Energy Technology Data Exchange (ETDEWEB)

    Coote, G E; Haywood, B C [Atomic Energy of Canada Ltd., Chalk River, Ontario (Canada)

    1963-01-15

    Neutrons of 0.037 eV and 0.0088 eV were scattered from a thin sample of liquid bromine at room temperature, and the energy distributions of the scattered neutrons measured at angles from 10{sup o} to 160{sup o} by the time-of-flight method. The angular distribution confirms the results of a previous study by Caglioti. Spectra were expressed in the form of the ''scattering law'' S({alpha},{beta}) of Egelstaff and analysed to derive the generalized frequency distribution p({beta}) of atomic motions in the liquid. The function p({beta}) has a broad smooth peak centred at {beta}{approx}0.3, and shows no evidence for discrete levels in the measured range 0<{beta}< 0.8: the general shape of the curve supports the 'quasi-crystalline' picture of the liquid. Difficulty in the absolute normalization of p({beta}) is discussed. (author) [French] Des neutrons de 0,037 eV et 0,0088 eV ont ete dissuses par un echantillon mince de brome liquide a la temperature ambiante; on a mesure, par la methode du temps de vol, les distributions d'energies des neutrons diffuses, pour des angles compris entre 10{sup o} et 160{sup o}. La distribution angulaire confirme les resultats d'une etude anterieure faite par Caglioti. Les spectres ont ete exprimes d'apres la ''loi de dispersion'' S({alpha},{beta}) d'Egelstaff et analyses pour determiner la distribution generalisee des frequences p({beta}) des mouvements atomiques dans le liquide. La fonction p({beta}) comporte un pic large et a faible pente dont le centre est a {beta} {approx} 0,3 et ne presente aucune indication de niveaux discrets dans la gamme mesuree 0 < {beta} < 0,8; la forme generale de la courbe confirme l'image ''quasi cristalline'' du liquide. Les auteurs examinent les difficultes qui s'opposent a la normalisation absolue de p({beta}). (author) [Spanish] Los autores han estudiado la dispersion de neutrones de 0,037 eV y 0,0088 eV en una muestra de bromo liquido de espesor reducido, a temperatura ambiente. La distribucion

  14. Safety evaluation of liquid radioactive effluents treatment system in a BWR reactor, through the LIQM03 code

    International Nuclear Information System (INIS)

    Zorrilla R, S.H.

    1978-01-01

    In this work we made a safety evaluation of the liquid radioactive effluents system in a plant using a BWR similar to that now installed in Laguna Verde. For that purpose, the computation program ORIGENwas modified, in order to keep up to date and adapt it to the PDP 10 computer, which is operating at the Computation Department of the Nuclear Center of Mexico, the code LIQM03 was the result of this modification. As usual in this work we dealt with problems which were solved opportunely, now we have at our disposal the code LIQM03 which will be in the future a very useful tool for this kind of evaluations. (author)

  15. Calculation of the annual radiation dose to the population in the vicinity of nuclear installations due to liquid effluents

    International Nuclear Information System (INIS)

    Gans, I.

    1991-01-01

    Since 1974, assessments of radiation exposure due to the emission of radioactive substances with liquid effluents have been done by the Institut fuer Wasser-, Boden- und Lufhygiene of the Federal Health Office and data have bee published in the annual reports in the series 'Umweltradioaktivitaet und Strahlenbelastung'. The paper explaines the radioecological models of ABG and AVV as far as they relate to the wastewater pathway, as well as the required modifications. Individual aspects of computation are explained referring to the dose calculations for 1989. (orig./DG) [de

  16. Evaluation code for the dose due to the discharges of liquid effluents of the Embalse nuclear power plant

    International Nuclear Information System (INIS)

    Lopez, Fabio O.; Boutet, Luis I.; Bruno, Hector A.; Gavini, Ricardo M.

    2004-01-01

    A new methodology is presented to assess the evaluation of the radiological impact to the population, due to the discharges to the environment of liquids effluents of Central Nuclear Embalse (CNE), located in the Province of Cordoba (Argentina). In order to carry out the dose evaluation, a code denominated EDDELIQ was developed, in this code the calculation of the radionuclides concentration in the water lake is made by means of a simple physical model of the type of complete mixture. The physical model is solved numerically by means of Runge Kutta method of second order. (author)

  17. Wastes treatment: Naskeo undertakes on the way of methanization; Traitement des effluents: Naskeo mise sur la methanisation

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    2005-09-15

    Naskeo proposes to cleanse the organic effluents of the chemical or pharmaceutical firms by methanization. A process which produces a renewable biogas, directly valorizable at the level of the process of the manufacturer. (O.M.)

  18. Disposal of Low-Activity Liquid Effluents by Dilution; Elimination par Dilution d'Effluents Liquides Faiblement Radioactifs; 0423 0414 0410 041b 0414 ; Eliminacion de Efluentes Liquidos de Baja Radiactividad por Dilucion

    Energy Technology Data Exchange (ETDEWEB)

    Bovard, P.; Candillon, C. [Service de Controle des Radiations et de Genie Radioactif, Commissariat a l' Energie Atomique, Saclay (France)

    1960-07-01

    From the results already obtained in France by monitoring radioactivity in the neighbourhood of nuclear plant, some conclusions may be drawn regarding the choice of disposal procedures. I. Results obtained In 1957 we started a progressive study of the effect exerted by nuclear plant. In order to establish the proportion due to the nuclear centres, the study comprises determination of the levels of natural radioactivity and artificial contamination. Examples related to reference areas are quoted. The greater part of artificial radioactivity is apparently due to radioactive fall-out; this is not surprising, considering the quantities of radioactive isotopes disposed of in France to date. Some laboratory tests have been made. These have helped to determine certain mechanisms, have increased our knowledge of site pollution, and have enabled us to improve our sampling methods. II. Laboratory tests These were concerned with 1. adsorption phenomena similar to those occurring in rivers and streams in the course of effluent dilution: fixation on finely-divided minerals, e.g. mica and quartz. Radioisotopes such as Sr{sup 9}'0, Cs{sup 137} and Y{sup 90} appear to behave very differently: under average disposal conditions Sr{sup 90} seems to be the least adsorbed; 2. soil and plant contamination, utilizing columns and cubes of soil in situ. We found it necessary to standardize our samples so as to facilitate further analysis and make the results comparable. III. Site selection and ways and means of disposal From this group of still incomplete results and studies we are attempting to educe certain principles to govern site selection. Once the site has been chosen, the experience gained enables natural conditions to be turned to account. (author) [French] Des resultats deja fournis par la surveillance en France, de la radioactivite aux alentours des installations nucleaires, il est possible de tirer certains enseignements quant au choix des processus de rejet. I. Resultats

  19. Calculation of risk-based detection limits for radionuclides in the liquid effluents from Korean nuclear power plants

    International Nuclear Information System (INIS)

    Cheong, Jae Hak

    2017-01-01

    In order to review if present detection limits of radionuclides in liquid effluent from nuclear power plants are effective enough to warrant compliance with regulatory discharge limits, a risk-based approach is developed to derive a new detection limit for each radionuclide based on radiological criteria. Equations and adjustment factors are also proposed to discriminate the validity of the detection limits for multiple radionuclides in the liquid effluent with or without consideration of the nuclide composition. From case studies to three nuclear power plants in Korea with actual operation data from 2006 to 2015, the present detection limits have turned out to be effective for Hanul Unit 1 but may not be sensitive enough for Kori Unit 1 (8 out of 14 radionuclides) and Wolsong Unit 1 (9 out of 42 radionuclides). However, it is shown that the present detection limits for the latter two nuclear power plants can be justified, if credit is given to the radionuclide composition. Otherwise, consideration should be given to adjustment of the present detection limits. The risk-based approach of this study can be used to determine the validity of established detection limits of a specific nuclear power plant. (author)

  20. Development of a surfactant liquid membrane extraction process for the cleansing of industrial aqueous effluents containing metallic cation traces

    International Nuclear Information System (INIS)

    Rapaumbya Akaye, Guy-Roland

    1994-01-01

    The purpose of this work was to develop a process of surfactant liquid membrane extraction to purify industrial waste solution containing Cu(II), Fe(III), and Zn(II) (about 0,1 g/L). The extractant is the ammonium salt of Cyanex 306 and Aliquat 336. The first part of this work deals with the study of the liquid-liquid extraction of the metals. The efficiency of the extractant has been shown for the extraction of each metal alone and for Cu(II) and Zn(II) in the case of a mixture of the three metals. During this study we have observed that Fe(III) is reduced to Fe(II) (which is not extracted by the salt of Cyanex 301) in presence of Cu(II) and the quaternary ammonium salt (Aliquat 336). The optimisation of the experimental conditions for the discontinuous surfactant liquid membrane process led us to choose the following composition of the emulsion: 1,5 % of Cyanex 301 salt, 2,5 % of ECA 4360, dodecan. The internal phase is an aqueous solution containing 3,5 mol/L of NaOH and 0,5 mol/L tri-ethanolamin The residual concentration of Cu(II) and Zn(II) in the external phase is very low. In the case of iron, only 60 % are extracted because of the reduction phenomenon (10 % in liquid-liquid extraction). The realisation of the continuous process in pulsed column, after optimisation of hydrodynamics conditions, leads to similar results. In stationary conditions, we obtain a raffinate containing less than 0,5 mg/L of Cu(II) and Zn(II) and 36 mg/L of iron. The internal phase contains about 2 g/L of Cu(II) an Zn(II). We tried and minimize the reduction of Fe(III) in surfactant liquid membrane process. Less than 16 % of iron cannot be reduced. This leads to a purification of only 84 % In the basis of these results, processes of purification have been proposed for effluents of various composition. They enable to purify the effluent and besides to concentrate the pollutants about twenty times. (author) [fr

  1. Design, calculation and testing on mock-up of B(U) f type LR 56 packaging for radioactive liquid effluent transport

    International Nuclear Information System (INIS)

    Belaud; Leconnetable; Daspet; Tombini; Tanguy

    1986-06-01

    Transport of radioactive acid liquid effluents are effected on tank truck inside nuclear center of the CEA. The cylindrical packaging type B(U) f has a capacity of 4,000l, a maximum permissible activity of 110 T Bq (3x10 4 Ci) and comprises a central element for liquid effluent containment to prevent contamination of environment and peripheral elements for mechanical, biological and thermal protection. This packaging is fixed on a trailer associated with a control box. Design and equipment of the packaging are studied for a maximum safety and in accordance with regulations [fr

  2. Study of the retention of fission products by a few common minerals. Application to the treatment of medium activity effluents (1962); Etude de la retention des produits de fission par quelques mineraux usuels. Application aux traitements d'effluents de moyenne activite specifique (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Auchapt, J M [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1962-07-01

    The conditions in which strontium is fixed on calcite (the object of the Geneva report P/395 - USA - 1958) are more closely studied and the work is extended to five fission products present in the effluents, and to 17 common rocks and minerals. Although as it turns out this fixation is not suitable as a method of treating the S.T.E. effluents (i.e. those from the Effluent Treatment plant at Marcoule), the study shows that all the crystals considered are strongly contaminated by simple contact with the effluents. (author) [French] Les conditions de fixation du strontium sur la calcite (objet du rapport de Geneve P/395 - USA - 1958) sont approfondies et l'etude est etendue aux cinq produits de fission presents dans les effluents et a 17 roches et minerais courants. Bien qu'en definitive cette fixation se revele inutilisable comme procede de traitement d'effluents S.T.E. (Station de Traitement des Effluents, Marcoule), l'etude montre que tous les cristaux consideres se contaminent fortement par simple contact avec les effluents. (auteur)

  3. A contribution to the study of radioactive waste dilution in the Rhone involving tests with a rhodamine B tracer; Contribution a l'etude de la dilution des effluents radioactifs dans le Rhone par le rejet experimental de rhodamine B

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J.; Marichal, M. [Commissariat a l' energie atomique et aux energies alternatives - CEA, Centre de production de plutonium de Marcoule, Service de protection contre les radiations (France)

    1961-07-01

    The process whereby waste from the Marcoule plant mixes with the water in the Rhone was followed in tests with rhodamine as a chemical tracer. Satisfactory dispersion was noted less than 4 km downstream from the waste discharge duct outlet, and the degree of homogeneity was considered to be satisfactory at the bridge of Roquemaure, und perfect at Avignon. This investigation not only revealed a complete absence of any preferential flow paths containing high radioactive waste concentrations, but it also enabled the most representative points to be selected at which to take Rhone water samples during future radioactive waste discharges. Reprint of a paper published in 'La Houille Blanche' N. 5 - Aug 196, p. 636-641 [French] L'emploi de la rhodamine comme traceur chimique a permis de suivre l'evolution du melange des effluents du Centre de Marcoule aux eaux du Rhone. La dispersion est deja satisfaisante a moins de 4 km en aval de la conduite des rejets, et l'homogeneite peut etre consideree comme atteinte au pont de Roquemaure et parfaite a Avignon. Cette etude a montre que les veines preferentielles ou se concentrait l'ecoulement des effluents radioactifs n'existent pas. Elle a permis de preciser en outre les emplacements les plus representatifs des points d'echantillonnage des eaux du Rhone au cours des rejets. Reproduction d'un article publie dans 'La houille blanche' N. 5 - Aug 196, p. 636-641.

  4. Analyse chronometrique intersexes de la resolution de la tache d'horizontalite des liquides

    Science.gov (United States)

    Berthiaume, Francois

    D'abondantes recherches ont demontre que la reussite a la tache d'horizontalite des liquides est en moyenne plus elevee chez les individus de sexe masculin que chez ceux de sexe feminin. Deux facteurs principaux ont ete proposes: il s'agit de la connaissance du principe physique de l'invariance de l'orientation des liquides et de certaines habiletes perceptives d'ordre visuel. Le but de la presente recherche est d'etablir la duree detaillee de la resolution de la tache d'horizontalite des liquides chez 185 filles et 180 garcons, ages de 15 a 19 ans et repartis en 8 groupes. Dans une version informatisee, le premier groupe trace la position de la surface de l'eau a l'interieur d'un contenant dans diverses inclinaisons et le deuxieme evalue si l'orientation d'une ligne y represente bien cette position; le troisieme groupe trace une horizontale dans un rectangle et le quatrieme juge si la ligne illustree y est bien horizontale. Quatre autres groupes executent respectivement les memes taches dans la version classique papier-crayon. Le temps accorde a la reflexion avant de commencer le trace, le temps de tracage comme tel et le temps de verification du trace complete sont calcules. Chez les groupes qui evaluent l'orientation d'une ligne sur support informatique, le temps requis pour y parvenir est note. Enfin, un questionnaire estime si les participants connaissent ou non le principe physique d'invariance de l'orientation de la surface d'un liquide. Les resultats revelent que cette connaissance est plus frequente chez les garcons dans l'ensemble des groupes. Dans le cas ou les sujets ont a tracer une ligne, les filles reussissent moins d'essais que les garcons s'il faut, sur support informatique, tracer la surface de l'eau dans un contenant incline ou a l'horizontale. Il en va de meme s'il faut, sur support papier, tracer une horizontale dans un contenant incline. Le trace de la surface de l'eau est plus exact chez les sujets connaissant le principe d'invariance et l

  5. Radioactive liquid effluent management - state of art and the role of membrane processes

    International Nuclear Information System (INIS)

    Panicker, S.T.; Prabhakar, S.; Misra, B.M.; Ramani, M.P.S.

    1990-01-01

    This report reviews the conventional methods involving filtration, chemical precipitation, evaporation and ion exchange, employed for the treatment of low level radioactive effluents. The role of membrane processes, particularly reverse osmosis and ultrafiltration has been assessed with a view to increase the effectiveness of the existing methods. After overviewing the practices followed in major countries, a possible scheme has been proposed. (author). 66 refs., 4 tabs., figs

  6. Nuclide separation by hydrothermal treatment and ion exchange: a highly effective method for treatment of liquid effluents - 59217

    International Nuclear Information System (INIS)

    Braehler, Georg; Rieck, Ronald; Avramenko, V.A.; Sergienko, V.I.; Antonov, E.A.

    2012-01-01

    Liquid low level radioactive effluents, when solidified in e.g. cement matrix, contribute to a significant extent to the waste amount to be disposed of in final repositories. Accordingly, since many years scientists and engineers investigate processes to remove the radioactive nuclides selectively from the effluents, to split the raw solution into two separate fractions: a large fraction with activity concentrations below the limits for free release; and a small fraction, containing the activity in concentrated form on e. g. ion exchanger materials (ion exchange has proven to be the most promising method for such 'nuclide separation'). The challenge to be taken up is: When (and this is most often the case) the effluent contains organic materials and complexing agents, the formation of e. g. the 60-Co-EDTA complex prohibits its fixation to the ion exchangers. Accordingly the complexing agent needs to be removed or destroyed. The Institute for Chemistry of the Russian Academy of Sciences has applied the method of hydrothermal treatment (at elevated temperature and pressure, 200 deg. C, 200 bar), supported by Hydrogen Peroxide oxidation, to allow virtually complete removal of radioactive nuclides on inorganic ion exchangers. Pilot plants have been operated successfully in Russian power stations, and an operational plant has been designed. The method is being extended for an interesting and promising application: spent organic ion exchange resins, loaded up to the medium activity level, represent a serious disposal problem. With the hydrothermal process, in a process cycle, the activity can be stripped from the resins, the organic content is destroyed, and the activity is fixed on an inorganic absorber, well suited for final disposal. (authors)

  7. Les effets sur la compétitivité internationale des réglementations relatives à la gestion des effluents d'élevage

    DEFF Research Database (Denmark)

    Andersen, Mikael Skou

    2003-01-01

    différences sensibles de compétitivité de la production porcine et d’une concurrence internationale croissante sur le marché de la viande de porc explique que l’on se préoccupe de la charge financière imposée par les politiques de l’environnement aux éleveurs, notamment en ce qui concerne la gestion des...

  8. Comprehensive Two-dimensional Liquid Chromatography coupled to High Resolution Time of Flight Mass Spectrometry for Chemical Characterization of Sewage Treatment Plant Effluents

    NARCIS (Netherlands)

    Ouyang, X.; Leonards, P.E.G.; Legler, J.; van der Oost, R.; de Boer, J.; Lamoree, M.H.

    2015-01-01

    For the first time a comprehensive two-dimensional liquid chromatography (LC. ×. LC) system coupled with a high resolution time-of-flight mass spectrometer (HR-ToF MS) was developed and applied for analysis of emerging toxicants in wastewater effluent. The system was optimized and validated using

  9. Evaluation of genotoxicity of liquid effluents from gas washing systems by means of bioassay Trad-MCN

    International Nuclear Information System (INIS)

    Machado, Alessandra Carla Fattori Ergesse; Alves, Edenise Segala

    2007-01-01

    In the gas washing systems the gaseous emissions from a facility are forced through an absorbing liquid preventing pollutants to be dispersed into the atmosphere. In the Centro Tecnologico da Marinha em Sao Paulo/Centro Experimental Aramar (CEA), the gas washing are used to control the emissions from the uranium enrichment facilities. Uranium. fluoride, ammonia and hydrogen fluoride are the main contaminants, all heavily toxic. Biological assays, using plants or other living organisms, have been used to assess genotoxic agents in the environment. Among the bioassays using plants, the Trad-MCN has been used extensively, as it allows the evaluation of liquid or gaseous contaminants. The species Tradescantia pallida (Rose) was exposed in a dynamic system to liquid effluents from CEA. A positive control was the exposure to formaldehyde 10% in water, known as a very toxic solution, and the negative control was the exposure to filtered air. The protocol established by Ma (1983) for hybrid clones and validated for the T. pallida by Guimaraes (2003) was used to perform the Trad-MCN assays. Only preparations containing early tetrads were scored. In that context, the present study objectifies to evaluate, by the Trad-MCN bioassay, the genotoxicity of the solution from the gas washing and, also, evaluate the efficiency of that system. The results obtained show that the T. pallida is a sensitive bioindicator for the pollutants tested and can be useful for in vitro environmental monitoring under controlled conditions. (author)

  10. Evaluation of genotoxicity of liquid effluents from gas washing systems by means of bioassay Trad-MCN

    Energy Technology Data Exchange (ETDEWEB)

    Machado, Alessandra Carla Fattori Ergesse [Centro Tecnologico da Marinha em Sao Paulo (CTMSP), SP (Brazil). Div. de Monitoracao Ambiental], E-mail: alessandra@ctmsp.mar.mil.br; Alves, Edenise Segala [Instituto de Botanica de Sao Paulo, SP (Brazil). Secao de Anatomia], E-mail: ealves@ibot.sp.gov.br

    2007-07-01

    In the gas washing systems the gaseous emissions from a facility are forced through an absorbing liquid preventing pollutants to be dispersed into the atmosphere. In the Centro Tecnologico da Marinha em Sao Paulo/Centro Experimental Aramar (CEA), the gas washing are used to control the emissions from the uranium enrichment facilities. Uranium. fluoride, ammonia and hydrogen fluoride are the main contaminants, all heavily toxic. Biological assays, using plants or other living organisms, have been used to assess genotoxic agents in the environment. Among the bioassays using plants, the Trad-MCN has been used extensively, as it allows the evaluation of liquid or gaseous contaminants. The species Tradescantia pallida (Rose) was exposed in a dynamic system to liquid effluents from CEA. A positive control was the exposure to formaldehyde 10% in water, known as a very toxic solution, and the negative control was the exposure to filtered air. The protocol established by Ma (1983) for hybrid clones and validated for the T. pallida by Guimaraes (2003) was used to perform the Trad-MCN assays. Only preparations containing early tetrads were scored. In that context, the present study objectifies to evaluate, by the Trad-MCN bioassay, the genotoxicity of the solution from the gas washing and, also, evaluate the efficiency of that system. The results obtained show that the T. pallida is a sensitive bioindicator for the pollutants tested and can be useful for in vitro environmental monitoring under controlled conditions. (author)

  11. Development of improved liquid radioactive effluents treatment technology by precipitation and ion exchange and the related analytical control system

    Energy Technology Data Exchange (ETDEWEB)

    Rahman, M M; Mollah, A S; Alam, M K; Begum, A; Islam, S; Koddus, A [Institute of Nuclear Science and Technology, Savar, Dacca (Bangladesh)

    1997-02-01

    Chemical precipitation method for treatment of LLW and ILW by co-precipitation of caesium with nickel ferrocyanide was employed. High decontamination factors were observed in the pH range of 9 to {approx} 11. The percentage removals of {sup 137}Cs from 37 kBq, 370 kB and 3.4 MBq per litre of simulated effluents were {approx} 90%, 99.7% and 99.8% respectively. Liquid radioactive wastes generated from radioisotope production facilities of AERE, Savar were found to contain {sup 134}Cs and {sup 60}Co with the average activity levels of 13.23 kBq/L and 5.3 kBq/L, respectively. Test runs for removal of {sup 134}Cs from the wastes varied from {approx} 90% to 99%. The radioactive concentrates (sludges) were conditioned by cementation and safely stored in interim storage room. (author). 4 refs, 1 fig., 9 tabs.

  12. Development of improved liquid radioactive effluents treatment technology by precipitation and ion exchange and the related analytical control system

    International Nuclear Information System (INIS)

    Rahman, M.M.; Mollah, A.S.; Alam, M.K.; Begum, A.; Islam, S.; Koddus, A.

    1997-01-01

    Chemical precipitation method for treatment of LLW and ILW by co-precipitation of caesium with nickel ferrocyanide was employed. High decontamination factors were observed in the pH range of 9 to ∼ 11. The percentage removals of 137 Cs from 37 kBq, 370 kB and 3.4 MBq per litre of simulated effluents were ∼ 90%, 99.7% and 99.8% respectively. Liquid radioactive wastes generated from radioisotope production facilities of AERE, Savar were found to contain 134 Cs and 60 Co with the average activity levels of 13.23 kBq/L and 5.3 kBq/L, respectively. Test runs for removal of 134 Cs from the wastes varied from ∼ 90% to 99%. The radioactive concentrates (sludges) were conditioned by cementation and safely stored in interim storage room. (author). 4 refs, 1 fig., 9 tabs

  13. Analysis and study on generic models for use in assessing the impact of radioactive liquid effluent to the environment

    International Nuclear Information System (INIS)

    Ma Wenlin; Cao Jianzu; Fang Dong

    2008-01-01

    The assessment of the impact of discharges of radioactive substances into surface water under normal condition of nuclear facilities is an important part of the environmental impact analysis. Generic methods for assessing the impact of radioactive liquid effluent release into surface water provided by IAEA Safety Reports Series 19 are studied in this paper, and also an example calculation that assesses the impact of radioactive surface water discharge of HTR-PM ( High Temperature Air-cooled Reactor demonstration unit) in Anhui is presented in this paper to illustrate that a simplified but conservative assessment can be used for the purpose of screening proposed radioactive discharges. If the results meet the relevant requirements specified by the relevant regulatory authority, the further calculations are not needed. If they fails to meet the requirements, the more field data are to be sampled for calculations by more sophisticated mode or otherwise. (authors)

  14. Treatment of liquid effluents from uranium analytical method 'DAVIES & GRAY' by electrodialysis and electrodialysis reactive tests

    International Nuclear Information System (INIS)

    Zuniga Alvear, Karina Andrea

    2014-01-01

    This work describes the process which produces liquid waste coming from the chemical analysis laboratory of the Chilean Nuclear Energy Commission (CCHEN), from the analytical technique called 'Davies and Gray' and their further treatment, using electro dialysis (ED) and reactive electro dialysis (RED), in order to achieve lower uranium contents in solution. The contamination in water is a big problem, since there are many places in the world where is limited. For these reasons new treatments must be done, and the ion-selective membrane has opened a new path for these processes. The radioactive liquid waste have lots of other restrictions in their final disposal, which difficult even more the water recovery, because the law has very strict security margins with respect to these ones. In the case of liquid waste containing uranium, the concern increases, because being the uranium a radioactive element has it has to be lowered at its maximum, or eliminated directly, in order to avoid any kind of contamination. There exist national regulations and international recommendations. They have stipulated the correct management and disposal for radioactive waste. These can come from any uranium production process. In any of these, the liquid waste contains certain uranium content, which after the end of the process; the discarded waste must go through a conditioning and cleaning process for its afterward liberation or recycling. In this study, it was tested the electro dialysis as a radioactive waste treatment, only uranium containing waste coming from the chemical analysis laboratory in CCHEN. The electro dialysis process has a direct competition with other separation process, such as distillation, ionic exchange, and reverse osmosis, among others. The classic electro dialysis has been developed during the 50's, and until today, there has been different version, as inverse, reactive, reversible. The unidirectional and reactive electro dialysis will be the

  15. Amélioration de la qualité microbiologique des effluents secondaires par stockage en bassins

    Directory of Open Access Journals (Sweden)

    Trad-Rais M.

    1999-01-01

    Full Text Available Microbiological quality improvement of secondary effluent by reservoir storage. Storing secondary effluents is of particular interest for water resource management. It constitutes further treatment which reduces the microbial contamination of water to a level where it can be used for the irrigation of all crops, without restriction. The storage of treated wastewater takes place during the winter, ensuring that such a resource is not lost and enabling a larger area to be irrigated during the dry season, thereby increasing agricultural production. Storage trials in reservoirs were conducted in north-eastern Tunisia. Their objective was to determine the length and conditions of secondary effluent decontamination as well as the impact of seasonal storage on water quality. The results indicate that the decontamination of effluents slows down with increased reservoir depth. For a depth of less than 150 cm, a reduction of fecal coliforms in the order of 3 log units is attained in 3 days when the average temperature of the water ranges from 22 to 25 degrees C; when this temperature is between 25.5 and 28 degrees C, the same reduction takes 8 days. Below 20 degrees C, decontamination is considerably reduced: for a mean water temperature ranging from 12.5 to 18 degrees C, the reduction of fecal coliforms reaches 3 log units only after a retention time of 17 days in the reservoir. Seasonal storage from 2 to 7 months does not affect the bacteriological quality of water: after decontamination, no proliferation of bacterial indicators occurs during storage.

  16. Treatment of liquid effluents from an ammonia/urea/sulphur plant

    Energy Technology Data Exchange (ETDEWEB)

    Padula, R.C.; Amabal, S.P.

    1979-01-01

    The effluent treatment processes planned for a new 1500 ton/day urea, 1200 ton/day ammonia plant in Brazil, based on the two-stage reaction of ammonia and carbon dioxide to form urea and on the catalytic hydrogenation of nitrogen to ammonia, will include the steps of equalization, flocculation, flotation, nitrification, sedimentation, denitrification, rapid aeration, further settlement, filtration, and discharge to a river. Sludge will be chemically conditioned as needed, and will be thickened, filtered, and disposed of by land application. There will be considerable recycling of nutrients.

  17. On-line liquid-effluent monitoring of sewage at Lawrence Livermore National Laboratory

    International Nuclear Information System (INIS)

    Dreicer, M.; Cate, J.L.; Rueppel, D.W.; Huntzinger, C.J.; Gonzalez, M.A.

    1982-01-01

    An automatic on line sewage effluent monitoring system has been developed. A representative fraction of the total waste stream leaving the site is monitored for pH, radiation, and metals as it passes through a detection assembly. This assembly consists of an industrial pH probe, NaI radiation detectors, and an x-ray fluorescence metal detector. A microprocessor collects, reduces and analyzes the data to determine if the levels are acceptable by established environmental limits. Currently, if preset levels are exceeded, a sample of the suspect sewage is automatically collected for further analysis, and an alarm is sent to a station where personnel can be alerted to respond on a 24-hour basis. Since at least four hours pass before LLNL effluent reaches the treatment plant, sufficient time is available to alert emergency personnel, evaluate the situation, and if necessary arrange for diversion of the material to emergency holding basins at the treatment plant. Information on the current system is presented, and progress is reported in developing an on-line tritium monitor as an addition to the assembly

  18. Assessment of options for the treatment of Sizewell PWR liquid effluent

    International Nuclear Information System (INIS)

    Hornby, J.; Allam, J.; Knibbs, R.H.

    1992-01-01

    This report describes the origins of PWR liquid waste streams, their composition and rates of arising. Data has been collected from operational PWRs and estimates obtained for Sizewell B PWR liquid waste streams. Current liquid waste treatment practices are reviewed and assessments made of established and novel treatment techniques which could be applicable to Sizewell B. A short list of treatment options is given and recommendations are made relating to established treatment technologies suitable for Sizewell B and also to development work on more novel treatments which could lead to a reduction in waste disposal volumes. (author)

  19. Determination of trace amount of lead in industrial and municipal effluent water samples based on dispersive liquid-liquid extraction

    Energy Technology Data Exchange (ETDEWEB)

    Shirkhanloo, H. [Iranian Petroleum Industry Health Research Institute, Occupational and Environmental Health Research Center, Tehran (Iran, Islamic Republic of); Sedighi, K.; Mousavi, H. Z., E-mail: hzmousavi@semnan.ac.ir [Semnan University, College of Science, Department of Chemistry, Semnan (Iran, Islamic Republic of)

    2014-10-01

    In this study, a simple, sensitive and accurate method was developed for the determination of lead ion by combining ionic liquid dispersive liquid-liquid extraction (Il-DLL E) with flame atomic absorption spectrometry. Tetraethyl thiuram disulfide (Tetd), acetone and 1-octyl-3m ethylimidazolium hexafluorophosphate [(C{sub 8}MIM) (PF{sub 6})] were used as the chelating agent, dispersive and extraction solvent, respectively. Under the optimal conditions, the calibration graph was linear in the range of 5-190 μg L{sup -1} of lead and the detection limit was 0.8 μg L{sup -1} with a sample volume of 200 ml. The proposed method was validated by the analysis of one certified reference material and applied successfully to the determination of lead in real water samples. (Author)

  20. Determination of trace amount of lead in industrial and municipal effluent water samples based on dispersive liquid-liquid extraction

    International Nuclear Information System (INIS)

    Shirkhanloo, H.; Sedighi, K.; Mousavi, H. Z.

    2014-01-01

    In this study, a simple, sensitive and accurate method was developed for the determination of lead ion by combining ionic liquid dispersive liquid-liquid extraction (Il-DLL E) with flame atomic absorption spectrometry. Tetraethyl thiuram disulfide (Tetd), acetone and 1-octyl-3m ethylimidazolium hexafluorophosphate [(C 8 MIM) (PF 6 )] were used as the chelating agent, dispersive and extraction solvent, respectively. Under the optimal conditions, the calibration graph was linear in the range of 5-190 μg L -1 of lead and the detection limit was 0.8 μg L -1 with a sample volume of 200 ml. The proposed method was validated by the analysis of one certified reference material and applied successfully to the determination of lead in real water samples. (Author)

  1. Radioactivity measurement of the liquid effluents of two university hospital methodology, problems arising

    International Nuclear Information System (INIS)

    Basse-Cathalinat, B.; Barthe, N.; Chatti, K.; Ducassou, D.

    2005-01-01

    The authors present methodology used to measure the radioactivity of the effluents at the output of two services of Nuclear medicine located in two Hospital complexes of the Area of Bordeaux. These measures are intended to answer at the requests of circular DGS/DHOS no 2001/323 of the Ministry for Employment and Solidarity. The selected method is more powerful since it is based on the use of a whole of spectrometry to very low background noise. These devices of measurements make it possible to take into account all the isotopes coming from a service of Nuclear medicine. The authors are conscious that of such measurements cannot be considered in all the services of Nuclear medicine. Other technical articles will specify simpler methods allowing a satisfactory management of the radioactive wastes. (author)

  2. French practice and trends in the treatment and conditioning of PWR liquid effluents and solid wastes

    International Nuclear Information System (INIS)

    Celeri, J.J.; Pottier, P.; Sousselier, Y.

    1982-01-01

    From the early stages of the development of the nuclear industry in France, it has been decided to avoid radioactive effluent release by treatment, conditioning and storage of the wastes. It was not possible, when choosing this option, to reach the optimum from the beginning for the whole management system. The selection of a treatment process requires a precise knowledge of the nature, the composition and the arisings of radioactive wastes and these data are only available when commercial size reactors are in operation. To solve this problem, a close collaboration has been developed between the nuclear station operators and the R and D laboratories in charge of studying new treatment methods. This cooperation is a fruitful permanent exchange giving precise data about the waste, results of treatment operation on the industrial units, allowing modification in the installations to improve their efficiency and sometimes, resulting in new trends for the research program

  3. 40 CFR 417.162 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... AGENCY (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS SOAP AND DETERGENT MANUFACTURING POINT SOURCE CATEGORY Manufacture of Liquid Detergents Subcategory § 417.162 Effluent limitations guidelines... available (BPT): (a) For normal liquid detergent operations the following values pertain: Effluent...

  4. Estimative of dilution factor for radioactive liquid effluents employing the H-3 and Cs-137 radiotracers present as pollutant

    International Nuclear Information System (INIS)

    Nisti, Marcelo Bessa; Santos, Adir Janete Godoy dos

    2011-01-01

    It was estimated the dilution factor for liquid effluents at the discharge points of the IPEN, Sao Paulo, Brazil, employing as radiotracers the radioisotope routinely liberated for the sewage of 'Cidade Universitaria Armando de Salles Oliveira' - CUASO 3 H and 137 Cs, not generating either monetary or environmental cost associated to the estimation. The 137 Cs was determined by gamma spectrometry and the 3 H was determined liquid phase scintillation. The results showed that the dilution factor varied according to the employed radiotracer in a crescent order of 3 H and 137 Cs according to the characteristics of each element. The average of dilution factors obtained at the first and second liberation day were 4.3 and 7.4 respectively for the 3 H and 6.2 and 13.9 for the 137 Cs. The ratio of dilution factors of calculated 3 H and 137 Cs were coherent with the ratio verified at the twelve hydrometers distributed by the IPEN campus. The dilution factors were estimated in operational and laboratory study, in a single controlled discharge of the TR1 tank

  5. Sr{sup 90} determination in calcareous water; Determination du {sup 90}Sr dans des eaux chargees en calcium

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, P; Pardo, G; Wormser, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    The Straub method (ref. 2) for determination of radioactive strontium in water containing calcium is valid within very wide limits, and particularly in the case of residual water from the chemical purification treatment of the radioactive liquid effluent at the C.E.N. Saclay. (author) [French] La methode de Straub (ref. 2) de determination du strontium radioactif dans une eau chargee en calcium est valable dans des limites tres larges et en particulier dans le cas d'eaux residuaires provenant du traitement d'epuration chimique des effluents liquides radioactifs du C.E.N. de Saclay. (auteur)

  6. Applications of hydrophobic Pt catalysts in separation of tritium from liquid effluents

    International Nuclear Information System (INIS)

    Ionita, Gheorghe; Popescu, Irina; Stefanescu, Ioan; Varlam, Carmen

    2003-01-01

    Hydrophobic Pt catalysts were first prepared and used in deuterium or tritium separation while after their application was extended to chemical reactions occurring in liquid water or saturated humidity environments. Capillary condensing produced at the contact with liquid water or vapors engenders in classical hydrophilic catalysts a decrease in activity what makes them inefficient. Consequently, liquid water 'repealing' catalysts are to be used allowing, at the same time gaseous reactants and reaction products to diffuse to and fro the catalytic active centers. These catalysts were successfully applied in deuterium enrichment and tritium separation based on hydrogen- liquid water isotopic exchange at both pilot and industrial scale. High activity and a prolonged stability were demonstrated and checked in: - detritiation of the heavy water used as both moderator and coolant in CANDU type reactors; removing of tritium from light water recirculated in nuclear fuel reprocessing facilities; removal and recovery of tritium from atmosphere and tritium processing installations. Due to their incontestable advantages the use of these catalysts was recently extended to other chemical processes occurring in the presence of liquid water or in high humidity environment or else when water occurs as a reaction product, such as catalytic hydrogen - oxygen recombination at room temperature or removal of stable organic pollutants from waste waters

  7. The determination of Pu-241 by liquid scintillation counting in gaseous effluents of an incineration facility, FERAB, and the Karlsruhe Nuclear Reprocessing Plant, WAK

    International Nuclear Information System (INIS)

    Godoy, J.M.; Schuettelkopf, H.

    1983-03-01

    Although the concentration of Pu-241 in nuclear fuel to be reprocessed is high, there are only few results published about the emission of Pu-241 with gaseous and liquid effluents. Nearly no information is available, too, about the environmental contamination of nuclear installations by Pu-241. Therefore a procedure was developed to measure Pu-241 by liquid scintillation counting. Sample preparation was performed by electroplating of plutonium on stainless steel planchets. To correct the selfabsorption the linear dependence of counting efficiency in the liquid scintillation counter and the resolution in the α-spectrometer was used. (orig./HP) [de

  8. Study on radioactive release of gaseous and liquid effluents during normal operation of AP1000

    International Nuclear Information System (INIS)

    Gong Quan; Zhou Jing; Liu Yu

    2014-01-01

    The gaseous and liquid radioactive releases of pressurized water reactors plant during normal operation are an important content of environmental impact assessment and play a significant role in the design of nuclear power plant. According to the design characters of AP1OOO radioactive waste management system and the study on the calculation method and the release pathways, the calculation model of the gaseous and liquid radioactive releases during normal operation for AP1OOO are established. Base on the established calculation model and the design parameters of AP1000, the expected value of gaseous and liquid radioactive releases of AP1OOO is calculated. The results of calculation are compared with the limits in GB 6249-2011 and explain the adder that is included tu account for anticipated operational occurrences, providing a reference for environmental impact assessment of pressurized water reactor. (authors)

  9. Treatment of radioactive liquid effluents by reverse osmosis membranes: From lab-scale to pilot-scale.

    Science.gov (United States)

    Combernoux, Nicolas; Schrive, Luc; Labed, Véronique; Wyart, Yvan; Carretier, Emilie; Moulin, Philippe

    2017-10-15

    The recent use of the reverse osmosis (RO) process at the damaged Fukushima-Daiichi nuclear power plant generated a growing interest in the application of this process for decontamination purposes. This study focused on the development of a robust RO process for decontamination of two kinds of liquid effluents: a contaminated groundwater after a nuclear disaster and a contaminated seawater during a nuclear accident. The SW30 HR membrane was selected among other in this study due to higher retentions (96% for Cs and 98% for Sr) in a true groundwater. Significant fouling and scaling phenomenon, attributed to calcium and strontium precipitation, were evidenced in this work: this underscored the importance of the lab scale experiment in the process. Validation of the separation performances on trace radionuclides concentration was performed with similar retention around 96% between surrogates Cs (inactive) and 137 Cs (radioactive). The scale up to a 2.6 m 2 spiral wound membrane led to equivalent retentions (around 96% for Cs and 99% for Sr) but lower flux values: this underlined that the hydrodynamic parameters (flowrate/cross-flow velocity) should be optimized. This methodology was also applied on the reconstituted seawater effluent: retentions were slightly lower than for the groundwater and the same hydrodynamic effects were observed on the pilot scale. Then, ageing of the membrane through irradiation experiments were performed. Results showed that the membrane active layer composition influenced the membrane resistance towards γ irradiation: the SW30 HR membrane performances (retention and permeability) were better than the Osmonics SE at 1 MGy. Finally, to supplement the scale up approach, the irradiation of a spiral wound membrane revealed a limited effect on the permeability and retention. This indicated that irradiation conditions need to be controlled for a further development of the process. Copyright © 2017 Elsevier Ltd. All rights reserved.

  10. The choice of sites considered with respect to problems of radioactive waste disposal; Le choix des sites considere dans ses rapports avec les problemes de rejets d'effluents radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Duhamel, F [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The author of this article shows clearly that a knowledge of the behaviour of wastes together with an analysis of the risks of accidents makes it possible to define the general characteristics of a site as a function of, on the one hand the geological and meteorological factors, and on the other, the proposed installations. Consideration of the biological environment makes it possible to clarify the sitological study and to make a choice between the several sites possible. The author shows the real necessity for radio-protection specialists to share their knowledge, to establish regulations, and to cooperate with the authors responsible for the installations, from the moment of the choice of the site and of the planning of the apparatus up to the final reject of the waste. (author) [French] L'auteur de ce rapport montre clairement que la connaissance du comportement des effluents jointe a l'analyse des risques d'accident permettent de degager les caracteristiques generales d'un site en fonction d'une part, des donnees geologiques et meteorologiques, d'autre part des installations projetees. La consideration du milieu biologique permet de preciser l'etude sitologique et d'effectuer un choix entre plusieurs sites donnes. L'auteur met en evidence la necessite absolue pour les specialistes de la radioprotection d'echanger leurs connaissances, d'etablir des reglements et de cooperer avec les autorites responsables des installations depuis le choix des sites et le projet des appareillages jusqu'au rejet ultime des residus. (auteur)

  11. Experiment of decontamination of radioactive liquid by a biological method; Experience de decontamination de liquides radioactifs far voie biologique

    Energy Technology Data Exchange (ETDEWEB)

    Wormser, G.

    1962-07-01

    The author reports experiments of treatment of radioactive liquid effluents by percolation on a bacterial bed like the one used for the treatment of sewer wastewaters. He also reports results obtained in other countries in terms of reduction of effluent radioactivity for various radioactive ions. The installation is described and results are presented in terms of variation of contamination of an effluent with respect to its recycling on a bacterial bed [French] Dans le monde entier, on se preoccupe des moyens de decontamination pour des liquides radioactifs. Les experiences de l'auteur ont confirme qu'un lit bacterien neuf peut donner de bons resultats: il est a noter que ce procede biologique se montre selectif a l'egard des divers ions radioactifs. (auteur)

  12. Use of macrophites for removal of Co e Zn in liquid effluents

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Juliana de Almeida S.; Silva, Paulo Sergio Cardoso da Silva, E-mail: ju_aso@usp.br, E-mail: pscsilva@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

    2017-07-01

    This study proposes the application of Eichhornia crassipes roots biomass to remove cobalt and zinc ions from solution, aiming its application to effluent treatment. The efficiency of adsorption and the percent of removal were checked as a function of pH and contact time. The plants, for biomass production, were collected at the Billings reservoir in São Bernardo do Campo, located in the Southeast of São Paulo Metropolitan Region. The biomass obtained was subjected to the chemical activation process by the treatment with HCl 0.1 molL{sup -1} in order to increase its surface area. The concentrations of cobalt and zinc, present in the adsorbent, before and after the adsorption experiments were determined by the instrumental neutron activation analysis (INAA) technique. Results showed that the pH of the solution must be adjusted after the addition of the biomass. The contact time for maximum removal of both ions is between 20 and 30 min. (author)

  13. Evaluation of the development conditions for an 'on-farm' breeding effluent anaerobic digestion sector; Evaluation des conditions de developpement d'une filiere de methanisation -a la ferme- des effluents d'elevage

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    In a first part, this report presents some characteristics and key aspects of the anaerobic digestion process. It highlights its environmental benefits, notices that energy production from breeding effluents is not optimal, that this energy is easily exportable, but that this process does not process nitrogen and phosphorus surpluses. It gives an overview of the status of practices in France, in Germany where incentive policies have promoted the development of on-farm anaerobic digestion for many years, in Denmark, in Sweden and in Switzerland where the gas feeds directly the network. It presents the legal and regulatory framework for installations classified with respect to the protection of the environment, for the digestate approval and standardization, for the connection to the electric network, for bio-gas transportation and injection in networks, and for taxes. It proposes an economic analysis: investments and scale effects, cogeneration and electricity sale, perspectives for biogas direct sale, waste and digestate value, and so on. It proposes a review of research and development works in this domain, and finally addresses some issues of economic and regional development

  14. BNFL Sellafield assessment of public radiation exposure due to liquid effluents from fuel reprocessing

    International Nuclear Information System (INIS)

    Hunt, G.J.

    1982-01-01

    Individual (critical group) doses resulting from liquid discharges from the British Nuclear Fuels Limited (BNFL) Sellafield Works have been derived in a form normalised to unit radionuclide discharge rates. This has been done for the purpose of providing a basis for predicting doses in the event of nuclear fuel from a future Sizewell 'B' power station being reprocessed. These doses would have to be reviewed in the light of prevailing circumstances at the time when the actual discharges are known. (author)

  15. Movement of Radioactive Effluents in Natural Waters at Hanford; Le Mouvement des Effluents Radioactifs dans les Eaux Naturelles a Hanford; 0414 0412 0418 0416 0414 ; Movimiento de los Efluentes Radiactivos en Aguas Naturales en Hanford

    Energy Technology Data Exchange (ETDEWEB)

    Honstead, J. F.; Foster, R. F.; Bierschenk, W. H. [Hanford Laboratories Operation, Hanford Atomic Products Operation, General Electric Company, Richland, WA (United States)

    1960-07-01

    ) [French] L'installation de Hanford se trouve dans une region semi-aride-de sediments non consolides en couche tres epaisse, qui ont ete deposes par les eaux et reposent sur un lit rocheux basaltique. Ces roches forment deux couches geologiques, la couche inferieure etant beaucoup moins permeable que la couche superieure. La Columbia traverse les terrains de l'installation et ce n'est qu'a environ 55 kilometres en aval du dernier reacteur qu'on commence a utiliser les eaux pour la consommation humaine. Les effluents de faible intensite provenant des reacteurs sont evacues dans la Columbia apres un sejour d'une a trqis heuges dans des reservoirs. Dans les effluents, on a pu identifier plus de 60 radioisotopes, qui, pour la plupart, ont y une tres courte periode. On a observe l'appauvrissement de l'eau fluviale en plusieurs radioisotopes par suite de mecanismes autres que la desintegration. Cet appauvrissement atteint 40% en moyenne sur les 55 kilometres qui separent les reacteurs et Pasco; il serait du a des processus d'assimilation biologique et de sedimentation. Les solutions de dechets de faible intensite provenant des usines de traitement chimique sont evacuees dans le sol ou elles filtrent a travers les sediments sur une profondeur de 70 a 120 metres avant d'atteindre la nappe aquifere. Pendant leur passage a travers le sol, la plupart des substances radioactives sont retenues par adsorption ou par d'autres reactions. L'eau et les quelques contaminants qui atteignent le niveau hydrostatique se deplacent avec les eaux souterraines en direction de la Columbia. La vitesse et la direction de ce deplacement sont determines par la forme de la surface piezometrique et les caracteristiques hydrauliques de l'aquifere. La configuration locale de la nappe a ete fortement influencee par l'evacuation de grandes quantites d'eau. Compte tenu du gradient hydraulique et du degre de permeabilite des aquiferes, on estime a 180 annees la duree moyenne du deplacement de J'eau. On reconnait

  16. Treated Effluent Disposal Facility

    Data.gov (United States)

    Federal Laboratory Consortium — Treated non-hazardous and non-radioactive liquid wastes are collected and then disposed of through the systems at the Treated Effluent Disposal Facility (TEDF). More...

  17. Fragilisation par le zinc liquide des aciers haute résistance pour l'automobile Liquid zinc embrittlement of high strength automotive steels

    Directory of Open Access Journals (Sweden)

    Frappier Renaud

    2013-11-01

    Full Text Available Cette étude présente les investigations menées sur la fragilisation par le zinc liquide d'un acier électro-zingué. La caractérisation mécanique par essais de traction à haute température montre un important puits de ductilité entre environ 700 ∘C et environ 950 ∘C. L'observation au MEB des éprouvettes de traction indique que, dans la gamme de température observée pour laquelle il y a fragilisation, on a mouillage intergranulaire des joints de grains de l'acier à l'interface acier/revêtement par des films de Zn. La corrélation entre mouillage intergranulaire thermiquement activé d'une part, et propagation de fissure lors du chargement d'autre part, est discutée. This study deals with liquid zinc embrittlement for electro-galvanized steel. Mechanical characterization by high temperature tensile tests shows a drastic loss of ductility between 700 ∘C and 950 ∘C. SEM investigations show that steel grain boundaries under the steel/coating interface are penetrated by a liquid Zn channel, only in the temperature range of embrittlement. A correlation can be drawn between i thermal activated-grain boundary wetting and ii crack propagation in presence of external stress.

  18. Regulating Effluents From India’s Textile Sector: New Commands and Compliance Monitoring for Zero Liquid Discharge

    Directory of Open Access Journals (Sweden)

    Jenny Grönwall

    2017-06-01

    Full Text Available In 2016 large parts of India had experienced failing monsoons for two consecutive years. Textiles production was a natural target in the quest for solutions when re-distribution of water between sectors became imperative, and it seemed likely that the zero liquid discharge (ZLD approach would be mainstreamed nationwide. However, when amended standards for discharge of effluents were enacted it was without strict requirements for reuse of water in-house; the legislator chose to make ZLD applicable only to large units and refrained from making it mandatory. The carrying capacity of the environment in sensitive or otherwise critical areas may henceforth be taken into account by the executive, but the textile sector’s wastewater is not yet regarded the resource that a circular economy calls for. This paper examines the command-side of regulation by shedding light on the applicable law, the reform steps taken in 2014–16 and how judicial interventions influenced these. It also seeks to contribute to the understanding of enforcement control by discussing what role court-established committees are playing in implementation and monitoring of compliance, based on an in-depth case study of Tirupur, India’s ‘knit city’.

  19. Determination and behaviour of plutonium emitted with liquid effluents and exhaust air into the environment of the Nuclear Research Centre Karlsruhe

    International Nuclear Information System (INIS)

    Schuettelkopf, H.; Pimpl, M.

    1986-01-01

    The plutonium concentrations in the surroundings of the Karlsruhe Nuclear Research Centre (KfK) are in the range of variation of the global plutonium contamination caused by fallout of atmospheric nuclear tests. Exclusively in the sediments of the Old River Rhine, which serves as main canal for the liquid effluents, higher plutonium concentrations could be detected. The dose exposure of the population living in the environment of the KfK caused by the measured plutonium concentrations is negligible low. From the Karlsruhe Reprocessing Plant (WAK) and the facilities needed to decontaminate radioactive wastes 0.48 GBq (13 mCi) plutonium alpha activity has been emitted within 11 years of operation until 1982 - 1/3 with the liquid effluents and 2/3 with the exhaust air. Following the pathway with the exhaust air, plutonium concentrations in the environment of the Karlsruhe Reprocessing Plant were measured in groundlevel air, in soil, in plants, in food and in animal tissues. Radioecological parameters like dispersion factors, deposition velocities, migration velocities in soil and transfer soil-to-plant were investigated. Following the pathway with the liquid effluents, plutonium concentrations were measured in surface waters, sediments, water plants, plankton and animals. Dilution and sedimentation behaviour were studied as well as the transfer water-to-plant and water-to-animals. (orig.) [de

  20. Liquid effluent/Hanford Environmental compliance FY 1995 Multi-Year Program Plan/Fiscal Year Work Plan, WBS 1.2.2.1 and 1.2.2.2

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    This document details the program effort to eliminate the use of the soil column for liquid effluent treatment and to manage current and future liquid effluent streams at the Hanford Site, in a safe responsible cost effective and legally compliant mannger. This should be achieved through planning, public and stakeholder interaction, definition of requiremtns for generators, and provision of timely treatment, stroage, disposal capability, and waste minimization of waste streams.

  1. Liquid effluent/Hanford Environmental compliance FY 1995 Multi-Year Program Plan/Fiscal Year Work Plan, WBS 1.2.2.1 and 1.2.2.2

    International Nuclear Information System (INIS)

    1994-09-01

    This document details the program effort to eliminate the use of the soil column for liquid effluent treatment and to manage current and future liquid effluent streams at the Hanford Site, in a safe responsible cost effective and legally compliant mannger. This should be achieved through planning, public and stakeholder interaction, definition of requiremtns for generators, and provision of timely treatment, stroage, disposal capability, and waste minimization of waste streams

  2. 239Np application as tracer of 237Np in liquid effluents and nuclear wastes

    International Nuclear Information System (INIS)

    Diodati, Jorge M; Sartori, F.M.

    2003-01-01

    In this paper a technique to separate and measure 237 Np using 239 Np as a tracer, is presented. After the radiochemical separation, a liquid scintillation measurement with pulse decay discrimination and a γ measurement on the same vial is performed. The method also allows an electrodeposition for an α and γ measurement. The chemical recoveries obtained by LSC and γ spectrometry in vial are similar to those obtained by α and γ spectrometry on electroplated disc. The MDA is 0.08 Bq/l by α spectrometry and 0.22 Bq/l by LSC, with 2 σconfidence interval, and 93.7 % measurement efficiency and 98.0% chemical recovery. (author)

  3. Public exposure due to radioactive liquid effluent discharges from Instituto de Pesquisas Energeticas Nucleares/IPEN

    International Nuclear Information System (INIS)

    Rocca, Fatima F.D.

    1995-01-01

    The physical and social-economic characterization of aquatic environment influenced by IPEN was performed and possible exposure pathways were identified. The effective dose equivalent to the critical groups were estimated by using a mathematic model that simulate radionuclide transport through environment components, and dosimetric models that relate activity at environment components to public exposure. This study has concluded that there is not a single critical group that receives the highest dose equivalents from the source, but all the populational groups potentially exposed receive doses at the same level, and then all of them must be considered in a radiological assessment process. The results showed that the public exposure due to liquid discharges from IPEN remains bellow established dose limits. (author). 58 refs., 28 figs., 24 tabs

  4. Revue des aspects hydrodynamiques des réacteurs catalytiques gaz-liquide-solide à lit fixe arrosé Hydrodynamics of Gas-Liquid-Solid Trickle-Bed Reactors: a Critical Review

    Directory of Open Access Journals (Sweden)

    Attou A.

    2006-12-01

    Full Text Available Bien que les aspects hydrodynamiques soient d'une importance primordiale lors de la conception et du fonctionnement d'un réacteur gaz-liquide-solide à lit fixe arrosé, les méthodes de calcul prédictif proposées sont restées fort rudimentaires. La plupart des études portant sur ce sujet ont été menées dans des conditions quasi atmosphériques alors que les réacteurs industriels fonctionnent à des pressions élevées. C'est seulement récemment que quelques résultats expérimentaux ont été obtenus à des hautes pressions, et des corrélations ont été proposées dans ces conditions pour prédire la transition entre les régimes ruisselant et pulsé, la perte de pression et le taux de rétention de liquide. L'objectif de cet article est double. D'une part, une synthèse y est présentée ; elle fait état des connaissances acquises sur les divers aspects hydrodynamiques du réacteur triphasique à lit fixe, incluant les récents développements réalisés à hautes pressions. D'autre part, les modèles et les corrélations actuels de transitions de régimes, de la perte de pression et du taux de rétention de liquide sont soumis à une analyse critique en confrontant leurs prédictions à l'ensemble des données expérimentales obtenues pour un large intervalle de la pression de fonctionnement du réacteur. Des conclusions objectives ont pu être tirées concernant les aptitudes des corrélations et des modèles actuels à être utilisées pour les calculs de conception des réacteurs triphasiques à lit fixe industriels. Malheureusement, il apparaît qu'aucun modèle de transitions entre les régimes ruisselant et pulsé n'est satisfaisant. Seule la corrélation empirique de Larachi et al. (1993 s'avère être jusqu'à présent la méthode la plus précise pour prédire la position de la frontière entre les régimes ruisselant et pulsé dans un large domaine de la pression de fonctionnement. Par ailleurs, aucune corr

  5. Application of functionalized calixarenes to the processing of radioactive effluents by supported liquid membranes

    International Nuclear Information System (INIS)

    Hill, Clement

    1994-01-01

    In a first part, this research thesis presents the general context of nuclear waste processing (nature of wastes to be processed, characteristics of the used method and products), and proposes an overview of results obtained during previous campaigns which were based on the use of the technique of supported liquid membranes, but with other types of extracting components. The second part focuses on the tracking of complexing and extractive properties of all functionalized calixarenes which had been synthesised by different research teams. Several experiments have been performed to determine the extraction efficiency and selectivity of these organic compounds with respect to the studied radio-elements. The third part reports the detailed study of a specific family of functionalized calixarenes for which two thermodynamic models of membrane transport described in the literature have been applied. Validity limits are discussed with respect to operation conditions. Some results are finally given on the caesium and actinide (neptunium, plutonium) decontamination of synthetic concentrates which simulate actual radioactive wastes [fr

  6. Methodological studies for deriving release criteria for liquid effluents from medical installations

    International Nuclear Information System (INIS)

    Shu, Jane; Comissao Nacional de Energia Nuclear; Rochedo, Elaine R.R.; Heilbron Filho, Paulo F.L.; Crispim, Verginia R.

    2009-01-01

    This work aims to develop a methodology for the assessment of clearance limits for the release of liquid waste arising from medical installations using radionuclides for medical diagnostic purposes in the town of Rio de Janeiro. The results will be used to assess the need to justify or to revise the current clearance values as specified in regulation CNEN-NE-6.05 - Radioactive Waste Management in Radioactive Facilities. The proposed methodology is based on the mathematical model recommended by the International Atomic Energy Agency, adapted to the observed release conditions in the study area. In order to turn the assessment as realistic as possible, two scenarios are simulated. The first scenario simulates the release to the sewage system with access to a sewer treatment stations. The second scenario simulates the releases without passing a treatment station, with direct outflow to surface water. Probabilistic assessments were performed using the Crystal Ball software. Distributions were than compared to current IAEA clearance criteria that include specific values for average and low probability scenarios. The results will be used to derive adequate clearance levels for radionuclides used in nuclear diagnostic medicine in Brazil according to the specific relevant release scenario. (author)

  7. Biotic survey of Los Alamos radioactive liquid-effluent receiving areas

    International Nuclear Information System (INIS)

    Miera, F.R. Jr.; Bostick, K.V.; Hakonson, T.E.; Nyhan, J.W.

    A preliminary study was completed of the vegetation and small mammal communities and associated climatology in three canyon liquid waste receiving areas at the Los Alamos Scientific Laboratory. Data were gathered on plant and animal composition, distribution, and biomass, along with air temperature, humidity, and precipitation, as a function of elevation and where data were available with season. Initial studies of the understory vegetation in the spring of 1974 indicate grass species to be dominant at higher elevations, with forb species becoming dominant at lower elevations. Generally, the highest total mass estimates for standing green vegetation were obtained in the study sites located in the upper portions of the canyons where precipitation is greatest, and where the terrain and intermittent stream flow result in a wetter habitat. Fourteen species of small mammals were trapped or observed in canyon study areas during two trapping sessions of May--June 1974 and December 1974--February 1975. A greater number of species and the highest rodent biomass estimates in the spring were generally associated with the ponderosa pine/pinion--juniper woodland in the upper reaches of the canyons, and were lowest in the pinion--juniper woodland at the lower portions of the canyons. This trend was observed in only one of the canyons during the winter season. Climatological data gathered in the three canyons since 1973 are also presented to serve as a data base for future reference

  8. 40 CFR 417.83 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS SOAP AND DETERGENT MANUFACTURING POINT SOURCE CATEGORY Manufacture of Liquid Soaps Subcategory § 417.83 Effluent limitations guidelines representing the degree of...

  9. 40 CFR 417.82 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... AGENCY (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS SOAP AND DETERGENT MANUFACTURING POINT SOURCE CATEGORY Manufacture of Liquid Soaps Subcategory § 417.82 Effluent limitations guidelines representing the...

  10. Design of a treatment pilot by electro-coagulation and electro-flotation of high charged liquid effluents; Conception d'un pilote de traitement par electrocoagulation-electroflottation d'effluents liquides fortement charges

    Energy Technology Data Exchange (ETDEWEB)

    Cames, M.C.; Leclerc, J.P.; Valentin, G.; Sanchez-Calvo, L.; Lapicque, F. [Centre National de la Recherche Scientifique (CNRS-ENSIC), Lab. des Sciences du Genie Chimique, 54 - Nancy (France); Rostan, A.; Muller, P. [Centre de Recherche pour l' Environnement, l' Energie et le Dechet, Vivendi Environnement, 78 - Limay (France)

    2001-07-01

    The possibilities of the electro-coagulation and electro-flotation process has been studied on many industrial effluents by cells. The results show that the process efficiency is conditioned by the effluent nature and the dissolved aluminium quantity, what ever the initial rate of Carbon Organic Total (COT). Other parameters as the current density and the circulation speed are not significant. (A.L.B.)

  11. Control system of liquid effluents generated in treatment with I-131; Sistema de control de efluentes liquidos generados en el tratamiento con I-131

    Energy Technology Data Exchange (ETDEWEB)

    Garcia M, T.; Ruiz C, M. A.; Angeles C, A.; Ramirez S, R., E-mail: teodoro.garcia@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2015-09-15

    In recent years, nuclear medicine has developed greatly in our country and around the world. Techniques for both medical diagnosis and therapy have increased the use of radiopharmaceuticals, notably the I-131. In Mexico there are around 150 nuclear medicine establishments authorized by the Comision Nacional de Seguridad Nuclear y Salvaguardias. Most of these establishments do not have an appropriate facility for the treatment of radioactive liquid effluents, to ensure compliance with the concentration limits established in the regulations. The Instituto Nacional de Investigaciones Nucleares (ININ) developed and implemented successfully, a control system of radioactive effluents (named SACEL) from a nuclear medicine facility. This system ensures an effective compliance with regulations and also better management and control of these radioactive effluents. Calculations and design of SACEL were made with respect to I-131, because is one of the most commonly used in radiotherapy and medical diagnostics, besides its half-life is greater in relation to other radionuclides. SACEL is comprised of four storage tanks and decay and a fifth tank for measuring the concentration of I-131 and later discharge to the drain; these tanks are connected to an automated system that controls the effluents passage. The calculation to determine the volume of the tanks was carried out according to the demand that has the hospital, to the maximum activity being poured in effluents and time required to decay. In this paper the design and installation of SACEL system, in addition to functioning as a facility that enables the Hospital meet the required standards is presented. Dose calculations performed with MCNPX and the methodology used in the calibration of the detection system is also presented. (Author)

  12. Detection of high energy gamma radiations with liquid rare gases as scintillators; Detection des rayonnements Gamma de grande energie avec les gaz rares liquides comme scintillateurs

    Energy Technology Data Exchange (ETDEWEB)

    Ho, Phan Xuan

    1965-11-25

    This research thesis reports the study of a sensor based on a liquid scintillator for the detection of high energy (10 to 30 MeV) gamma radiations. The scintillator is a liquefied argon or xenon rare gas. The author first studies the process of energy transfer from the particle to the sensing medium. He addresses the different involved elements and phenomena: electromagnetic radiations (Compton Effect, photoelectric effect, pair production, and total gamma absorption), charged particles (braking radiation, collisions) and application to gamma spectrometry. He describes and discusses the scintillation mechanisms (scintillation of organic and inorganic materials), the general characteristics of scintillators (impurities, converters), and then reports the practical realisation of the sensor. Results are presented and discussed [French] Dans ce travail, nous nous proposons d'etudier une technique. Il s'agit d'un detecteur a scintillateur liquide pour la detection des rayonnements gamma energiques (10 a 30 MeV). Le scintillateur utilise est un gaz rare liquefie argon ou xenon. Nous examinerons d'abord les processus de transfert de l'energie de la particule au milieu detecteur puis les mecanismes de scintillation en general pour pouvoir exploiter au mieux les phenomenes favorables. Nous presenterons ensuite la realisation pratique du detecteur. Ses qualites (et defauts) trouveront leur place dans la fin de ce memoire. Bien qu'a l'heure actuelle, par la methode de Kyropoulos, on puisse faire pousser des gros cristaux d'iodure de sodium, l'utilisation des 'gaz rares' liquefies comme scintillateurs est, grace a la brievete de la scintillation, tres utile lorsqu'on recherche un fort taux de comptage (jusqu'a 10 impulsions par seconde) ou lorsqu'on veut resoudre certains problemes de coincidence. Les cristaux NaI(Tl) de grandes dimensions sont d'un montage facile mais leur manipulation requiert beaucoup de precautions du fait qu'ils supportent tres mal les chocs thermiques

  13. Combination of biological treatment of waste air and liquid effluents in small and medium-sized businesses by using spherical carrier media in exchange with each other. Final report; Kombination der biologischen Behandlung von Abluft- und Abwasserreinigung in kleinen und mittleren Unternehmen durch die Verwendung von kugeligen Traegermaterialien im gegenseitigen Austausch. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Kunz, P.M.; Brunk, M.; Bentz, P.; Bach, K.; Marcos del Rio, O.; Stahl, B.; Wolf, C.

    2002-05-08

    A combined system for biological treatment of solvent-contaminated liquid and gaseous effluents was to be constructed. The system was to be mobile for demonstration purposes in industrial processes and was to serve for dimensioning of full-scale systems. The system works by a combined process via exchange of spherical carriers with a growth of micro-organisms. Two pilot systems of the Institut fuer Biologische Verfahrenstechnik, one for liquid and one for gaseous effluents, were combined for this purpose, ensuring exchange of carrier materials between the two units. (orig.) [German] Aufgabe im Rahmen dieses F+E-Vorhabens war es gewesen, eine kombinierte biologische Abluft- und Abwasserreinigungsanlage - speziell fuer loesungsmittelhaltige Abluft und Abwaesser - zu untersuchen. Dazu sollte eine Anlage aufgebaut werden, die auch als Demonstrations- und Versuchsanlage zu Industriebetrieben gebracht und dort zur Dimensionierung von full-scale-Anlage eingesetzt werden kann. Idee fuer dieses Vorhaben war gewesen, die Kombination beider Behandlungssysteme ueber den Austausch von mit Mikroorganismen bewachsenem Traegermaterial herzustellen. Am Institut fuer Biologische Verfahrenstechnik existierte bereits eine Pilotanlage fuer die biologische Abwasserreinigung mit kugeligem Traegermaterial (Vario-Bio-Reaktor) und eine Pilotanlage fuer die biologische Behandlung von Abluft nach dem Trickling-Filter-Prinzip mit ebenfalls kugeligem Traegermaterial. Diese beiden Anlagen sollten miteinander kombiniert und der Austausch des Traegermaterials hergestellt werden. (orig.)

  14. Dynamic containment of gaseous effluents in the auxiliary buildings and reinjection of liquid effluents from these buildings back into the reactor building for 900 MWe PWRs under accident condition

    International Nuclear Information System (INIS)

    Demoulin, F.; Collinet, J.; Nguyen, C.

    1987-04-01

    Examination of the lessons to be learned from the accident of the Three Mile Island nuclear power plant on 20 March 1979 led the French Safety Authorities and EDF (Electricite de France) to adopt a series of measures intended to improve the performance of the containment of French PWRs, especially in the event of accident. Among the measures adopted, two of them contribute to the upgrading of the containment of nuclear island buildings, by reducing radioactivity constraints inside these buildings and by limiting radioactive releases into the environment. These are: (1) dynamic containment of auxiliary buildings likely to be contaminated following an accident, (2) reinjection back into the reactor building of liquid effluents arising in the auxiliary buildings. In this paper we shall discuss, for each measure, the approach to the problem and describe the arrangements made to arrive at a satisfactory solution [fr

  15. Electrolytic treatment of liquid effluents: decontamination by electro coagulation of release water of a petroleum platform; Traitement electrolytique des effluents liquides: decontamination par electrocoagulation des eaux de rejet d'une plate forme petroliere

    Energy Technology Data Exchange (ETDEWEB)

    Nanseu-Njiki, Ch.P.; Ngameni, E.; Poumiba, S. [Yaounde Univ., Laboratoire de Chimie Analytique, Dept. de Chimie Inorganique, Faculte des Sciences (Cameroon); Darchen, A. [Ecole Nationale Superieure de Chimie de Rennes, Laboratoire d' Electrochimie, 35 - Rennes (France)

    2005-07-01

    The water releases of petroleum platforms present lots of pollutants; Usually, these waters are reinjected in ground water when it is possible. In the other cases they are released at the surface and need then a treatment. The electro-coagulation is a suitable method often used. The authors propose to study the optimum conditions of decontamination by this method, by a parametric evaluation (water flow, charge density, ph). Experiments used iron and aluminium electrodes. (A.L.B.)

  16. Effect of the tide on the diffusion of 3H in the liquid effluent discharged from Daya Bay Nuclear Power Station

    International Nuclear Information System (INIS)

    Zhang Jie; Zhang Chunlin; Pan Meng

    2006-01-01

    The tide field at the time of liquid effluent discharging from Daya Bay nuclear power station, and the average water speed at the monitoring points in west Daya Bay from the time of discharging to the time of sampling were calculated by ADI (Alternating Direction Implicit) method. By comparing analysis, the difference of 3 H diffusion between spring tide and neap tide (the expansion of 3 H within one day of spring tide is greater than that within one day of neap tide) was found. So, an equivalent diffusion time is introduced to modify the original model, and a better attenuation relation between the average 3 He concentration in west Daya Bay and the time since the liquid 3 H discharging is obtained. (authors)

  17. 102 La décoloration des rejets liquides de textile (noir de soufre) par ...

    African Journals Online (AJOL)

    pc

    Résumé. Dans cette étude, nous nous intéressons au traitement d'un rejet de coloration de textile par voie ... L'industrie textile utilise environs 10 000 types de colorants, la ..... Electrochemical coagulation for textile effluent decolorization.

  18. Decision no 2009-DC-0157 of the 15. of September 2009 by the Nuclear Safety Authority specifying the limits of releases in the environment of liquid and gaseous effluents of the base nuclear installation n. 29 operated by the CIS Bio International on the district of Saclay (Essonne department)

    International Nuclear Information System (INIS)

    2009-01-01

    This document contains references to the different legal and official documents (codes, orders, minister's opinion, public surveys, administrative authorizations, local community opinion) at the root of this specification of limits related to releases in the environment of liquid and gaseous effluents of a base nuclear installation. Tables present the limits for radioactive liquid effluents (iodine, rare earths, and other beta and gamma emitters) and the maximum admitted concentrations for gaseous chemical effluents (SO 2 , H 2 S, VOCs)

  19. Filtration device for active effluents

    International Nuclear Information System (INIS)

    Guerin, M.; Meunier, G.

    1994-01-01

    Among the various techniques relating to solid/liquid separations, filtration is currently utilized for treating radioactive effluents. After testing different equipments on various simulated effluents, the Valduc Center has decided to substitute a monoplate filter for a rotative diatomite precoated filter

  20. Clean technologies: methods for minimizing the releases and choice of the effluents valorization processes. Application to metal workshops; Technologies propres: methodes de minimisation des rejets et de choix des procedes de valorisation des effluents. Application aux ateliers de traitement de surface

    Energy Technology Data Exchange (ETDEWEB)

    Laforest, V.

    1999-12-10

    Currently, the essential part of the money invested by the industrialist is for the water treatment. In France, most of the 20 billions francs per year devoted to the water treatment is used for the industrial activity. The global management of effluents favour the integration of clean technologies (optimization, change and modification of the production process) in order to reduce the pollution problem at its source. Our study aims at the introduction of clean technologies in the metal workshops (consumer and generator of water and chemicals) by the development of two data management methods, which lead to two decision support systems. The aim of the first one is to minimize both the water consumption and the wastewater disposal by optimizing the production process (optimum yield and efficiency of the rinsing baths). The second one concerns the choice of valorization techniques considering the valorization objectives, the effluents characteristics and the parameters limiting the use of the techniques. Our approach fits into a global management method for the metal finishing industry wastewater. Its aim is to limit the quantity of wastewater generated, to valorize effluents and by this way to develop the clean technologies.

  1. Underground disposal of tanks containing liquid and inflammable hydrocarbons; Mise sous talus ou sous terre des reservoirs contenant des hydrocarbures liquides inflammables

    Energy Technology Data Exchange (ETDEWEB)

    Kukuczka, P.; Giovannini, B.; Caumont, M.; Varin, F

    2001-09-15

    The protection from thermal and mechanical stresses, of hazardous products tanks, by earth covering, is often used since many years in France and in many countries of Europe. In the case of hydrocarbons tanks, only small capacity tanks are covering. The aim of this report is to evaluate the feasibility of this technique for big capacity tanks as refinery tanks. It details the different typologies of tanks containing inflammable liquids and the associated systems, examines if the covering technique presents some special difficulties and precises the specifications needed for the new tanks being covering. (A.L.B.)

  2. Characterization of an acidification and equalization tank (AET operating as a primary treatment of swine liquid effluent

    Directory of Open Access Journals (Sweden)

    Fabrício Motteran

    2013-06-01

    Full Text Available This work evaluated the potential of the acidification equalization tank (AET used as a primary treatment unit, treating the hog farming wastewater. The treatment system consisted of a degritter with a triangular-notch weir, for measuring the flow, a static sieve, and an acidification and equalization tank (AET, an anaerobic baffled reactor (ABR, an upflow anaerobic sludge blanket (UASB reactor, a settling tank, a greenhouse for fertirrigation and two infiltration ponds. The AET had a net capacity of 8,000 liters, internally covered with asphalt blanket, worked based on surface loading rates application. The unit operated continuously, with its flow varying from 0.1 to 10 L s-1. To determine the efficiency, the following parameters were measured: pH; COD; BOD; volatile and fixed solids; settleable solids; total, intermediate and partial alkalinity and total acidity. The COD removal varied from 5 to 20%. The average pH was 7.3 and the total, intermediate and partial alkalinity in the effluent, were 1919, 846, 1197 mg L-1, respectively. The total acidity in the effluent was 34 mg L-1. The influent and effluent total BOD and oil & grease concentrations were 3436 and 3443 mg L-1, and 415 and 668 mg L-1, respectively. It was found that the AET worked properly concerning the acidification, equalization and sedimentation processes, confirming low cost of implementation and easy operation, when compared to other traditional decanters.

  3. Evaluation of the dispersion of oil refinery liquid effluent; Avaliacao da dispersao de efluente liquido de refinaria de petroleo

    Energy Technology Data Exchange (ETDEWEB)

    Mariano, Adriano Pinto; Silva, Ariovaldo Jose da; Oliveira, Valdenilson Jose Alves de; Angelis, Dejanira de Franceschi de [Universidade Estadual Paulista (UNESP), Rio Claro, SP (Brazil). Dept. de Bioquimica e Microbiologia. Inst. de Biociencias], e-mail: adrianomariano@yahoo.com.br

    2010-07-15

    In this paper, two techniques to evaluate the dispersion of the effluent of an oil refinery are presented. Thus, the dispersion plume was characterized by field measurements of electrical conductivity and by computational simulation (Cormix simulator). An oil refinery whose effluent is discharged on the Atibaia river (Paulinia/SP) is taken as study case. The behavior of the effluent was evaluated until 1000 m after the discharge. The results show that the measurement of electrical conductivity is a suitable technique to evaluate the dispersion of oil refinery wastewaters, since they have high conductivity and for this reason there is a strong contrast between the values of the wastewater and the ambient background. Furthermore, other water quality parameters had a dispersion behavior similar to that shown by the conductivity. The dispersion plume generated by the computational simulator showed high concordance with the field data. In this manner, computational simulation can be a useful tool to evaluate the dispersion of discharges considering hypothetical scenarios, as well as to design the discharge channel. (author)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2003-09-01

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

  5. Electromagnetic control of mass transfer at liquid/liquid interfaces; Controle electromagnetique des transferts de masse aux interfaces liquide/liquide

    Energy Technology Data Exchange (ETDEWEB)

    Saadi, B

    2006-04-15

    Most metallurgical processes, such as steel refining or nuclear waste processing; the interfaces between two liquid phases are the regions of mass transfer. These transfers require the implementation of a means of stirring to accelerate the kinetics of the pollutants transfer between both phases. This thesis deals with the use of the electromagnetic forces to stir, without any material contact, the bath core and the interface in order to control or even increase the kinetic transfers. To achieve this, two complementary experimental installations were used. The first experiment allows the measurement of the Indium transfer, initially dissolved in mercury towards a covering electrolyte layer and the velocity field in mercury. The performed experiments, determine the topology of the fields flows speeds in the mercury bath, moreover the behaviour of the transfer kinetics versus the intensity of the magnetic field are established. This evolution is correlated with the dynamic behaviour of the mercury surface. The second installation allows the characterization of an element transfer (Pb, Zr or Ce) initially contained in a fluorinated salt towards an antimony matrix containing lithium. It appears that all transfers kinetics are very fast. The proposed experimental set-up is particularly efficient for Cerium transfer (limited by the interface) but does not present any action for Zirconium transfer. (author)

  6. Study of the mineral absorbent precipitation phenomena used in decontamination of radioactive effluents; Etude des phenomenes de precipitation d'adsorbants mineraux utilises en decontamination d'effluents radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Pacary, V. [Institut National Polytechnique, 54 - Nancy (France)]|[CEA Valrho, Lab. des Procedes Avances de Decontamination (LPAD), 30 - Marcoule (France)

    2006-07-01

    The aim of this work is to determine the optimal conditions of the reactor running (feed rate, reagents concentration..) for which the effluent decontamination is the most efficient. Thus will be in particular studied the coprecipitation mechanisms and the influence of the physico-chemical conditions on these mechanisms. On the other hand, the processes occurred in the coprecipitation phenomenon being complex, the elaboration of a model is indispensable to guide and interpret the experimental work. This model will be based on the knowledge developed in precipitation and will allow to simulate the decontamination in two reactors types: the reactor fed in continuous in reagents and in effluents as the Hague's ones and the closed reactor fed only in reagents as the Marcoule's ones. (O.M.)

  7. Some magnetic resonance properties of solutions of sodium in liquid ammonia; Contribution a l'etude des solutions de sodium dans l'ammoniac liquide par resonance magnetique

    Energy Technology Data Exchange (ETDEWEB)

    Lambert, C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1968-02-01

    Dilute solutions of sodium in liquid ammonia are studied by the mean of dynamic polarization techniques, and with the aid of Becker Lindquist and Alder model. Paramagnetic shifts are computed as a function of the 'average spin density', for each of the nuclear spin system. The nuclear contributions to the Overhauser shift are computed in the same way. A theoretical study of the main relaxation processes is carried out for each of the nuclear spin system and for the electronic spin system. The dynamic polarization experiments consist in classical measurement of the Overhauser enhancement for nitrogen, and in direct measurements of nitrogen Knight shift and nuclear contributions to the Overhauser shift by the mean of double irradiation techniques. The results show that, in dilute solutions, the relaxation of nitrogen arises from quadrupole interaction and from hyperfine interaction with unpaired electrons. Both interactions are of the same order of magnitude. Overhauser shift measurements show that the spin density is negative at the proton site, in agreement with Hughes results. (author) [French] Les solutions diluees de sodium dans l'ammoniac sont etudiees au moyen des techniques de la polarisation dynamique, sur la base du modele de Becker Lindquist et Aider. Les deplacements paramagnetiques des raies de resonance nucleaire des differents noyaux sont analyses en faisant appel a la notion de ''densite moyenne de spin'' introduite par l'auteur; et les differentes contributions nucleaires au deplacement d'Overhauser sont calculees en fonction de cette meme grandeur. Une etude theorique de la relaxation de chaque systeme de spin permet d'evaluer l'importance relative des differents mecanismes mis en jeu. Les experiences de polarisation dynamique effectuees au cours de ce travail consistent en mesures classiques de l'effet Overhauser sur l'azote, d'une part, et en la mise en oeuvre de techniques originales pour mesurer le deplacement de Knight de l'azote et les

  8. A green deep eutectic solvent dispersive liquid-liquid micro-extraction (DES-DLLME) for the UHPLC-PDA determination of oxyprenylated phenylpropanoids in olive, soy, peanuts, corn, and sunflower oil.

    Science.gov (United States)

    Ferrone, Vincenzo; Genovese, Salvatore; Carlucci, Maura; Tiecco, Matteo; Germani, Raimondo; Preziuso, Francesca; Epifano, Francesco; Carlucci, Giuseppe; Taddeo, Vito Alessandro

    2018-04-15

    A green dispersive liquid-liquid microextraction (DLLME) using deep eutectic solvent (DES) as the extracting solvent has been developed and applied for the simultaneous quantification of ferulic acid, umbelliferone, boropinic acid, 7-isopentenyloxycoumarin, 4'-geranyloxyferulic acid (GOFA), and auraptene in some vegetable oils using ultra high performance liquid chromatography (UHPLC) with photodiode array detection (PDA). All parameters in the extraction step, including selection and loading of both extracting and dispersing solvents, amount of both extractant and disperser solvent were investigated and optimized. PhAA/TMG DES achieved higher recovery and enrichment factor compared to other DESs. The validated method showed good linearity with correlation coefficients, r 2 >0.9990 for all the analytes. Furthermore, this is the first time that eco-friendly solvents are used for the extraction of oxyprenylated phenylpropanoids and the corresponding extract analyzed with ultra high performance liquid chromatography with photodiode array detection. Copyright © 2017 Elsevier Ltd. All rights reserved.

  9. Order of 24 July 1992 on the licensing of liquid radioactive effluent releases from the large nuclear installation called Atalante at the nuclear research centre in the Rhone valley on the Marcoule nuclear site

    International Nuclear Information System (INIS)

    1992-01-01

    This Order fixes the annual authorized limits and procedures for the transfer from Atalante to the Cogema establishment also at Marcoule of the low-level liquid effluents for treatment. It also specifies the measures for their control and surveillance. (NEA)

  10. Order of the 10 january 2003 authorizing the national agency for the radioactive wastes management to follow the gaseous and liquid effluents release for the exploitation of the radioactive wastes storage center of the Manche

    International Nuclear Information System (INIS)

    2003-01-01

    This document, took out from the Official Journal, is the law text relative to the order of the 10 january 2003 authorizing the national agency for the radioactive wastes management to follow the gaseous and liquid effluents release for the exploitation of the radioactive wastes storage center of the Manche. (A.L.B.)

  11. Industrial solid and liquid waste treatment processes; Les procedes de traitement des dechets industriels solides et liquides

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1995-11-01

    This catalogue gives information on 68 chemical, mechanical, magnetic, electrical, thermal, etc. techniques for the processing of solid, viscous and liquid, common or special, industrial wastes. The various processes are presented as files, which are easily retrievable through keywords, waste type or industry codes, processing types, distributors. Technologies, performances and applications of each techniques are presented, together with references and company contacts

  12. On-line immunoaffinity column-liquid chromatography-tandem mass spectrometry method for trace analysis of diuron in wastewater treatment plant effluent sample.

    Science.gov (United States)

    Zhang, Xiuli; Martens, Dieter; Krämer, Petra M; Kettrup, Antonius A; Liang, Xinmiao

    2006-11-10

    An on-line immunoaffinity column with liquid chromatography/tandem mass spectrometry (IAC-LC-MS/MS) method for the determination of diuron in water matrices was described. This method used a sol-gel immunoaffinity column (20 mm x 4 mm I.D.) for on-line sample cleanup and enrichment, a monolithic analytical column (100 mm x 4.6 mm I.D.) for separation, and a triple quadrupole mass spectrometer for quantitation. The major challenges for the on-line set-up were discussed. The optimized on-line protocol was emphasized by the fact that low limit of quantitation (LOQ) of 1.0 ng/L was achieved with only 2.5-mL sample. In addition, a satisfactory accuracy ( approximately 90% of recovery) and precision (effect, the on-line IAC-LC-MS/MS analysis method can reliably determine diuron in wastewater treatment plant effluent sample.

  13. Cryo magnetic separation adaptation to environment technologies: application to industrial effluents; Adaptation de la separation cryomagnetique aux technologies de l`environnement: application a l`epuration d`effluents liquides industriels

    Energy Technology Data Exchange (ETDEWEB)

    Bureau, V

    1993-12-20

    Cryomagnetic separation adaptation to environment technologies application to industrial liquid effluents. The performance, obtained by superconducting high filed - high gradient magnetic separation, permitted to foresee the magnetic treatment of heavy metals in rinse waters, derived from the surface finishing industry. The paramagnetic ions, precipitated in basic media as hydroxides, present a very hydrated amorphous structure, which masks their subjacent magnetic properties. Coprecipitation of a `magnetic carrier`, jointly with the heavy metals, has been studied: ferric chloride forms in basic media, an hydrated iron oxide. Its structure is of the goethite type, and it stabilizes as hematite. The magnetic susceptibility of the obtained product is still weak and its crystalline structure is not enough affirmative to utilize magnetic filtration with efficiency. Mixture of ferrous sulphate and ferric chloride forms, in a basic media, an hydrated magnetite. Initial ideal ratio between divalent iron and trivalent iron, varies between 0,5 and 1,2. This mixture, coprecipitated with the heavy metals, permits to optimize the magnetic cleaning of the fluids in a high field - high gradient filter. (author)

  14. Modélisation des jets diphasiques liquide vapeur et du "Rain-Out"

    OpenAIRE

    Touil , Abdellah

    2005-01-01

    This work aims at modelling flashing liquid jets. It deals particularly with velocity and diameter of droplets formed near the orifice (orifice diameters between a few millimetres and a few decimetres). The model not only calculates changes of temperature, fluid concentration, size and velocity of droplets, but also « rain-out » fraction (liquid which falls down on the ground). This work contributes to developoing tools for estimating safety distances. An experimental program allowed measurin...

  15. Séparations par changement de phase. Etude et représentation des équilibres liquide-vapeur Separation by Phase Hange. Study and Computing Liquid-Vapor Equilibria

    Directory of Open Access Journals (Sweden)

    Asselineau L.

    2006-11-01

    Full Text Available Pour concevoir et optimiser les principales opérations de séparation (particulièrement les distillations avec ou sans solvant et l'extraction liquide-liquide on doit disposer de méthodes de corrélation ou, mieux, de prédiction des équilibres entre phases. A basse pression, et pour les mélanges d'hydrocarbures, les résultats présentés permettent la prévision des coefficients d'équilibre, même pour les séparations les plus délicates. En présence de constituants polaires, les données expérimentales d'équilibre liquide-liquide et liquide-vapeur de mélanges binaires et ternaires peuvent être simultanément corrélées dans le but de simuler et d'optimiser les distillations azéotropiques ou extractives. Sous haute pression, et particulièrement aux abords immédiats du point critique, le choix d'une équation d'état conduit à un traitement unitaire des phases en présence et permet, en particulier, la prédiction du lieu des points critiques des mélanges d'hydrocarbures et la corrélation de ce lieu en présence de solvants polaires. To determine and optimize the main separation operations (in particular distillations with or without a solvent, and liquid-liquid extraction correlation methods must be available or, better yet, methods of predicting phase equilibria. At low pressure and for hydrocarbon mixtures, the results described make the prediction of equilibrium coefficients possible, even for the most delicate separation. In the presence of polar constituents, the experimental data for the liquid-liquid and liquid-vapor equilibrium of binary and ternary mixtures can be simultaneously correlaten so as to simulate and optimize azeotropic or extractive distillations. Under high pressure and especially in the immediate vicinityof the critical point, the choice of an equation of state leads ta a unit treatment of the phases present and, in particular, makes it possible to predict the location of critical points in hydrocarbon

  16. The treatment of effluents

    International Nuclear Information System (INIS)

    Wormser, G.; Rodier, J.; Robien, E. de; Fernandez, N.

    1964-01-01

    For several years the French Atomic Energy Commission has been studying with interest problems presented by radio-active effluents. Since high activities have not yet received a definite solution we will deal only, in this paper, with the achievements and research concerning low and medium activity effluents. In the field of the achievements, we may mention the various effluent treatment stations which have been built in France; a brief list will be given together with an outline of their main new features. Thus in particular the latest treatment stations put into operation (Grenoble, Fontenay-aux-Roses, Cadarache) will be presented. From all these recent achievements three subjects will be dealt with in more detail. 1 - The workshop for treating with bitumen the sludge obtained after concentration of radionuclides. 2 - The workshop for treating radioactive solid waste by incineration. 3 - A unit for concentrating radio-active liquid effluents by evaporation. In the field of research, several topics have been undertaken, a list will be given. In most cases the research concerns the concentration of radionuclides with a view to a practical and low cost storage, a concentration involving an efficient decontamination of the aqueous liquids in the best possible economic conditions. For improving the treatments leading to the concentration of nuclides, our research has naturally been concerned with perfecting the treatments used in France: coprecipitation and evaporation. In our work we have taken into account in particular two conditions laid down in the French Centres. 1 - A very strict sorting out of the effluents at their source in order to limit in each category the volume of liquid to be dealt with. 2 - The necessity for a very complete decontamination due to the high population density in our country. In the last past we present two original methods for treating liquid effluents. 1 - The use of ion-exchange resins for liquids containing relatively many salts. The

  17. The processing and management of wastes from atomic reactors; Nouvelles installations industrielles du C.E.A. pour le traitement des dechets radioactifs liquides et solides

    Energy Technology Data Exchange (ETDEWEB)

    Cerre, P; Mestre, E; Bourdrez, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-01

    The policy concerning radioactive wastes studied by all Atomic Centres has led to various procedures which, while apparently numerous, come under a few standard headings. Whether the wastes are in the liquid or solid state their management depends on their physical and chemical nature. The procedure adopted is governed by three general principles: - determination of the most economical means possible of storage and processing by volume reduction; - conversion to a solid compact form; - complete acceptance of the accepted standards at all places and all times. In this communication all the standard solutions adopted and used by the various Centres of the Commissariat a l'Energie Atomique will be examined bearing in mind the preceding remarks. Particular mention will be made of the following: - For liquids, physical, chemical and physico-chemical processing - For solids, decontamination, volume reduction and long-term conditioning techniques. The different procedures for collecting and storing solid wastes before and after processing are also discussed. The paper ends with a brief review of the studies, both technical and economic, being pursued on this subject. (authors) [French] La gestion des dechets etudies par tous les Centres Atomiques a donne lieu a des solutions qui - bien que nombreuses en apparence - se ramenent a quelques solutions types, peu nombreuses. Qu'il s'agisse de dechets solides ou liquides, la nature physique et chimique des dechets conditionne leur mode de gestion. Celle-ci procede de trois principes generaux: - recherche du mode de stockage et de traitement aussi economique que possible par reduction de volume; - mise sous forme compacte solide; - garantie du respect des normes en tous lieux et en tous temps. Dans cette communication, nous examinons toutes les solutions types, compte tenu des remarques precedentes, qui ont ete adoptees et sont utilisees par les differents Centres du Commissariat a l'Energie Atomique. Nous rappelons en

  18. Separation by liquid-liquid extraction of actinides(III) from lanthanides(III) using new molecules: the picolinamides; Separation par extraction liquide-liquide des actinides(III) des lanthanides(III) par de nouvelles molecules: les picolinamides

    Energy Technology Data Exchange (ETDEWEB)

    Cordier, P Y [CEA Marcoule, Departement de Recherche en Retraitement et en Vitrification, 30 - Bagnols-sur-Ceze (France); [Clermont-Ferrand-2 Univ., 63 - Aubiere (France)

    1996-07-01

    In the field of long-lived radionuclides separation from waste generated during spent fuel reprocessing, the picolinamides have been chosen as potential extractants for the selective extraction of actinides (III) from lanthanides (III). The first studies initiated on the most simple molecule of the picolinamide family, namely 2-pyridinecarboxamide, pointed out that in an aqueous media the complexation stability constant between this ligand and Am(III) is roughly 10 times higher than the ones corresponding to Ln(III). The synthesis of lipophilic derivatives of 2-pyridinecarboxamide leaded to extraction experiments. The extraction of metallic cation by lipophilic picolinamides, according to a solvatation mechanism, is strongly dependent on the nature of the amide function: a primary amide function (group I) leads to a good extraction; on the contrary, there is a decrease for secondary (group II) and tertiary (group III) amide functions. From a theoretical point of view, this work leads finally to the following conclusions: confirmation of the importance of the presence of soft donor atoms within the extractants (nitrogen in our case) for An(III)/Ln(III). Also, sensitivity of this soft donor atom regarding the protonation reaction; prevalence in our case of the affinity of the extractant for the metallic cation over the lipophilia of the extractant to ensure good distribution coefficients. The extraction and Am(III)/Ln(III) separation performances of the picolinamides from pertechnetic media leads to the design of a possible flowsheet for the reprocessing of high level liquid waste, with the new idea of an integrated technetium reflux. (author) 105 refs.

  19. Some analytical methods used by the Marcoule Centre for the control of radioactive effluents; Quelques methodes analytiques, utilisees sur le centre de Marcoule pour le controle radioactif des effluents

    Energy Technology Data Exchange (ETDEWEB)

    Scheidhauer, J.; Messainguiral, L.; Drogue, N.; Meiranesio, A. M.

    1962-07-09

    After three years of operation, the authors propose a review of the various methods used to determine the radioactivity of wastewaters released by the Marcoule Centre Laboratory. They describe the three main steps of this control: firstly, measurements of the global alpha radioactivity and beta radioactivity (principle and measurement method), secondly, dosing of strontium 89 and strontium 90 (principle, used reactants, operation mode for nitric compound precipitation, ferric decontamination, separation of barium 140, oxalic precipitation, precipitate counting, exploitation of counting results), and thirdly, the possible dosing of other fission products present in the effluents: cerium 144, plutonium (by two different methods), natural uranium, caesium 137, zirconium 95, niobium 95, ruthenium 103 and 106, iodine 131. The principle, reactants, operational mode with different precipitations, measurement devices are indicated for each of these radio-elements.

  20. Restoration of liquid effluent from oil palm agroindustry in Malaysia using UV/TiO2 and UV/ZnO photocatalytic systems: A comparative study.

    Science.gov (United States)

    Ng, Kim Hoong; Khan, Maksudur R; Ng, Yun Hau; Hossain, Sk Safdar; Cheng, Chin Kui

    2017-07-01

    In this study, we have employed a photocatalytic method to restore the liquid effluent from a palm oil mill in Malaysia. Specifically, the performance of both TiO 2 and ZnO was compared for the photocatalytic polishing of palm oil mill effluent (POME). The ZnO photocatalyst has irregular shape, bigger in particle size but smaller BET specific surface area (9.71 m 2 /g) compared to the spherical TiO 2 photocatalysts (11.34 m 2 /g). Both scavenging study and post-reaction FTIR analysis suggest that the degradation of organic pollutant in the TiO 2 system has occurred in the bulk solution. In contrast, it is necessary for organic pollutant to adsorb onto the surface of ZnO photocatalyst, before the degradation took place. In addition, the reactivity of both photocatalysts differed in terms of mechanisms, photocatalyst loading and also the density of photocatalysts. From the stability test, TiO 2 was found to offer higher stability, as no significant deterioration in activity was observed after three consecutive cycles. On the other hand, ZnO lost around 30% of its activity after the 1st-cycle of photoreaction. The pH studies showed that acidic environment did not improve the photocatalytic degradation of the POME, whilst in the basic environment, the reaction media became cloudy. In addition, longevity study also showed that the TiO 2 was a better photocatalyst compared to the ZnO (74.12%), with more than 80.0% organic removal after 22 h of UV irradiation. Copyright © 2017 Elsevier Ltd. All rights reserved.

  1. Comprehensive determination of macrolide antibiotics, their synthesis intermediates and transformation products in wastewater effluents and ambient waters by liquid chromatography-tandem mass spectrometry.

    Science.gov (United States)

    Senta, Ivan; Krizman-Matasic, Ivona; Terzic, Senka; Ahel, Marijan

    2017-08-04

    Macrolide antibiotics are a prominent group of emerging contaminants frequently found in wastewater effluents and wastewater-impacted aquatic environments. In this work, a novel analytical method for simultaneous determination of parent macrolide antibiotics (azithromycin, erythromycin, clarithromycin and roxithromycin), along with their synthesis intermediates, byproducts, metabolites and transformation products in wastewater and surface water was developed and validated. Samples were enriched using solid-phase extraction on Oasis HLB cartridges and analyzed by reversed-phase liquid chromatography coupled to electrospray ionization tandem mass spectrometry. The target macrolide compounds were separated on an ACE C18 PFP column and detected using multiple reaction monitoring in positive ionization polarity. The optimized method, which included an additional extract clean-up on strong anion-exchange cartridges (SAX), resulted in high recoveries and accuracies, low matrix effects and improved chromatographic separation of the target compounds, even in highly complex matrices, such as raw wastewater. The developed method was applied to the analysis of macrolide compounds in wastewater and river water samples from Croatia. In addition to parent antibiotics, several previously unreported macrolide transformation products and/or synthesis intermediates were detected in municipal wastewater, some of them reaching μg/L levels. Moreover, extremely high concentrations of macrolides up to mg/L level were found in pharmaceutical industry effluents, indicating possible importance of this source to the total loads into ambient waters. The results revealed a significant contribution of synthesis intermediates and transformation products to the overall mass balance of macrolides in the aquatic environment. Copyright © 2017. Published by Elsevier B.V.

  2. Performance of cellulose acetate membrane with different additives for palm oil mill effluent (POME) liquid waste treatment

    Science.gov (United States)

    Aprilia, N. A. S.; Fauzi; Azmi, N.; Najwan, N.; Amin, A.

    2018-03-01

    Performance of cellulose acetate membrane for treatment of POME liquid has studied with different additives. Cellulose acetate membranes were prepared with different additive ie formamide and polyethylene glycol and used acetone as solvent. The function of formamide and polyethylene glycol (PEG) is to increase the porosity of the membrane surface. Performance of the membrane were included SEM, FT-IR and coefficient permeability. Membrane performance has been performed for percent rejection of total suspended solid (TSS) and turbidity of POME liquid waste. Cellulose acetate with formamide shows an increased percentage of rejection in removing TSS and turbidity than cellulose acetate with PEG.

  3. Study of the extraction and the purification of americium and trivalent actinides contained in effluents with supported liquid membranes

    International Nuclear Information System (INIS)

    Guillou, P.

    1990-12-01

    The supported liquid membrane technique is studied and developed for americium recovery from uranium or plutonium matrices and decontamination of liquid radioactive wastes. First tests on uranium-nickel solutions with a flat membrane showed the easiness of the operation and the efficiency of the process. Acid-resistant (10 N), interchangeable elements with hollow fibers, are developed and also a computerized automatic device. The different tests on americium solutions demonstrate the feasibility and the reliability of the system. Influence of various parameters on transfer kinetics is investigated

  4. Plant and soil modifications by continuous surface effluent application

    Energy Technology Data Exchange (ETDEWEB)

    Tedesco, M.J.; Levien, R. [Rio Grande do Sul Univ., Porto Alegre, RS (Brazil). Dept. of Solos; Mohrdieck, F.G.; Rodrigues, N.R. [CORSAN-SITEL, Triunfo, RS (Brazil). Polo Petroquimico do Sul. Dept. de Operacao e Manutencao; Flores, A.I.P.

    1993-12-31

    In order to study the effects on soil and plants of the liquid effluent generated by a the Integrated Liquid Effluent Treatment System of a large Brazilian petrochemical complex, a field study was conducted in four areas which received the effluent and compared to control sites. This work presents some results of this study. 12 refs., 1 fig., 3 tabs.

  5. Plant and soil modifications by continuous surface effluent application

    Energy Technology Data Exchange (ETDEWEB)

    Tedesco, M J; Levien, R [Rio Grande do Sul Univ., Porto Alegre, RS (Brazil). Dept. of Solos; Mohrdieck, F G; Rodrigues, N R [CORSAN-SITEL, Triunfo, RS (Brazil). Polo Petroquimico do Sul. Dept. de Operacao e Manutencao; Flores, A I.P.

    1994-12-31

    In order to study the effects on soil and plants of the liquid effluent generated by a the Integrated Liquid Effluent Treatment System of a large Brazilian petrochemical complex, a field study was conducted in four areas which received the effluent and compared to control sites. This work presents some results of this study. 12 refs., 1 fig., 3 tabs.

  6. Automatic filling of liquid nitrogen traps auxiliary safety devices of a pumping unit; Alimentation automatique des pieges a azote liquide securites annexes d'un groupe de pompage

    Energy Technology Data Exchange (ETDEWEB)

    Chatel, S [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1969-07-01

    The liquid nitrogen traps in our laboratories are generally filled at fixed time intervals, the supply being cut when the liquid flowing through the overflow pipe acts on a lever to which is fixed a small cup fitted with a hole which allows the water of condensation to escape. This system is reliable. After a certain time however, the escape hole blocks up, water accumulates and the lever arm no longer works properly. Furthermore the duration of any cuts in the current, is added to the fixed time intervals, and in this case there can be a lack of liquid nitrogen for several hours after the current has been restored. The device described here avoids these problems. A stainless steel tube containing a copper wire passes into the trap and is immersed in the nitrogen which boils at its tip. A mercury manometer with concentric reservoirs, or an oil manometer, acting on two micro switches through a floater, records the pressure corresponding to the difference in level and controls the filling operation. If there is a lack of nitrogen, a valve can be closed by means of a falling weight, or a diffusion pump can be cut off; one time switch and at least two relays are required. One single relay can be used to control, the supply of several similar traps placed in series. [French] Dans nos laboratoires, les pieges a azote liquide sont generalement remplis a intervalles fixes jusqu'a ce que le trop-plein d'azote actionne une bascule dont le recipient presente un petit trou par ou s'en va l'eau de condensation. Ce systeme est sur. A la longue, pourtant, le trou d'ecoulement se bouche, l'eau s'accumule et la bascule cesse de fonctionner. De plus, la duree des pannes de courant s'ajoute aux 'intervalles fixes' de sorte que l'azote peut manquer plusieurs heures apres le retour du courant. Le dispositif suivant evite ces ennuis. Un tube d'acier inoxydable contenant un fil de cuivre penetre dans le piege et plonge dans l'azote qui bout a son extremite. Un manometre a mercure a cuves

  7. Study of thermodynamic properties of binary and ternary liquid alloys of aluminium with the elements iron, cobalt, nickel and oxygen; Etude des proprietes thermodynamiques des alliages liquides binaires et ternaires de l'aluminium avec les elements fer, cobalt, nickel et l'oxygene

    Energy Technology Data Exchange (ETDEWEB)

    Vachet, F [CEA Vallee du Rhone, 26-Pierrelatte (France)

    1966-07-01

    The present work deals with the thermodynamic study of aluminium liquid alloys with the metals iron, cobalt and nickel. The experiments carried out lead to the activity, at 1600 deg C, of aluminium in the (Al, Fe), (Al, Co), (Al, Ni) liquid alloys. The experimental method used consists in studying the partition of aluminium between the liquid immiscible phases made up with the pairs of metals (Fe, Ag), (Co, Ag), (Ni, Ag). The informations so obtained are used for drawing the isothermal equilibrium phases diagrams sections of (Al, Fe, Ag), (Al, Co, Ag), (Al, Ni, Ag) systems. The study of the partition of silver between lead and aluminium joined with the determinations of several authors allows us to determine the aluminium activity, analytically presented, in the metal M (iron cobalt and nickel). The Wagner's interaction parameters of aluminium in metal M are determined. The results obtained as the equilibrium phases diagrams of (Al, M) systems allow to compare the thermodynamic properties of the Al Fe system in liquid and solid states and to estimate the enthalpies of melting of the AlCo and AlNi intermetallic compounds. The activity, at 1600 deg C, of aluminium in (Al, Fe, Co), (Al, Fe, Ni), (Al, Co, Ni) liquid alloys is estimated through thermodynamic properties of binary components systems by application of several methods leading to results in good agreement. The study of aluminium-oxygen interactions in the liquid metallic solvants M allows us to propose an explanation for the shape of the deoxidation equilibrium line of iron, cobalt and nickel by aluminium and to compare the de-oxidizing power of aluminium toward iron, cobalt and nickel oxides. (author) [French] Le travail presente se rapporte a l'etude thermodynamique des alliages liquides de l'aluminium avec les metaux fer, cobalt et nickel. Les experiences effectuees ont pour but de determiner l'activite, a 1600 C, de l'aluminium dans les alliages liquides (Al, Fe), (Al, Co), (Al, Ni). La methode

  8. Mechanism of calcium phosphates precipitation in liquid crystals; Mecanisme de precipitation de phosphates de calcium dans des cristaux liquides

    Energy Technology Data Exchange (ETDEWEB)

    Prelot, B.; Zemb, T

    2004-04-01

    The possibility of using as a precursor an easily wet meso-porous powder would be a breakthrough in the preparation of nuclear waste storage ceramics. A concentrated solution containing ions to be stored would wet a dry powder and then, subjected to mild compression, lead to a micro-crystalline matrix of calcium phosphate at acceptable temperatures. Since no porous calcium phosphate different from calcined bone (patented) is described as porous precursor, we have compared the different synthesis routes towards meso-porous ceramics. First, we considered homogeneous precipitation of slats in water: using initially off-stoichiometry in reaction, micron-sized hydroxyapatite particles are produced with a specific surface up to 100 m{sup 2}/g. Then, we consider the classical route of precipitation of an hybrid material in the miscibility gap of a phase diagram, when an hexagonal liquid crystal is used a matrix for precipitation. The surfactant family consists in single chain surfactants containing phosphates as head-group to poison the growing surface of calcium phosphate nano-domains. Since the reaction is still too brutal, we considered using a cat-anionic precursor material of controllable surface charge. For certain concentrations and molar ratios, a new structure not yet described in surfactant precipitation literature is observed: since the periodicity is lower than twice the chain length, a disordered constant curvature monolayer (instead of the classical cylinder of twice chain length diameter) of surfactant is implied. Finally, we have investigated synthesis routes implying slow dissolution of pre-formed calcium phosphate in an already existing hexagonal matrix. For all these routes of synthesis, micro-structural determinations using SAXS, WARS and BET are performed, with a special attention to comparison of the precipitation material, the matrix obtained with all elements present, and also the material obtained after calcinations. (authors)

  9. Reduction of the barium concentration presents in liquid effluents by mean of non-dispersive extraction in hollow fiber modules

    International Nuclear Information System (INIS)

    Duperle Yaruro, Gladys; Pena, Dario Yesid; Escalante Hernandez, Humberto

    2008-01-01

    This work has been focused on the study of the viability of barium removal, present in a waste liquid phase, by means of non-dispersive extraction (NDE) in hollow fiber modules. An organic solution based on DEPHA (Bis-2-ethylhexyl phosphate) 30% (v/v), isopropilic alcohol 30% (v/v) and kerosene is used as selective extraction medium. For the extraction process was made a contactor with five hollow microporous propilenic fibers. A solution contained 100 ppm of BaCl 2 H 2 O, level concentration very equal as generated on the petroleum industrial wastes, is used as liquid phase. a efficiency of 95,25% is obtained when the NDE take place at pH = 9, and them 9 hours of process

  10. Effluent Guidelines

    Science.gov (United States)

    Effluent guidelines are national standards for wastewater discharges to surface waters and municipal sewage treatment plants. We issue the regulations for industrial categories based on the performance of treatment and control technologies.

  11. Health physics challenges during decontamination for safe disposal of low level liquid effluent tank as inactive scrap

    International Nuclear Information System (INIS)

    Akila, R.; Sultan, Bajeer; Sarangapani, R.; Jose, M.T.

    2018-01-01

    The Low-level Liquid waste (LLW) generated during the regeneration of mixed bed column of KAMINI reactor is collected in the SS Delay Tanks located on the western side of RML building. It was proposed to dismantle and dispose the tank as solid waste. The tank weighs about 2 ton. An attempt was made to decontaminate the tank to levels below the exempt quantity so as to qualify it as scrap of unrestricted release. This is first time in IGCAR wherein a material used in a radioactive facility for storing LLW is being released as scrap of unrestricted release and this paper discusses about the same

  12. Impact assessment for the aquatic biota arising from discharges of radioactive liquid effluents into the marine environment - Angra dos Reis nuclear power plants

    International Nuclear Information System (INIS)

    Lauria, D.C.; Peres, S.S.; Martins, S.F.

    2011-01-01

    The Piraquara de Fora Bay receives the liquid effluents from the two Brazilian nuclear power plants (NPPs): Angra I that has been operating since 1985 and Angra II that started operating in 2000. The monitoring data set obtained by IRD/CNEN for marine samples over a period of 25 years (from 1985 to 2010) were statistically evaluated. Despite the high presence of non detect observations, suitable statistical tests were applied to compare 60 Co levels in sediments between two periods of time and from different sampling locations. The natural dose and the dose derived from the NPPs routine radioactive releases on the marine biota were assessed by the Erica tool. The highest value of dose rate due to the naturally occurrence radionuclides was estimated to be around 0.6 μGy h -1 for phytoplankton, mainly due to internal dose contribution of 238 U, while fishes received the highest dose (value around 0.4 μGy h -1 ) due to the radionuclide discharges of the NPPs. Accordingly, the dose rates to the studied species (fish, crustacean, macroalgae, zooplankton and phytoplankton) were clearly below the Erica screening level of 10 μGy h -1 , indicating no significant radiological impact of NPPs on these species. (author)

  13. Automated system for the safe management of the radioactive wastes and liquid effluents in a Radiopharmaceutical an labelled compounds production center

    International Nuclear Information System (INIS)

    Amador B, Z.H.; Guerra V, R.

    2006-01-01

    The Center of Isotopes of the Republic of Cuba is a radioactive installation of first category that executes the administration of their radioactive waste under authorization of the National Regulatory Authority. The principles of the design and operation of the 'SADR' system for the safe administration of the radioactive waste and liquid effluents are presented. The Visual Basic 6 platform for the programming of the SADR is used and through of their schematic representation, the control flows and of data of the 7 modules that conform it are shown. For each module the functions are described and it presents an image of the corresponding interface. With the SADR its can be carried out the one registration and the upgrade of the inventory of radioactive waste, the planning of those disqualification operations, the annual consolidation of the volumes of waste generated and disqualified, the evaluation of specific and general indicators and the one tendencies analysis. The handling of the system through the intranet allows the enter of data from the operations place with the radioactive wastes. The results of the operation of the SADR show the utility of this work to elevate the efficiency of the administration of the radioactive wastes. (Author)

  14. Suivi des métaux et métalloïdes dans les effluents de centres de stockage de déchets : Spéciation et devenir des composés de l'arsenic et de l'étain dans les lixiviats et les biogaz

    OpenAIRE

    Pinel-Raffaitin , Pauline

    2006-01-01

    Landfilling is still nowadays the most used way of municipal solid waste (MSW) management with incineration. MSW landfills remain « black boxes » in which physical, chemical and biological phenomena interact simultaneously. Two effluents are produced during the waste degradation: leachates and biogases. Even if there are limited contact between effluents and the surrounding ecosystem, effluent monitoring is required to improve their treatments and to prevent sanitary and environmental risks. ...

  15. Supercritical water oxidation test bed effluent treatment study

    International Nuclear Information System (INIS)

    Barnes, C.M.

    1994-04-01

    This report presents effluent treatment options for a 50 h Supercritical Water Test Unit. Effluent compositions are calculated for eight simulated waste streams, using different assumed cases. Variations in effluent composition with different reactor designs and operating schemes are discussed. Requirements for final effluent compositions are briefly reviewed. A comparison is made of two general schemes. The first is one in which the effluent is cooled and effluent treatment is primarily done in the liquid phase. In the second scheme, most treatment is performed with the effluent in the gas phase. Several unit operations are also discussed, including neutralization, mercury removal, and evaporation

  16. Automated system of control of radioactive liquid effluents of patients submitted to therapy in hospitals of nuclear medicine (SACEL); Sistema automatizado de control de efluentes liquidos radiactivos de pacientes sometidos a terapia en hospitales de medicina nuclear (SACEL)

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz C, M A; Rivero G, T; Celis del Angel, L; Sainz M, E; Molina, G [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2006-07-01

    Different hospitals of nuclear medicine require of the technical attendance for the design, construction and instrumentation of an effluents retention system coming from the room dedicated to the medical application of iodine 131, with the one object of giving execution to the normative requirements of radiological protection, settled down in the General Regulation of Radiological Safety (RGSR) emitted by the CNSNS in November, 1988 and in the corresponding official standards. An automatic system of flow measurement, the activity concentration of the effluents to the drainage, the discharges control and the automated report it will allow the execution of the national regulations, also the elimination of unhealthy activities as the taking of samples, analysis of those same and the corresponding paperwork, its will allow that the SACEL is capable of to carry out registrations that are to consult in an automated way. The changes in the demands of the National Commission of Nuclear Safety and Safeguards in relation to the liberation of radioactive material in hospitals by medical treatments, it has created the necessity to develop a system that quantifies and dose the liquid effluents of people under thyroid treatment with iodine-131 to the drainage. The Automated System of Control of radioactive liquids effluents generated in Hospitals of Nuclear Medicine (SACEL) developed in the National Institute of Nuclear Research, it fulfills this regulation, besides improving the work conditions for the medical and technical personnel of the hospital in that are installed, since this system has the advantage of to be totally automated and to require of a minimum of attendance. The SACEL is an electro-hydraulic system of effluents control, based in the alternate operation of two decay deposits of the activity of the material contaminated with iodine-131. The system allows to take a registration of those volumes and liberated dose, besides being able to be monitoring in remote

  17. The radiation exposure of the UK population from liquid effluents discharged from civil nuclear installations in the UK in 1978

    International Nuclear Information System (INIS)

    Camplin, W.C.; Clark, M.J.; Delow, C.E.

    1982-04-01

    The collective effective dose equivalent commitment to the UK population from routine liquid discharges by civil nuclear establishments during 1978 has been estimated at 134 man Sv. The major pathway considered in the assessment was the consumption of seafoods, because most discharges were made directly to sea. Over 90% of this collective dose commitment will be delivered within a few years of the discharges, and caesium-137 from the nuclear fuel reprocessing facility at Windscale (now known as Sellafield) will have made the main contribution to this commitment. These discharges were primarily due to corrosion of nuclear fuel during storage at the reprocessing plant, and there is no simple relationship between the level of collective dose commitment and the amount of energy generated by nuclear means during 1978. (author)

  18. Study of optimal transformation of liquid effluents resulting from the destruction of radioactive sodium by water into ultimate solid wastes

    International Nuclear Information System (INIS)

    Rodriguez, G.; Camaro, S.; Fiquet, O.; Bernard, A.; Le Bescop, P.

    1997-01-01

    In the framework of sodium waste processing, it has been proposed to retain only processes that treat the sodium using water, thus generating the same by-products: hydrogen and sodium hydroxide. As the objective is to minimise radioactive liquid releases and as, moreover, the authorizations with respect to sodium salt releases are highly restrictive, several solutions have been envisaged for transforming the active sodium hydroxide coming from sodium destruction processes into ultimate solid wastes that can be stored on the surface in a storage site approved by the ANDRA (National Radioactive Waste Management Agency): the Aube Storage Site (CSA). Two processes have been considered and compared: immobilisation in concrete (cementation) and immobilisation in ceramic (ceramisation). These two processes are evaluated according to several criteria: the state of advancement of the process, the quantity of sodium hydroxide (and therefore of sodium) that can be treated per package. (author)

  19. Effluent standards

    Energy Technology Data Exchange (ETDEWEB)

    Geisler, G C [Pennsylvania State University (United States)

    1974-07-01

    At the conference there was a considerable interest in research reactor standards and effluent standards in particular. On the program, this is demonstrated by the panel discussion on effluents, the paper on argon 41 measured by Sims, and the summary paper by Ringle, et al. on the activities of ANS research reactor standards committee (ANS-15). As a result, a meeting was organized to discuss the proposed ANS standard on research reactor effluents (15.9). This was held on Tuesday evening, was attended by members of the ANS-15 committee who were present at the conference, participants in the panel discussion on the subject, and others interested. Out of this meeting came a number of excellent suggestions for changes which will increase the utility of the standard, and a strong recommendation that the effluent standard (15.9) be combined with the effluent monitoring standard. It is expected that these suggestions and recommendations will be incorporated and a revised draft issued for comment early this summer. (author)

  20. USERDA effluent data collection and reporting program

    International Nuclear Information System (INIS)

    Elle, D.R.; Schoen, A.A.

    1978-01-01

    Effluent and environmental monitoring has been conducted at United States Energy Research and Development Administration (formerly United States Atomic Energy Commission) facilities and sites virtually since the inception of atomic energy research and development. In 1971, computer systems were developed that permitted storage of information and data characterizing each effluent and onsite discharge point and relevant information on sources, effluent treatment and control systems, and discharge data, and serve as ERDA's computer-based management information systems for compiling waste discharge control and monitoring data on radioactivity released as airborne or liquid effluents or liquid discharges to onsite retention basins at ERDA facilities. The information systems and associated data outputs have proved to be an effective internal management tool for identifying effluent control problem areas and for surveying an agencywide Radioactive Effluent Reduction Program. The trend data facilitate the detection of gradual changes in the effectiveness of waste treatment systems, and errors or oversights in monitoring and data handling. Other computer outputs are useful for identifying effluent release points that have significantly higher or lower concentrations or quantities in the discharge stream than were measured the previous year. The year-to-year trend reports and the extensive computer edit and error checks have improved the reliability of the reported effluent data. Adoption of a uniform, centralized reporting system has improved the understanding and credibility of effluent data, and has allowed management to evaluate the effectiveness of effluent control practices at ERDA facilities. (author)

  1. Uptake by benthic algae of critical radionuclides to be released in the liquid effluent of the Angra dos Reis Nuclear Power Plant, R.J., Brazil

    International Nuclear Information System (INIS)

    Guimaraes, J.R.D.

    1982-06-01

    In vitro interaction of benthic algae from the Angra dos Reis region, R.J., Brazil, was studied with critical radionuclides to be released in the liquid effluent of CNAAA (unit I). 137 Cs- 60 Co - and 125 I uptake and loss by Sargassum filipendula, Padina Vickersiae and Acanthophora Spicifera were observed. Biological half-lives and bioaccumulation factors (B.F.) were estimated. Co and I uptake were fast (apparent equilibrium in 3 to 7 days). Cs uptake was slower (2 to 3 weeks). Loss followed an inverse pattern (fast for Cs, slow for Co and I). B.F. ranged from 10 1 for Cs, to 10 3 for I and 10 3 -10 4 for Co. Higher B.F. for Co and I were found for P. vickersiae (up to 1,4 X 10 4 ) an A. spicifera (up to 7 X 10 3 ) respectively. These species represent important potential media for the transference of Co-I-and-to a much lesser extent - Cs isotopes, through food-webs. They exhibited high capacity to compete with local sandy sediments for the retention of Co and I. High B.F., rapid uptake and moderate to long biological half-lives enable S. filipendula, P. vickersiae and A. specifera to be powerful aids in the monitoring of radioactive contamination by Co and I isotopes. Since the majority of marine organisms tends to exhibit Cs B.F. similars to those reported here, these algae may also be used as monitors for Cs isotopes, the low B.F. being compensated by their abundance, wide distribution and facility of collection. (M.A.) [pt

  2. Applications des techniques de diffusion de la lumière, des rayons X et des neutrons a l'étude des systèmes colloïdaux. Troisième partie : caractérisation des microémulsions et des composés solides. Étude de différents systèmes d'intérêt industriel Application of Light, X-Ray and Neutron Diffusion Techniques to the Study of Colloidal Systems. Part Three: Microemulsions, Solid Materials, Liquids and Miscellaneous Systems with Industrial Uses

    Directory of Open Access Journals (Sweden)

    Espinat D.

    2006-11-01

    Full Text Available Cette troisième partie clôt une revue bibliographique concernant la caractérisation des systèmes colloïdaux par les techniques de diffusion (lumière, rayons X, neutrons (Rev. Inst. Franç. du Pétrole, Vol. 45, No 6, novembre-décembre 1990. Nous poursuivrons cette présentation en nous intéressant aux microémulsions. Après la présentation des informations que l'on peut obtenir sur les systèmes polymériques, les solutions micellaires ou les systèmes fractals, qui ont fait l'objet de multiples travaux, nous reviendrons sur les applications plus restreintes à des systèmes colloïdaux parfois moins bien définis et d'origine industrielle, telles les fractions lourdes des pétroles, les asphaltènes ou encore les additifs de lubrification. Les possibilités de la diffusion des rayons X et des neutrons à l'étude de matériaux solides seront présentées à travers la caractérisation des solides poreux et en particulier des catalyseurs. Nous terminerons cette présentation par les liquides purs ou les mélanges; les techniques de diffusion ont contribué fortement à la description des structures des phases liquides. This article is the second one (the first one was published in Revue de l'Institut Français du Pétrole No. 6, November-December 1990 concerning the application of techniques of light scattering, X rays and neutrons to the analysis of colloidal systems and more specifically to the theoretical description of the three methods. The aim of this second part is to make a nonexhaustive description of several fields of applications. A special effort is made to describe the potential of these methods for characterizing colloidal or divided systems encountered in a great many activities involving the petroleum industry. The first part of this article takes up polymer and colloidal solutions. Particular attention is paid to the importance of scattering techniques for characterizing polymers in solution and micellar solutions. A

  3. Étude de l'efficacité des modes de Lamb dans la signature acoustique en fonction du liquide de couplage

    Science.gov (United States)

    Brunet, N.; Cros, B.; Despaux, G.; Saurel, J.-M.

    1998-06-01

    The acoustic signature allows to measure the velocity of the longitudinal and transverse acoustic waves in bulk materials. From the velocities and density values the elastic properties can be calculated. For thin layer materials, these velocities are not directly measured but computed from the experimentally available velocities: the generalized Lamb waves velocities. These waves velocities are dispersive and their measurement depends on the liquid acting as a coupling fluid. In this study, the two faces of the layer are in contact with the liquid (methanol, water or aqueous solutions of potassium iodide KI_aq. 6 M and potassium hydroxyde KOH_aq. 12 M) chosen according to its acoustic parameters. The acoustic signature modeling allows to know their respective influence, the possible detection of the fast modes and, in general, the velocity measurement accuracy increase for all available modes. The experimental studies bear out that each mode characterization may be optimized by the appropriate choice of the frequency and of the coupling liquid according to its velocity, density and attenuation. L'étude de la signature acoustique permet de mesurer les vitesses de propagation des ondes acoustiques longitudinale et transverse dans les matériaux massifs, vitesses à partir desquelles on détermine leurs propriétés mécaniques. Pour des matériaux en couche mince, ces vitesses ne sont plus mesurées directement mais calculées à partir des vitesses accessibles expérimentalement : celles des modes de Lamb généralisés. Ces modes ont des vitesses dispersives et leur mesure dépend du liquide servant de couplant, dans lequel la couche est immergée. Dans cette étude, les liquides de couplage (méthanol, eau et solutions aqueuses de iodure de potassium KI_aq. 6 M et d'hydroxyde de potassium KOH_aq. 12 M) sont choisis en fonction de leurs paramètres acoustiques. La modélisation de la signature acoustique permet de prévoir leur influence respective, comment ils

  4. Valorisation des résidus carbonatés industriels pour le traitement de sulfure d'hydrogène dans les effluents gazeux

    OpenAIRE

    Galera Martinez , Marta

    2015-01-01

    The purpose of this study to valorize solid wastes from the Solvay process for the production of sodium carbonate as reagents for the treatment of H2S in air at concentrations typically found in wastewater treatment plants (tens to hundreds of ppmv of H2S). Firstly, the reactivity of two residues was evaluated in a gas-liquid-solid reactor at laboratory scale (250 ml). This reactor operates semi-continuously (continuous passage of gas through a fixed volume of slurry). The influence of operat...

  5. Frequency Spectrum of Liquids and Cold Neutron Scattering; Spectre de frequences des liquides et diffusion de neutrons froids; Chastotnyj spektr zhidkostej i rasseyanie kholodnykh nejtronov; Espectro de frecuencias de los liquidos y dispersion de neutrones frios

    Energy Technology Data Exchange (ETDEWEB)

    Singwi, K S; Sjolander, A; Rahman, A [Argonne National Laboratory, Argonne, IL (United States)

    1963-01-15

    An important question which arises in connection with slow neutron scattering by liquids is: does there exist a frequency spectrum tor liquids analogous to that in solids? The answer to this question is given by showing that the width function {gamma}(t) of the Gaussian space-time self-correlation function G{sub s}(r,t) can be expressed, by using the frequency spectrum of the velocity auto-correlation function, in a form which is formally identical with that of a harmonic solid. Thus a knowledge of the frequency spectrum of the velocity auto-correlation function should enable one to calculate slow neutron scattering by liquids as has been emphasized by Egelstaff and co-workers. Using a stochastic model of a liquid, the frequency spectrum f({omega}) of the velocity auto-correlation function is calculated for water at 300{sup o}K and for liquid lead at 620{sup o}K. In the case of water a maximum in f({omega}) corresponding to {Dirac_h} 75{sup o}K is predicted. For lead the maximum also occurs at nearly the same {omega}-value. There also occurs a minimum in f({omega})in both cases. Larsson and Dahlborg have observed a maximum in f({omega}) at the above predicted {omega}-value. A recent observation in liquid lead of Cotter et al. probably confirms our prediction too. (author) [French] Dans le domaine de la diffusion des neutrons lents par des liquides une question importante se pose: existe-t-il un spectre de frequences pour les liquides analogue au spectre pour les solides? On peut repondre d cette quesnon en montrant que la fonction de largeur {gamma}(t) de la fonction gaussienne spatio-temporelle d'auto-correlation G{sub s}(r,t) peut etre exprimee, en employant le spectre de frequences de la fonction d'auto-correlation des vitesses, sous uune forme qui presente le membe aspect formel que celle d'un solide harmonique. par consequent, la connaissance du spectre de frequences de la fonction d'auto-correlation des vitesses devrait permettre de calculer la diffusion des

  6. Applying tracer techniques to NPP liquid effluents for estimating the maximum concentration of soluble pollutants in a man-made canal

    International Nuclear Information System (INIS)

    Varlam, Carmen; Stefanescu, Ioan; Varlam, Mihai; Raceanu, Mircea; Enache, Adrian; Faurescu, Ionut; Patrascu, Vasile; Bucur, Cristina

    2006-01-01

    Full text: The possibility of a contamination agent being accidentally or intentionally spilled upstream from a water supply is a constant concern to those diverting and using water from a channel. A method of rapidly estimating the travel-time or dispersion is needed for pollution control or warning system on channels where data are scarce. Travel-time and mixing of water within a stream are basic streamflow characteristics needed in order to predict the rate of movement and dilution of pollutants that could be introduced in the stream. In this study we propose using tritiated liquid effluents from CANDU type nuclear power plant as a tracer, to study hydrodynamics on Danube-Black Sea Canal. This canal is ideal for this kind of study, because wastewater evacuations occur occasionally due to technical operations of nuclear power plant. Tritiated water can be used to simulate the transport and dispersion of solutes in Danube-Black Sea Canal because they have the same physical characteristics as the water. Measured tracer-response curves produced from injection of a known amount of soluble tracer provide an efficient method of obtaining the necessary data. This method can estimate: (1) the rate of movement of a solute through the canal reach: (2) the rate of peak attenuation concentration of a conservative solute in time; and (3) the length of time required for the solute plume to pass a point in the canal. This paper presents the mixing length calculation for particular conditions (lateral branch of the canal, and lateral injection of wastewater from the nuclear power plant). A study of published experimentally-obtained formulas was used to determine proper mixing length. Simultaneous measurements in different locations of the canal confirm the beginning of the experiment. Another result used in a further experiment concerns the tritium level along the Danube-Black Sea Canal. We measured tritium activity concentration in water sampled along the Canal between July

  7. Molecular dynamics simulations of hydrophobous ions at the liquid-liquid interfaces: case of dicarbollide anions as synergy agents and of ionic liquids as extracting medium; Simulations par dynamique moleculaire d'ions hydrophobes aux interfaces liquide - liquide: le cas des anions dicarbollides comme agents de synergie et celui des liquides ioniques comme milieu extractant

    Energy Technology Data Exchange (ETDEWEB)

    Chevrot, G

    2008-01-15

    Based on molecular dynamics simulations, we first describe the distribution of dicarbollide salts (CCD{sup -}, Mn{sup +}) in concentrated monophasic solutions (water, chloroform, octanol, nitrobenzene) and in the corresponding biphasic 'oil' - water solutions. We point to the importance of surface activity of the CCD{sup -}s and of their self-aggregation in water, with marked counterions effects, and we explain the synergistic effect of CCD{sup -}s in the Eu{sup 3+} extraction by BTP ligands. In the second part of the thesis we report exploratory simulations on the extraction of Sr{sup 2+} by 18-crown-6 to an hydrophobic ionic liquid ([BMI][PF6]), focusing on the liquid - liquid interface. Analogies and differences with a classical aqueous interface are outlined. (author)

  8. Tritium effluent removal system

    International Nuclear Information System (INIS)

    Lamberger, P.H.; Gibbs, G.E.

    1978-01-01

    An air detritiation system has been developed and is in routine use for removing tritium and tritiated compounds from glovebox effluent streams before they are released to the atmosphere. The system is also used, in combination with temporary enclosures, to contain and decontaminate airborne releases resulting from the opening of tritium containment systems during maintenance and repair operations. This detritiation system, which services all the tritium handling areas at Mound Facility, has played an important role in reducing effluents and maintaining them at 2 percent of the level of 8 y ago. The system has a capacity of 1.7 m 3 /min and has operated around the clock for several years. A refrigerated in-line filtration system removes water, mercury, or pump oil and other organics from gaseous waste streams. The filtered waste stream is then heated and passed through two different types of oxidizing beds; the resulting tritiated water is collected on molecular sieve dryer beds. Liquids obtained from regenerating the dryers and from the refrigerated filtration system are collected and transferred to a waste solidification and packaging station. Component redundancy and by-pass capabilities ensure uninterrupted system operation during maintenance. When processing capacity is exceeded, an evacuated storage tank of 45 m 3 is automatically opened to the inlet side of the system. The gaseous effluent from the system is monitored for tritium content and recycled or released directly to the stack. The average release is less than 1 Ci/day. The tritium effluent can be reduced by isotopically swamping the tritium; this is accomplished by adding hydrogen prior to the oxidizer beds, or by adding water to the stream between the two final dryer beds

  9. Reduction by metals dissolved in liquid ammonia of keto steroids. Equilibration of the alcohols; Reduction par les metaux dissous dans l'ammoniac liquide de cetones en serie steroide. Equilibration des alcools

    Energy Technology Data Exchange (ETDEWEB)

    Giroud, A M [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1970-07-01

    'une cetone par les metaux en dissolution fait intervenir deux electrons: on peut considerer comme intermediaire un radical-anion, puis un dianion ou un carbanion. Le radical-anion pouvant aussi se dimeriser pour donner des pinacols. Pour interpreter les resultats des reductions, il nous fallait connaitre les stabilites relatives des alcools ce qui nous a conduit a faire des equilibrations. Dans un premier chapitre, nous etudions les methodes de preparation de l'androstanone-ll et des androstanols-ll{alpha} et ll{beta}. Nous verifions ensuite qu'il n'est pas possible selon nos methodes de conclure sur la stabilite relative des deux alcools par equilibrations experimentales. Nous decrivons enfin les methodes de reduction de la cetone par les metaux alcalins et alcalino-terreux dissous dans l'ammoniac liquide, suivant deux procedes: soit en presence de donneur de protons, soit avec addition posterieure de donneur de protons. Ces reductions conduisent a un melange des deux alcools ou l'isomere {alpha} equatorial stable predomine. Dans un deuxieme chapitre, nous etudions l'action de l'acide selenique et de l'eau oxygenee sur la cholestanone-3, reaction qui nous a permis d'etudier la preparation et la stereochimie des derives du A-nor cholestane. Nous decrivons ensuite la preparation des A-nor cholestanols 2{alpha} et 2{beta} et des acetates correspondants. L'equilibration par des methodes chimiques de ces alcools montre que l'alcool 2 {alpha} est plus stable que l'alcool 2{beta}, ce qui est confirme par le calcul. Enfin, la reduction de la A-nor cholestanone-2 par les metaux en dissolution conduit toujours de facon preponderante a l'epimere 2 {beta} le moins stable avec en outre formation de pinacols. Nous consacrons enfin le troisieme chapitre a l'etude des reductions de l'androstanone-17 et des stabilites relatives des deux alcools 17{alpha} et 17{beta}. Quel que soit le mode operatoire utilise, nous obtenons toujours presque exclusivement l'acool 17{beta} le plus stable. D

  10. Reduction by metals dissolved in liquid ammonia of keto steroids. Equilibration of the alcohols; Reduction par les metaux dissous dans l'ammoniac liquide de cetones en serie steroide. Equilibration des alcools

    Energy Technology Data Exchange (ETDEWEB)

    Giroud, A.M. [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1970-07-01

    'une cetone par les metaux en dissolution fait intervenir deux electrons: on peut considerer comme intermediaire un radical-anion, puis un dianion ou un carbanion. Le radical-anion pouvant aussi se dimeriser pour donner des pinacols. Pour interpreter les resultats des reductions, il nous fallait connaitre les stabilites relatives des alcools ce qui nous a conduit a faire des equilibrations. Dans un premier chapitre, nous etudions les methodes de preparation de l'androstanone-ll et des androstanols-ll{alpha} et ll{beta}. Nous verifions ensuite qu'il n'est pas possible selon nos methodes de conclure sur la stabilite relative des deux alcools par equilibrations experimentales. Nous decrivons enfin les methodes de reduction de la cetone par les metaux alcalins et alcalino-terreux dissous dans l'ammoniac liquide, suivant deux procedes: soit en presence de donneur de protons, soit avec addition posterieure de donneur de protons. Ces reductions conduisent a un melange des deux alcools ou l'isomere {alpha} equatorial stable predomine. Dans un deuxieme chapitre, nous etudions l'action de l'acide selenique et de l'eau oxygenee sur la cholestanone-3, reaction qui nous a permis d'etudier la preparation et la stereochimie des derives du A-nor cholestane. Nous decrivons ensuite la preparation des A-nor cholestanols 2{alpha} et 2{beta} et des acetates correspondants. L'equilibration par des methodes chimiques de ces alcools montre que l'alcool 2 {alpha} est plus stable que l'alcool 2{beta}, ce qui est confirme par le calcul. Enfin, la reduction de la A-nor cholestanone-2 par les metaux en dissolution conduit toujours de facon preponderante a l'epimere 2 {beta} le moins stable avec en outre formation de pinacols. Nous consacrons enfin le troisieme chapitre a l'etude des reductions de l'androstanone-17 et des stabilites relatives des deux alcools 17{alpha} et 17{beta}. Quel que soit le mode operatoire utilise, nous

  11. Operability test procedure for the TK-900 effluent monitoring station

    International Nuclear Information System (INIS)

    Weissenfels, R.D.

    1994-01-01

    This procedure will verify that the 221-B liquid effluent monitoring system, installed near the east end of the 6-in. chemical sewer header, functions as intended by design. TK-900B was installed near stairwell 3 in the 221-B electrical gallery by Project W-007H. The system is part of BAT/AKART for the BCE liquid effluent system

  12. 40 CFR 417.163 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS SOAP AND DETERGENT MANUFACTURING POINT SOURCE CATEGORY Manufacture of Liquid Detergents Subcategory § 417.163 Effluent limitations guidelines representing the degree... subpart after application of the best available technology economically achievable: (a) For normal liquid...

  13. Order of 21 October 1988 withdrawing the licence for the release of liquid radioactive effluents by the Cattenom nuclear production centre (units 1 and 2)

    International Nuclear Information System (INIS)

    1988-01-01

    The Court of Justice of the European Communities decided on 22 September 1988 that the Commission of the European Communities had to be notified and give its opinion before the competent authorities of Member States authorised the release of radioactive effluents from a nuclear installation. In compliance with that judgment, this Order repeals an Order of 21 February 1986 licensing such release (NEA) [fr

  14. Administrative instruction D.G.S./S.D. 7 D./D.H.O.S./E. 4 n. 2001-323 of the 9 july 2001 relative to the management of effluents and wastes from treatment activity and contaminated by radioisotopes; Circulaire D.G.S./S.D. 7 D./D.H.O.S./E. 4 n. 2001-323 du 9 juillet 2001 relative a la gestion des effluents et des dechets d'activites de soins contamines par des radionucleides

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    The three parts for this administrative instruction are general principles of management of effluents and waste at radioactive character, management individualized plan for effluents and wastes, articulation with regulation relative to classified installations for the environmental protection. (N.C.)

  15. Ichthyofauna community from Saco de Piraquara de Fora area by the influence of liquid effluents from the Almirante Alvaro Alberto Nuclear Power in Angra dos Reis

    International Nuclear Information System (INIS)

    Almeida, A.F.V. de

    1995-01-01

    To verify if thermal and chemical effluents of Angra I Nuclear Power Plant are affecting the marine ictiofauna, Furnas Centrais Eletricas S.A. has implemented a monitoring program near the discharge area. Specific composition, frequency, specific relative abundance, specific diversity and others parameters are studied. The main target of this study is to check if the analyzed parametrers show any kind of impact on fish population. In this paper the results were presented. (author). 7 refs, 3 figs, 3 tabs

  16. Radiation protection at the RA reactor in 1984, Part III Removal of the liquid radioactive effluents for the needs of the RA reactor

    International Nuclear Information System (INIS)

    Mandic, M.; Plecas, I.; Vukovic, Z.; Knezevic, Lj.; Jankovic, O.; Kostadinovic, A.; Mihailovic, B.

    1984-01-01

    Contaminated water originates from: hot cells, heavy water distillation device, storage pools for cooling and cutting of fuel elements, water biological shield of the reactor. During 1984, 400 liters of water contaminated by 60 Co was treated. Most recent measurements showed that the VR-1 pool contains 280 m 3 of effluents having specific activity of 3.3 10 4 Bq/ml, and VR-2 contains 30 m 3 with specific activity of 4 10 3 Bq/ml

  17. Oligomerization of ethylene catalysed by nickel complexes associated with nitrogen ligands in ionic liquids; Oligomerisation de l'ethylene catalysee par des complexes du nickel associes a des ligands azotes dans les liquides ioniques

    Energy Technology Data Exchange (ETDEWEB)

    Lecocq, V.

    2003-09-01

    We report here the use of a new class of catalytic systems based on a nickel active center associated with nitrogen ligands, such as di-imines, or imino-pyridines, for the oligomerization of ethylene in a biphasic medium using ionic liquids as the catalyst solvent. The nickel catalyst is immobilized in the ionic liquid phase in which the olefinic reaction products are poorly miscible. This biphasic system makes possible an easy separation and recycle of the catalyst. Numerous di-imine and imino-pyridine ligands with different steric and electronic properties have been synthesized and their corresponding nickel complexes isolated and characterized. Different ionic liquids, based on chloro-aluminates or non-chloro-aluminates anions, have also been prepared and characterized. The effect of the nature of the ligand, the ionic liquid, the nickel precursor and its mode of activation have been studied and correlated with the selectivity and activity of the transformation of ethylene. (author)

  18. Determination of species activities in organic phase. Modelling of liquid-liquid extraction system using uniquac and unifac models; Determination des activites des especes en phase organique. Application d`uniquac et unifac a la modelisation des systemes d`extraction liquide-liquide

    Energy Technology Data Exchange (ETDEWEB)

    Rat, B. [CEA Saclay, 91 - Gif-sur-Yvette (France). Dept. de Recherche en Retraitement et en Vitrification]|[Paris-6 Univ., 75 (France)

    1998-12-31

    The aim of nuclear fuel reprocessing is to separate reusable elements, uranium and plutonium from the other elements, fission products and minor actinides. PUREX process uses liquid-liquid extraction as separation method. Numerical codes for modelling the extraction operations of PUREX process use a semi-empirical model to represent the partition of species. To improve the precision and precision and predictive nature of the models, we looked for a theoretical tool which permits to quantify medium effects, especially in the organic phase, for which few models are available. The Sergeivskii-Dannus model permits to quantify deviations from ideality in organic phase equilibrated with aqueous phase, but with parameters depending on extractant/diluent ratio. We decided to investigate UNIQUAC and UNIFAC models which permit to estimate activity coefficients in non-electrolytic phases taking account of the mutual interactions of molecules and their morphology. UNIFAC is based on UNIQUAC but molecules are considered as structural groups assemblies. Before applying these model to extraction systems, we investigate their abilities to describe simple systems, binary and ternary systems. UNIQUAC has been applied to TBP/diluent mixtures and permits to estimate activity coefficients for diluents whose interactions with TPB are very different in nature and strength. Group contribution (UNIFAC) applied to TBP/alkane mixtures permits to represent the effect of lengthening alkane chain but not the effect of branching. UNIQUAC fails to describe the TBP/diluent/water/non-extractable-salt systems in case of strong TBP diluent interactions. In order to obtain a correct description of these systems, we used the Chem-UNIFAC model, where the INIFAC equation is supplemented with chemical equilibria allowing explicitly for complexes formation and where group contribution is used to describes complexes. We have with Chem-UNIFAC a model available which can take the effect of the diluent into

  19. Olefins hydro-formylation catalysed by rhodium complexes using ionic liquids; Hydroformylation des olefines par les complexes du rhodium dans les liquides ioniques

    Energy Technology Data Exchange (ETDEWEB)

    Favre, F.

    2000-10-26

    Biphasic long chain olefins hydro-formylation catalysed by rhodium complexes using ionic liquids allows a selective reaction and an easy separation of the products from the catalyst. This study reports the synthesis of ionic liquids that were used as the catalyst's solvent. Their physical and chemical properties (melting point, solubility of organic substrates) can be varied with the structure of the organic cation (imidazolium, pyridinium, pyrrolydinium) and with its substituents (nature, length, number). It depends also on the nature of the inorganic anion (hexa-fluoro-phosphate, tetrafluoroborate, tri-fluoro-acetate, triflate, bistriflylamidure...). The use of phosphorus ligands bearing ionic functions proved to be efficient to maintain the onerous rhodium catalyst in the ionic liquid phase. Phosphines, phosphites and phosphinites including anionic (sulfonate, carboxylate) or cationic (imidazolium, pyridinium, guanidinium, phosphonium) groups have been synthesised. Finally, the influences of the ligand and of the ionic liquid on the catalytic system performances are described. Selectivities in aldehydes and reaction rates proved to be highly dependent on the nature of the ligand and of the ionic liquid. The different possibilities of recycling the ionic phase containing the rhodium catalyst have been also studied. (author)

  20. New structural studies of liquid crystal by reflectivity and resonant X-ray diffraction; Nouvelles etudes structurales de cristaux liquides par reflectivite et diffraction resonante des rayons X

    Energy Technology Data Exchange (ETDEWEB)

    Fernandes, P

    2007-04-15

    This memory presents three structural studies of smectic Liquid Crystals by reflectivity and resonant diffraction of X-rays. It is divided in five chapters. In the first a short introduction to Liquid Crystals is given. In particular, the smectic phases that are the object of this study are presented. The second chapter is consecrated to the X-ray experimental techniques that were used in this work. The three last chapters present the works on which this thesis can be divided. Chapter three demonstrates on free-standing films of MHPOBC (historic liquid crystal that possesses the antiferroelectric sub-phases) the possibility to extend the technique of resonant X-ray diffraction to liquid crystals without resonant element. In the fourth chapter the structure of the B{sub 2} liquid crystal phase of bent-core molecules (or banana molecules) is elucidated by using resonant X-ray diffraction combined with polarization analysis of the diffracted beam. A model of the polarization of the resonant beam diffracted by four different structures proposed for the B{sub 2} phase is developed in this chapter. In the fifth chapter a smectic binary mixture presenting a very original critical point of phase separation is studied by X-ray reflectivity and optical microscopy. A concentration gradient in the direction perpendicular to the plane of the film seems to be induced by the free-standing film geometry. The results of a simplified model of the system are compatible with this interpretation.

  1. Effluent Information System (EIS) / Onsite Discharge Information System (ODIS): 1986 executive summary

    International Nuclear Information System (INIS)

    Watanabe, T.

    1987-09-01

    Department of Energy (DOE) data base systems aid DOE-Headquarters and Field Offices in managing the radioactive air and liquid effluents from DOE facilities. Data on effluents released offsite are entered into effluent information system (EIS) and data on effluents discharged onsite and retained onsite are entered into Onsite Discharge Information System (ODIS). This document is a summary of information obtained from the CY 1986 effluent data received from all DOE and DOE contractor facilities and entered in the data bases. Data from previous years are also included. The summary consists of information for effluents released offsite, and information for effluents retained onsite

  2. Order of the 4 March 2014 on the homologation of the decision nr 2014-DC-4016 of the Nuclear Safety Authority of the 16 January 2014 defining the limits of releases in the environment of liquid and gaseous effluents by the basic nuclear installations nr 124, 125, 126 and 137 exploited by EDF-SA in Cattenom (Moselle district)

    International Nuclear Information System (INIS)

    Durand, J.M.

    2014-01-01

    This order issued by the French Ministry of ecology, sustainable development and energy is based on a decision taken by the ASN. It concerns the management of pollutions and of the impact of a nuclear installation on the environment: applicable limits of gaseous (notably carbon 14, tritium, rare gases, iodines), chemical, and liquid effluent release. Tables indicate the maximum concentrations

  3. Transport properties of silver telluride in the solid and liquid states; Etude des proprietes de transport dans le tellurure d'argent Ag{sub 2}Te aux hautes temperatures a l'etat solide et a l'etat liquide

    Energy Technology Data Exchange (ETDEWEB)

    Pham, N T [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1969-01-01

    Measurements of the electrical resistivity, Hall coefficient and thermoelectric power have been carried out for silver telluride over a large temperature range including both solid and liquid states. The analysis of the experimental data shows that in the solid state the transport properties are governed by an ambipolar process with an electron mobility much higher than the hole mobility ({mu}{sub n} = 10*{mu}{sub p}). It is found that the temperature dependence of the electron mobility can be represented by a T{sup -3} law. Deviations from the stoichiometric composition Ag{sub 2}Te have been studied. For all specimens, melting is accompanied by discontinuous variations in the transport properties. Above the melting point, the magnitude of the measured parameters and their temperature dependence show that liquid silver telluride behaves as a semiconductor. The contribution of Ag{sup +} ions to transport phenomena is suggested to account for the behaviour of the electrical properties. Experimental data have been analysed in terms of conventional theories. (author) [French] Les mesures de la resistivite electrique, du coefficient de Hall et du pouvoir thermoelectrique ont ete effectuees sur le tellurure d'argent dans un large domaine de temperature couvrant l'etat solide et l'etat liquide. L'analyse des resultats experimentaux obtenus a l'etat solide montre que les proprietes de transport sont gouvernees par le processus ambipolaire avec une mobilite des electrons beaucoup plus grande que celle des trous ({mu}{sub n} 10*{mu}{sub p}). On trouve que la mobilite des electrons varie avec la temperature suivant la loi T{sup -3}. Les ecarts de la composition stoechiometrique Ag{sub 2}Te ont ete etudies. Pour tous les echantillons, la fusion est caracterisee par des variations discontinues des proprietes de transport. Au dessus du point de fusion, la grandeur des parametres mesures ainsi que leur variation avec la temperature montrent que le tellurure d'argent liquide se

  4. CY-1981 effluent monitoring report

    International Nuclear Information System (INIS)

    Honkus, R.J.

    1982-05-01

    The effluent monitoring programs at ICPP for calendar year 1981 are summarized. During the year, five significant occurrences or unplanned releases occurred. These are briefly described and tabulated. In none of the instances were the applicable Radiation Concentration Guides (RCG's) exceeded. A graphic summary of the total airborne, liquid and solid releases during CY-1981 is presented. Liquid waste activity was higher than anticipated due to various processing factors throughout the year. Solid waste jumped dramatically in December due to shipment of end-prices from the EBR-II fuel which was processed during the Electrolytic campaign

  5. Trace analysis of 61 natural and synthetic progestins in river water and sewage effluents by ultra-high performance liquid chromatography-tandem mass spectrometry.

    Science.gov (United States)

    Shen, Xiaoyan; Chang, Hong; Sun, Dezhi; Wang, Linxia; Wu, Fengchang

    2018-04-15

    A broad number of natural and synthetic progestins are widely used in human and veterinary therapies. Although progestins exhibit adverse effects in aquatic organisms, information about environmental occurrence and fate have been limited to several compounds, hampering the accuracy of risk assessments of the compounds. In this study, a selective and sensitive analytical method was established to simultaneously determine 19 natural and 42 synthetic progestins in environmental waters, and the synthetic progestins included 19-nortestosterone, 17α-hydroxyprogesterone and progesterone derivatives. All of the target compounds were effectively separated using an HSS T3 column, and the recoveries for effluent and river samples were 80-115% and 75-105%, respectively. The detection limits for the 61 analytes were in the range of 0.05-0.60 ng/L and 0.03-0.40 ng/L for the effluent and river samples, respectively. The developed method is applied to analyze the target progestogens in sewage effluent and river water samples from Beijing. The detected concentrations of natural progesterone metabolites (3α-hydroxy-5β-tetrahydroprogesterone) were up to 63 times higher than those of the parent compound. Of the three groups of synthetic progestins, the progesterone derivatives were detected for the first time and had the highest concentrations followed by the 19-nortestosterone and 17α-hydroxyprogesterone derivatives. In contrast to previous studies, the predominant derivative compounds of 19-nortestosterone were found to be 19-nortestosterone, gestodene and mifepristone, and those of 17α-hydroxyprogesterone were 6-epi-medroxy progesterone 17-acetate and melengestrol acetate. The toxicities and environmental risk of these emerging progestins deserves more attention in the future. Copyright © 2018 Elsevier Ltd. All rights reserved.

  6. Fishes of Saco do Piraquara de Fora, in a discharge area of liquid effluents from Angra-1 Nuclear Power Plant (CNAAA)

    International Nuclear Information System (INIS)

    Almeida, Ademar Ferrari Vaz de; Santoro, Maria Dulce Novaes

    1996-01-01

    Because the thermal effluents, released from the Unit I condenser system, it was implanted, at discharge area (Saco Piraquara de Fora), a Marine Fauna and Flora Monitoring Program, been necton area part of this, to verify possible impact over fish population, quantitative and qualitative studies were performed. Trichiurus lipeturus and Diapterus rhombeus were chosen as indicators because the high frequencies and abundances. Besides this, Furnas implanted a Radiological Monitoring Program, where samples of fish were collected and analysed by gamma spectrometry, showing the presence of Cs-137 since the pre-operational period, caused by fall out process at the region, from nuclear weapons test at atmosphere. (author)

  7. Effluent treatment plant and decontamination centre, Trombay

    International Nuclear Information System (INIS)

    Kaushik, C.P.; Agarwal, K.

    2017-01-01

    The Bhabha Atomic Research Centre, Trombay, has a number of plants and laboratories, which generate Radioactive Liquid Waste and Protective Wears. Two facilities have been established in late 1960s to cater to this requirement. The Centre, on the average generates about 50,000 m"3 of active liquid effluents of varying specific activities. The Effluent Treatment Plant was setup to receive and process radioactive liquids generated by various facilities of BARC in Trombay. It also serves a single-point discharge facility to enable monitoring of radioactive effluents discharged from the Trombay site. About 120-150 Te of protective wears and inactive apparel are generated annually from various radioactive facilities and laboratories of BARC. In addition, contaminated fuel assembly components are generated by DHRUVA and formerly by CIRUS. These components require decontamination before its recycle to the fuel assembly process. The Decontamination Centre, setup in late 1960s, is mandated to carry out the above mentioned decontamination activities

  8. Radioactive clearance discharge of effluent from nuclear and radiation facilities

    International Nuclear Information System (INIS)

    Liu Xinhua; Xu Chunyan

    2013-01-01

    On the basis of the basic concepts of radiation safety management system exemption, exclusion and clearance, we expound that the general industrial gaseous and liquid effluent discharges are exempted or excluded, gaseous and liquid effluent discharged from nuclear and radiation facilities are clearance, and non-radioactive. The main purpose of this paper is to clarify the concepts, reach a consensus that the gaseous and liquid effluent discharged from nuclear and radiation facilities are non-radioactive and have no hazard to human health and natural environment. (authors)

  9. 3-D modeling of parietal liquid films in internal combustion engines; Modelisation tridimensionnelle des films liquides parietaux dans les moteurs a combustion interne

    Energy Technology Data Exchange (ETDEWEB)

    Foucart, H

    1998-12-11

    To simulate the air-fuel mixing in the intake ports and cylinder of an internal combustion engines, a wall fuel liquid film model has been developed for integration in 3D CFD codes. Phenomena taken into account include wall film formation by an impinging spray without splashing effect, film transport such as governed by mass and momentum equations with hot wall effects, and evaporation considering energy equation with an analytical mass transfer formulation developed here. A continuous-fluid method is used to describe the wall film over a three dimensional complex surface. The basic approximation is that of a laminar incompressible boundary layer; the liquid film equations are written in an integral form and solved by a first-order ALE finite volume scheme; the equation system is closed without coefficient fitting requirements. The model has been implemented in a Multi-Block version of KIVA-II (KMB) and tested against problems having theoretical solutions. Then in a first step, it has been compared to the measurements obtained in a cylindrical pipe reproducing the main characteristics of SI engine intake pipe flow and in a second step, it has been compared to the Xiong experiment concerning the film evaporation on a hot wall. The film behaviour is satisfactory reproduced by the computations for a set of operating conditions. Finally, engine calculations were conducted showing the importance of including a liquid film model for the simulations. (author) 54 refs.

  10. Impact evaluation of the liquid effluent disposal of the Duque de Caxias Refinery (REDUC) in fluvial waters and sediments, RJ, Brazil; Avaliacao do impacto do descarte de efluentes liquidos da Refinaria Duque de Caxias (REDUC) sobre aguas e sedimentos fluviais, RJ, Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Bidone, Edison Dausacker; Santelli, Ricardo Erthal; Cordeiro, Renato Campello [Universidade Federal Fluminense (UFF), Niteroi, RJ (Brazil); Gamboa, Carla Maria; Camaz, Fernando Ribeiro; Jorge, Fabricio Goncalves [PETROBRAS/REDUC, Rio de Janeiro, RJ, RJ (Brazil). Refinaria de Duque de Caxias; Carvalho, Maria de Fatima B. [PETROBRAS S.A., Rio de Janeiro, RJ (Brazil). Centro de Pesquisas (CENPES)

    2008-07-01

    The purpose of this work is to assess the contribution of the liquid effluents of the Duque de Caxias Refinery (REDUC) in the water and sediment contamination in the estuarine Iguacu-Sarapui system, a tributary of the Guanabara Bay, Rio de Janeiro, Brazil. Since 2002 is being conducted a quarterly monitoring of some parameters in water, river sediments and treated liquid effluent, such as: pH, suspended solids, total sedimented solids, dissolved oxygen, biochemical oxygen demand, chemical oxygen demand, total organic carbon, oil and grease (O and G), phenols, sulfide, ammonia, metals and metalloids (V, Cr, Pb, Ni, Cu, Cd, Zn, Hg, As, Se , Co, Fe, Mn), polycyclic aromatic hydrocarbons, coprostanol and cholesterol (indicators of domestic wastes). The obtained results show that the effluents meet the legal standards and the treated liquid effluents from REDUC in the estuarine system have little or no impact on river water quality. The higher levels of contaminants detected in water and sediments samples are directly related to untreated domestic sewage from urban areas. (author)

  11. Readiness Assessment Plan, Hanford 200 areas treated effluent disposal facilities

    International Nuclear Information System (INIS)

    Ulmer, F.J.

    1995-01-01

    This Readiness Assessment Plan documents Liquid Effluent Facilities review process used to establish the scope of review, documentation requirements, performance assessment, and plant readiness to begin operation of the Treated Effluent Disposal system in accordance with DOE-RLID-5480.31, Startup and Restart of Facilities Operational Readiness Review and Readiness Assessments

  12. Facility effluent monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Gleckler, B.P.

    1995-06-01

    This section of the 1994 Hanford Site Environmental Report summarizes the facility effluent monitoring programs and provides an evaluation of effluent monitoring data. These evaluations are useful in assessing the effectiveness of effluent treatment and control systems, as well as management practices.

  13. Absorption spectra between 0.8 {mu} and 30 {mu} of mixtures of H{sub 2}O - D{sub 2}O in the liquid state; Le spectre d'absorption des melanges H{sub 2}O-D{sub 2}O a l'etat liquide entre 0,8 et 30 {mu}

    Energy Technology Data Exchange (ETDEWEB)

    Ceccaldi, M; Goldman, M; Roth, E [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    There has been very little work carried out recently on the absorption bands of H{sub 2}O, HDO and D{sub 2}O in the liquid state. We have established the spectra of these molecules in between 0.8 and 30 p. The table of absorption bands of the molecules HDO and D{sub 2}O for which all the bands corresponding to those for H{sub 2}O had not been established has been completed. We have sought a convenient method of representing the variations in optical density of certain HDO bands as a function of the concentration of heavy water in the mixtures studied. (author) [French] Il y a peu de travaux recents sur les bandes d'absorption de H{sub 2}O, HDO et D{sub 2}O a l'etat liquide. Nous avons releve les spectres de ces molecules entre 0,8 et 30 p. Le tableau des bandes d'absorption des molecules HDO et D{sub 2}O, pour lesquelles le releve de toutes les bandes correspondantes a celles de H{sub 2}O n'etait pas encore effectue, a ete complete. Nous avons cherche des modes de representation commodes des variations de densite optique de certaines bandes de HDO en fonction de la teneur en eau lourde des melanges etudies. (auteur)

  14. Estimative of dilution factor for radioactive liquid effluents employing the H-3 and Cs-137 radiotracers present as pollutant; Estimativa do fator de diluicao para efluentes radioativos liquidos empregando os radiotracadores H-3 e Cs-137 presentes como poluentes

    Energy Technology Data Exchange (ETDEWEB)

    Nisti, Marcelo Bessa; Santos, Adir Janete Godoy dos, E-mail: mbnisti@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    It was estimated the dilution factor for liquid effluents at the discharge points of the IPEN, Sao Paulo, Brazil, employing as radiotracers the radioisotope routinely liberated for the sewage of 'Cidade Universitaria Armando de Salles Oliveira' - CUASO {sup 3}H and {sup 137}Cs, not generating either monetary or environmental cost associated to the estimation. The {sup 137}Cs was determined by gamma spectrometry and the {sup 3}H was determined liquid phase scintillation. The results showed that the dilution factor varied according to the employed radiotracer in a crescent order of {sup 3}H and {sup 137}Cs according to the characteristics of each element. The average of dilution factors obtained at the first and second liberation day were 4.3 and 7.4 respectively for the {sup 3}H and 6.2 and 13.9 for the {sup 137}Cs. The ratio of dilution factors of calculated {sup 3}H and {sup 137}Cs were coherent with the ratio verified at the twelve hydrometers distributed by the IPEN campus. The dilution factors were estimated in operational and laboratory study, in a single controlled discharge of the TR1 tank

  15. Oxydation en voie humide des effluents des distilleries d'alcool à partir de canne à sucre en présence de catalyseurs Ru et Pt supportés sur TiO2 ou ZrO2

    OpenAIRE

    Le , Phuong Thu

    2013-01-01

    Vinasse is an aqueous effluent originating from ethanol production process from sugarcane. It is a dark brown effluent with an extremely high COD and a low BOD. The treatment of this type of effluent by wet air oxidation (WAO) was the subject of this study using noble metal catalysts supported on TiO2 and ZrO2 at 190-210 ° C under 50-70 bar air. The addition of Ru catalysts allowed the complete mineralization of the organic model pollutants (sucrose, polyethylene glycol, melanoidin) or the re...

  16. Letters and Viewpoints Studies on the Effect of Laundry Effluent on ...

    African Journals Online (AJOL)

    topsoil, laundry effluent, soil physiochemical properties, pH, available phosphorus, exchangeable sodium, potassium, exchangeable sodium percentage, percentage base saturation, soil buffering capacity, cation exchange capacity, Edo, Nigeria Résume Des résidus issus des blanchisseries ont toujours prouvé leur effet ...

  17. Kinetic of liquid-liquid extraction for uranyl nitrate and actinides (III) and lanthanides (III) nitrates by amide extractants; Cinetique d`extraction liquide-liquide du nitrate d`uranyle et des nitrates d`actinides (III) et de lanthanides (III) par des extractants a fonction amide

    Energy Technology Data Exchange (ETDEWEB)

    Toulemonde, V [CEA Centre d` Etudes Nucleaires de Saclay, 91 -Gif-sur-Yvette (France); [CEA Centre d` Etudes de la Vallee du Rhone, 30 -Marcoule (France). Dept. d` Exploitation du Retraitement et de Demantelement

    1995-12-20

    The kinetics of liquid-liquid extraction by amide extractants have been investigated for uranyl nitrate (monoamide extractants), actinides (III) and lanthanides (III) nitrates (diamide extractants). The transfer of the metallic species from the aqueous phase to the organic phase was studied using two experimental devices: ARMOLLEX (Argonne Modified Lewis cell for Liquid Liquid Extraction) and RSC (Rotating Stabilized Cell). The main conclusions are: for the extraction of uranyl nitrate by DEHDMBA monoamide, the rate-controlling step is the complexation of the species at the interface of the two liquids. Thus, an absorption-desorption (according to Langmuir theory) reaction mechanism was proposed; for the extraction of actinides (III) and lanthanides (III) nitrates in nitric acid media by DMDBTDMA diamide, the kinetic is also limited by interfacial reactions. The behavior of Americium and Europium is very similar as fare as their reaction kinetics are concerned. (author). 89 refs.

  18. POLAR ORGANIC CHEMICAL INTEGRATIVE SAMPLING AND LIQUID CHROMATOGRAPHY-ELECTROSPRAY/ION-TRAP MASS SPECTROMETRY FOR ASSESSING SELECTED PRESCRIPTION AND ILLICIT DRUGS IN TREATED SEWAGE EFFLUENTS

    Science.gov (United States)

    The purpose of the research presented in this paper is two-fold: (1) to demonstrate the 4 coupling of two state-of-the-art techniques: a time-weighted polar organic integrative sampler (POCIS) and micro-liquid chromatography-electrospray/ion trap mass spectrometry (u-LC-6 ES/ITMS...

  19. NMR studies of the molecules dynamics to the solid-liquid interfaces: from graded porous materials to oil rocks; Etudes RMN de la dynamique des molecules aux interfaces solide-liquide: des materiaux poreux calibres aux roches petroliferes

    Energy Technology Data Exchange (ETDEWEB)

    Godefroy, S

    2001-11-01

    Low field NMR relaxation for laboratory or in-situ applications provides critical information for oil recovery such as porosity, saturation, and permeability of rocks. In addition, pore size distribution and wettability can also be obtained in some cases. The technique relies on the measurement of proton longitudinal (T{sub 1}) or transverse (T{sub 2}) nuclear relaxation times. For better predictions, the surface micro-dynamics and the chemical properties of the liquids entrapped in the pore space are important and must be characterized. It is well known that the NMR relaxation is enhanced by the paramagnetic impurities at the pore surface but many other parameters influence the relaxation time distributions. These parameters are used to derive the petrophysical properties of the rocks. We propose here an original method to probe the dynamics of water and oil at the pore surface. In the present study, we used both nuclear relaxation at 2.2 MHz and field cycling Nuclear Magnetic Relaxation Dispersion (NMRD) techniques. We applied these two techniques to different kinds of water or oil saturated macroporous media (grain packings, outcrop and reservoir rocks with SiO{sub 2} or CaCO{sub 3} surfaces). We studied the dependence of NMR relaxation on pore size, magnetic field and temperature. Varying the pore size and the surface density of paramagnetic impurities of water saturated grain packings allowed experimental evidence for the two limiting regimes of the water relaxation in pores (surface- and diffusion-limited regimes). NMRD technique (evolution of 1/T{sub 1} with the magnetic field) allowed us to probe liquid surface dynamics in water or oil fully saturated grain packing, outcrop rocks or reservoir rocks (water- and oil-wet surfaces). We evidenced a two-dimensional molecular surface diffusion and directly estimated important parameters such as correlation times, residence times and molecular self-diffusion on the surface. Finally, we proved that the temperature

  20. Effluent and water treatment at AERE Harwell

    International Nuclear Information System (INIS)

    Lewis, J.B.

    1977-01-01

    The treatment of liquid wastes at Harwell is based on two main principles: separation of surface water, domestic sewage, trade wastes and radioactive effluents at source, and a system of holding tanks which are sampled so that the appropriate treatment can be given to any batch. All discharges are subject to independent monitoring by the authorising departments and the Thames Water Inspectors. (author)

  1. Contribution to the study of hydrogenated and oxygenated impurities in liquid sodium; Contribution a l'etude des impuretees hydrogenees et oxygenees dans le sodium liquide

    Energy Technology Data Exchange (ETDEWEB)

    Naud, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1964-07-15

    'hydrogene total, en determinant successivement les concentrations en gaz present sous forme d'hydrure et d'hydroxyde. Cette methode est basee sur la decomposition thermique de l'hydrure et la reaction entre le sodium et l'hydroxyde. Notre contribution a l'etude du systeme Na-H{sub 2}-O{sub 2} comporte tout d'abord l'etude de la reaction de l'hydrogene avec le sodium dans l'intervalle de temperature 150-250 deg C et sous une pression de 150 mm de mercure environ. L'etude de la decomposition thermique de l'hydrure au sein du sodium a ete ensuite effectuee. Quelques indications qualitatives concernant la reaction entre le sodium et l'hydroxyde de sodium ont pu etre degagees. Enfin quelques essais complementaires nous ont permis de preciser la nature des phenomenes intervenant lors de l'attaque du verre pyrex par le sodium. (auteur)

  2. Extraction liquide-liquide des sels minéraux. Approximation analytique des isothermes de partage. Application au calcul sur ordinateur d'une installation Liquid-Liquid Extraction of Mineral Salts. Analytical Approximation of Partition Isotherms. Application to the Computer Designing of an Installation

    Directory of Open Access Journals (Sweden)

    Chaid M. T.

    2006-11-01

    Full Text Available Cet article comporte deux parties -dans la première on a calculé les isothermes de partage en partant des considérations thermodynamiques basées sur les travaux de Guggenheim. Les résultats ne sont bons que dans le cas des solutions idéales. On a donc simulé les isothermes par des fonctions analytiques. Celles-ci permettent de représenter convenablement tous les faisceaux d'isothermes quelles que soient l'acidité de la solution aqueuse et les concentrations dans les deux phases; - la deuxième partie est réservée au calcul d'une installation complète d'extraction avec colonne de récupération; le calcul, mené sur ordinateur, utilise les fonctions analytiques précédentes et permet d'obtenir les débits et les concentrations à chaque plateau. This article contains two parts: - the first part discusses the calculating of partition isotherms using thermodynamic considerations based on research by Guggenheim. The results are good only in the case of ideal solutions. Therefore, isotherms were simulated by ànalyticfunctionswhich are suitable for representing all isotherm bundles no matter what the acidity of the aqueous solution and the concentrations in both phases moy be. - the second part 'deals' with designing a complete extraction installation with a recovery column. Computerized designing makes use of the preceding analytic functions and enables flowrates and concentrations ta be determined at each plate.

  3. A guide for preparing Hanford Site facility effluent monitoring plans

    International Nuclear Information System (INIS)

    Nickels, J.M.

    1992-06-01

    This document provides guidance on the format and content of effluent monitoring plans for facilities at the Hanford Site. The guidance provided in this document is designed to ensure compliance with US Department of Energy (DOE) Orders 5400.1 (DOE 1988a), 5400.3 (DOE 1989a), 5400.4 (DOE 1989b), 5400.5 (DOE 1990a), 5480.1 (DOE 1982), 5480.11 (DOE 1988b), and 5484.1 (DOE 1981). These require environmental monitoring plans for each site, facility, or process that uses, generates, releases, or manages significant pollutants of radioactive or hazardous materials. In support of DOE Orders 5400.5 (Radiation Protection of the Public and the Environment) and 5400.1 (General Environmental Protection Program), the DOE Environmental Regulatory Guide for Radiological Effluent Monitoring and Environmental Surveillance (DOE 1991) should be used to establish elements of a radiological effluent monitoring program in the Facility Effluent Monitoring Plan. Evaluation of facilities for compliance with the US Environmental Protection Agency Clean Air Act of 1977 requirements also is included in the airborne emissions section of the Facility Effluent Monitoring Plans. Sampling Analysis Plans for Liquid Effluents, as required by the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), also are included in the Facility Effluent Monitoring Plans. The Facility Effluent Monitoring Plans shall include complete documentation of gaseous and liquid effluent sampling and monitoring systems

  4. Modelling and numerical simulation of liquid-vapor phase transitions; Modelisation et simulation numerique des transitions de phase liquide-vapeur

    Energy Technology Data Exchange (ETDEWEB)

    Caro, F

    2004-11-15

    This work deals with the modelling and numerical simulation of liquid-vapor phase transition phenomena. The study is divided into two part: first we investigate phase transition phenomena with a Van Der Waals equation of state (non monotonic equation of state), then we adopt an alternative approach with two equations of state. In the first part, we study the classical viscous criteria for selecting weak solutions of the system used when the equation of state is non monotonic. Those criteria do not select physical solutions and therefore we focus a more recent criterion: the visco-capillary criterion. We use this criterion to exactly solve the Riemann problem (which imposes solving an algebraic scalar non linear equation). Unfortunately, this step is quite costly in term of CPU which prevent from using this method as a ground for building Godunov solvers. That is why we propose an alternative approach two equations of state. Using the least action principle, we propose a phase changing two-phase flow model which is based on the second thermodynamic principle. We shall then describe two equilibrium submodels issued from the relaxations processes when instantaneous equilibrium is assumed. Despite the weak hyperbolicity of the last sub-model, we propose stable numerical schemes based on a two-step strategy involving a convective step followed by a relaxation step. We show the ability of the system to simulate vapor bubbles nucleation. (author)

  5. Synthesis and characterization of hybrid silicon based complexing materials: extraction of transuranic elements from high level liquid waste; Synthese et caracterisation de gels hybrides de silice a proprietes complexantes: applications a l'extraction des transuraniens des effluents aqueux

    Energy Technology Data Exchange (ETDEWEB)

    Conocar, O

    1999-07-01

    Hybrid organic/inorganic silica compounds with extractive properties have been developed under an enhanced decontamination program for radioactive aqueous nitric acid waste in nuclear facilities. The materials were obtained by the sol-gel process through hydrolysis and poly-condensation of complexing organo-tri-alkoxy-silanes with the corresponding tetra-alkoxy-silane. Hybrid silica compounds were initially synthesized and characterized from mono- and bis-silyl precursors with malonamide or ethylenediamine patterns. Solids with different specific areas and pore diameters were obtained depending on the nature of the precursor, its functionality and its concentration in the tetra-alkoxy-silane. These compounds were then considered and assessed for use in plutonium and americium extraction. Excellent results-partitioning coefficients and capacities have been obtained with malonamide hybrid silica. The comparison with silica compounds impregnated or grafted with the same type of organic group is significant in this respect. Much of the improved performance obtained with hybrid silica may be attributed to the large quantity of complexing groups that can be incorporated in these materials. The effect of the solid texture on the extraction performance was also studied. Although the capacity increased with the specific area, little effect was observed on the distribution coefficients -notably for americium- indicating that the most favorable complexation sites are found on the outer surface. Macroporous malonamide hybrid silica compounds were synthesized to study the effects of the pore diameter, but the results have been inconclusive to date because of the unexpected molecular composition of the materials. (author)

  6. Decision no 2010-DC-0188 by the Nuclear Safety Authority on the 7. of July 2010 specifying to Electricite de France-Societe Anonyme (EDF-SA) the limits of releases in the environment of liquid and gaseous effluents for the operation of Flamanville 1 (IBN n 108), Flamanville 2 (INB n 109) and Flamanville 3 (INB n 167) reactors

    International Nuclear Information System (INIS)

    2010-01-01

    This document contains references to the different legal and official documents (codes, orders, minister's opinion, public surveys, administrative authorizations, local community opinion) at the root of this specification of limits related to releases in the environment of liquid and gaseous effluents by the three Flamanville nuclear reactors operated by Electricite de France-Societe Anonyme (EDF-SA). Tables present the limits for different gaseous and liquid radioactive emissions (carbon 14, hydrogen 3, iodine, radioactive rare earths, and other beta and gamma emitters) from these different installations, but also the maximum admitted concentrations for gaseous chemical effluents (boric acid, hydrazine hydrate, morpholine, phosphates, nitrates, various metals, and so on). The limits for thermal releases are also specified

  7. Decision no 2009-DC-0158 of the 15. of September 2009 by the Nuclear Safety Authority specifying instructions related to modalities of water sampling and consumption, and of release in the environment of liquid and gaseous effluents from the base nuclear installation n. 29 operated by the CIS Bio International on the district of Saclay (Essonne department)

    International Nuclear Information System (INIS)

    2009-01-01

    After references to the different legal and official documents (codes, orders, minister's opinion, public surveys, administrative authorizations, local community opinion), this document specifies the instructions related to modalities of water sampling and consumption, and of release in the environment of liquid and gaseous effluents from the base nuclear installation operated by CIS Bio International in Saclay. These instructions and provisions concern the general means implemented by the operator, records, the control by authorities, the limits of water sampling and consumption, the water sampling process, the sampling works and their maintenance and control, the release of liquid, gaseous and radioactive effluents, their control and their transfer, the limit values for different compounds and species, the control of environment around the site, the information of authorities and of population

  8. Decision no 2010-DC-0183 by the Nuclear Safety Authority on the 18. of May 2010 specifying instructions related to modalities of water sampling and consumption, and of release in the environment of liquid and gaseous effluents from the base nuclear installations no 46, no 74 and no 100 operated by Electricite de France-Societe Anonyme (EDF-SA) on the district of Saint-Laurent-Nouan (Loir-et-Cher department)

    International Nuclear Information System (INIS)

    2010-01-01

    After references to the different legal and official documents (codes, orders, minister's opinion, public surveys, administrative authorizations, local community opinion), this document specifies the instructions related to modalities of water sampling and consumption, and of release in the environment of liquid and gaseous effluents from some specific base nuclear installations. These instructions and provisions concern the general means implemented by the operator, records, the control by authorities, the limits of water sampling and consumption, the water sampling process, the sampling works and their maintenance and control, the release of liquid, gaseous and radioactive effluents, their control, and the information of authorities and of population

  9. Method for removing and decolorizing aqueous waste effluents containing dissolved or dispersed organic matter

    International Nuclear Information System (INIS)

    Case, F.N.; Ketchen, E.E.

    1975-01-01

    A method is provided for treating organic waste material dissolved or dispersed in an aqueous effluent, which comprises contacting the effluent with an inert particulate carbonaceous sorbent at an oxygen pressure up to 2000 psi, irradiating the resultant mixture with high energy radiation until a decolorized liquid is produced, and then separating the decolorized liquid

  10. Instruments used to measure or check {alpha}, {beta}, {gamma} activity and neutron emission in the course of processing ore or irradiated fuel; Appareils de mesure ou de controle {alpha}, {beta}, {gamma}, n, des circuits des usines de traitement du minerai ou du combustible irradie

    Energy Technology Data Exchange (ETDEWEB)

    Blanc, A; Brunet, M; Kermagoret, M; Labeyrie, J; Roux, G; Vasseur, J; Weil, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1959-07-01

    One of the methods checking ores in the course of treatment is the rapid quantitative determination of thorium. This measurement is carried out by means of a scintillation instrument which shows the {beta} and {alpha} coincidences of ThC and ThC'. The treatment of irradiated fuel is accompanied by a large number of radioactive checks relative to the performance of the fixation and elution operations of uranium in the ion exchangers, to the concentration of radioactivity of effluent sent from the plant into watercourses. The operations of fixation and elution of the uranium are checked automatically by an instrument which takes a sample of 5 cm{sup 3} of solution, evaporates it and measures its activity every 10 or 20 minutes. Plutonium concentrations are measured: - in the presence of strong {beta} {gamma} activities, by means of rotating cylinder detectors; - in the presence of weak {beta} {gamma} activities, by means of {alpha} detectors scanning a constant level liquid surface; - by means of fission chambers relatively insensitive to {gamma}. Fission product concentrations are measured by chambers, counters or scintillators, according to the amount of {gamma} activity present. Finally, the activity of effluent to be emptied into watercourses is checked by means of a scintillation instrument, which measures the {alpha} activity on the one hand, and on the other hand the {beta} {gamma} activity of residue from a 100 cm{sup 3} sample taken and evaporated in 20 minutes. (author) [French] Parmi les controles relatifs au minerai en cours de traitement, figure le dosage rapide de thorium. Cette mesure est realisee au moyen d'un appareillage a scintillation qui met en evidence la coincidence des emissions {beta} et {alpha} du ThC et du ThC'. Le traitement des combustibles irradies s'accompagne d'un grand nombre de controles radioactifs portant sur le fonctionnement des operations de fixation et d'elution de l'uranium dans les echangeurs d'ions, sur la concentration du

  11. Study of the influence of the fast neutron spectrum on the production of defects in solids and liquids; Etude de l'influence du spectre des neutrons rapides sur la creation de defauts dans les solides et les liquides

    Energy Technology Data Exchange (ETDEWEB)

    Mas, P; Droulers, Y [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

    1964-07-01

    les neutrons rapides dans le carbone, l'oxygene et l'hydrogene. Dans une zone de 25 cm entourant le coeur d'une pile piscine, ces integrales de degagement d'energie sont a peu pres proportionnelles au flux de neutrons au-dessus de 1 MeV. La determination du degagement d'energie en provenance des neutrons dans les liquides organiques se ramene donc a la determination du flux au-dessus de 1 MeV sous le spectre reel. Une verification calorimetrique a ete faite pour l'eau. (auteurs)

  12. Procédé et dispositif de lombrifiltration pour l'assainissement des eaux usées

    OpenAIRE

    DUCLOS, Lucie; FILLIT, Fabien; SOTO, Patricio; BRUNEAU, Denis

    2013-01-01

    L'objet de l'invention est un dispositif de lombrifiltration pour l'assainissement des eaux usées, dans une habitation individuelle comprenant un lombrifiltre (18) ainsi que des moyens (16) de prétraitement par réduction des dimensions des particules solides des effluents eaux usées, des moyens (20) de post-traitement et une sortie (22) des eaux claires. L'invention couvre également le procédé associé.

  13. modelling effluent assimila modelling effluent assimilat modelling

    African Journals Online (AJOL)

    eobe

    G EFFLUENT ASSIMILATIVE CAPACITY OF IKPOBA RIVE. BENIN CITY, NIGERIA ... l purposes to communities rse such as ... treat in order for it to meet the aforeme of the communities. It is therefore i ..... Substituting and integrating yields the following equations ..... Purification Potentials of Small Tropical Urban. Stream: A ...

  14. Selective catalytic reduction of nitrogen oxides from industrial gases by hydrogen or methane; Reduction catalytique selective des oxydes d'azote (NO{sub x}) provenant d'effluents gazeux industriels par l'hydrogene ou le methane

    Energy Technology Data Exchange (ETDEWEB)

    Engelmann Pirez, M

    2004-12-15

    This work deals with the selective catalytic reduction of nitrogen oxides (NO{sub x}), contained in the effluents of industrial plants, by hydrogen or methane. The aim is to replace ammonia, used as reducing agent, in the conventional process. The use of others reducing agents such as hydrogen or methane is interesting for different reasons: practical, economical and ecological. The catalyst has to convert selectively NO into N{sub 2}, in presence of an excess of oxygen, steam and sulfur dioxide. The developed catalyst is constituted by a support such as perovskites, particularly LaCoO{sub 3}, on which are dispersed noble metals (palladium, platinum). The interaction between the noble metal and the support, generated during the activation of the catalyst, allows to minimize the water and sulfur dioxide inhibitor phenomena on the catalytic performances, particularly in the reduction of NO by hydrogen. (O.M.)

  15. Rapid wide-scope screening of drugs of abuse, prescription drugs with potential for abuse and their metabolites in influent and effluent urban wastewater by ultrahigh pressure liquid chromatography-quadrupole-time-of-flight-mass spectrometry

    International Nuclear Information System (INIS)

    Hernandez, Felix; Bijlsma, Lubertus; Sancho, Juan V.; Diaz, Ramon; Ibanez, Maria

    2011-01-01

    This work illustrates the potential of hybrid quadrupole-time-of-flight mass spectrometry (QTOF MS) coupled to ultrahigh pressure liquid chromatography (UHPLC) to investigate the presence of drugs of abuse in wastewater. After solid-phase extraction with Oasis MCX cartridges, seventy-six illicit drugs, prescription drugs with potential for abuse, and metabolites were investigated in the samples by TOF MS using electrospray interface under positive ionization mode, with MS data acquired over an m/z range of 50-1000 Da. For 11 compounds, reference standards were available, and experimental data (e.g., retention time and fragmentation data) could be obtained, facilitating a more confident identification. The use of a QTOF instrument enabled the simultaneous application of two acquisition functions with different collision energies: a low energy (LE) function, where none or poor fragmentation took place, and a high energy (HE) function, where fragmentation in the collision cell was promoted. This approach, known as MS E , enabled the simultaneous acquisition of full-spectrum accurate mass data of both protonated molecules and fragment ions in a single injection, providing relevant information that facilitates the rapid detection and reliable identification of these emerging contaminants in the sample matrices analyzed. In addition, isomeric compounds, like the opiates, morphine and norcodeine, could be discriminated by their specific fragments observed in HE TOF MS spectra, without the need of reference standards. UHPLC-QTOF MS was proven to be a powerful and efficient technique for rapid wide-scope screening and identification of many relevant drugs in complex matrices, such as influent and effluent urban wastewater.

  16. Rapid wide-scope screening of drugs of abuse, prescription drugs with potential for abuse and their metabolites in influent and effluent urban wastewater by ultrahigh pressure liquid chromatography-quadrupole-time-of-flight-mass spectrometry

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez, Felix, E-mail: felix.hernandez@qfa.uji.es [Research Institute for Pesticides and Water, University Jaume I, Avda. Sos Baynat s/n, E-12071 Castellon (Spain); Bijlsma, Lubertus, E-mail: bijlsma@guest.uji.es [Research Institute for Pesticides and Water, University Jaume I, Avda. Sos Baynat s/n, E-12071 Castellon (Spain); Sancho, Juan V.; Diaz, Ramon; Ibanez, Maria [Research Institute for Pesticides and Water, University Jaume I, Avda. Sos Baynat s/n, E-12071 Castellon (Spain)

    2011-01-17

    This work illustrates the potential of hybrid quadrupole-time-of-flight mass spectrometry (QTOF MS) coupled to ultrahigh pressure liquid chromatography (UHPLC) to investigate the presence of drugs of abuse in wastewater. After solid-phase extraction with Oasis MCX cartridges, seventy-six illicit drugs, prescription drugs with potential for abuse, and metabolites were investigated in the samples by TOF MS using electrospray interface under positive ionization mode, with MS data acquired over an m/z range of 50-1000 Da. For 11 compounds, reference standards were available, and experimental data (e.g., retention time and fragmentation data) could be obtained, facilitating a more confident identification. The use of a QTOF instrument enabled the simultaneous application of two acquisition functions with different collision energies: a low energy (LE) function, where none or poor fragmentation took place, and a high energy (HE) function, where fragmentation in the collision cell was promoted. This approach, known as MS{sup E}, enabled the simultaneous acquisition of full-spectrum accurate mass data of both protonated molecules and fragment ions in a single injection, providing relevant information that facilitates the rapid detection and reliable identification of these emerging contaminants in the sample matrices analyzed. In addition, isomeric compounds, like the opiates, morphine and norcodeine, could be discriminated by their specific fragments observed in HE TOF MS spectra, without the need of reference standards. UHPLC-QTOF MS was proven to be a powerful and efficient technique for rapid wide-scope screening and identification of many relevant drugs in complex matrices, such as influent and effluent urban wastewater.

  17. Radioactive effluent monitoring at the Idaho National Engineering Laboratory

    International Nuclear Information System (INIS)

    Simpson, O.D.

    1975-01-01

    The Effluent and Radiation Measurements Laboratory at the Idaho National Engineering Laboratory (INEL) has recently upgraded capabilities in the field of monitoring and analysis of radioactive airborne and liquid effluents using the techniques of gamma-ray spectrometry. The techniques and equipment used include remotely-operated, computer-based Ge(Li) spectrometers which obtain data on a real-time basis. Permanent record files are maintained of both the effluent release values and the gamma-ray data from which the release values are calculated. Should values for release levels ever be challenged, the gamma-ray spectral information for any measurement can be recalled and analyzed as needed. Daily effluent release reports are provided to operating personnel which contributes to prompt correction of any operational problems. Monthly, quarterly, and annual reports are compiled which provide inventories of the radionuclides released. A description of the effluent monitoring, reporting and records system developed at INEL for this application will be presented

  18. The Hydrodynamic Characteristics of Cocurrent Downflow and Cocurrent Upflow Gas-Liquid-Solid Catalytic Fixed Bed Reactors: the Effect of Pressure Les caractéristiques hydrodynamiques des réacteurs gaz-liquide-solide à lit de catalyseur fixe à écoulement cocourant montant et descendant : l'influence de la pression

    Directory of Open Access Journals (Sweden)

    Wild G.

    2006-11-01

    Full Text Available While most catalytic fixed bed gas-liquid reactors of the petrol industry work at quite high pressures, the academic scientific work in this field concerned itself almost exclusively with the domain of approximatively atmospheric pressures. The authors present the results of some years of experimental investigations on the hydrodynamic characteristics of trickle bed reactors and lately of cocurrent upflow reactors. During the last years, results were also obtained under pressures up to 8 MPa. The measurements were made in a small scale cold flow equipment (diameter 23 mm. Different aqueous and organic more or less viscous, eventually coalescence inhibiting liquids, four gases and a number of non porous more or less wettable particles were used. The liquid holdup was determined in all cases by measuring liquid phase residence time distribution by different tracers. The following conclusions may be drawn:(a In the high interaction regime, it is the inertia of the gas and the liquid phases which is the main cause of the dissipation of mechanical energy. In this regime, results obtained in cocurrent upflow and downflow are approximately equal. (b Most correlations of literature are unable to predict the effect of pressure on the pressure drop or the liquid holdup. (c The gas viscosity has no influence on the hydrodynamics. It is therefore possible to simulate for example hydrogen under high pressure conditions by another gas of the same density (at a much lower pressures. A critical evaluation of the correlations and/or models of literature is presented, concerning their ability to represent the different characteristics as a function of pressure. Tandis que la plupart des réacteurs industriels gaz-liquide à lit de catalyseur fixe fonctionnent à assez hautes pressions, les travaux scientifiques académiques sont, dans ce domaine, presque exclusivement consacrés aux pressions avoisinant la pression atmosphérique. Les auteurs présentent les r

  19. A database system for the control of radioactive effluents generated by the IPEN-CNEN/SP installations

    International Nuclear Information System (INIS)

    Maduar, M.F.

    1992-01-01

    A PC-compatible database system has been developed in order to optimize the control of liquid and gaseous effluents generated by the installations of IPEN-CNEN/SP. The system implements source-term generation, optimizes the discharge control of the effluents and allows several ways for the retrieval of data concerning to the effluents. (author)

  20. Nuclear reactor effluent monitoring

    Energy Technology Data Exchange (ETDEWEB)

    Minns, J.L.; Essig, T.H. [Nuclear Regulatory Commission, Washington, DC (United States)

    1993-12-31

    Radiological environmental monitoring and effluent monitoring at nuclear power plants is important both for normal operations, as well as in the event of an accident. During normal operations, environmental monitoring verifies the effectiveness of in-plant measures for controlling the release of radioactive materials in the plant. Following an accident, it would be an additional mechanism for estimating doses to members of the general public. This paper identifies the U.S. Nuclear Regulatory Commission (NRC) regulatory basis for requiring radiological environmental and effluent monitoring, licensee conditions for effluent and environmental monitoring, NRC independent oversight activities, and NRC`s program results.

  1. Nuclear reactor effluent monitoring

    International Nuclear Information System (INIS)

    Minns, J.L.; Essig, T.H.

    1993-01-01

    Radiological environmental monitoring and effluent monitoring at nuclear power plants is important both for normal operations, as well as in the event of an accident. During normal operations, environmental monitoring verifies the effectiveness of in-plant measures for controlling the release of radioactive materials in the plant. Following an accident, it would be an additional mechanism for estimating doses to members of the general public. This paper identifies the U.S. Nuclear Regulatory Commission (NRC) regulatory basis for requiring radiological environmental and effluent monitoring, licensee conditions for effluent and environmental monitoring, NRC independent oversight activities, and NRC's program results

  2. Management of radioactive effluents from research Reactors and PHWRs

    International Nuclear Information System (INIS)

    Bodke, S.B.; Surender Kumar; Sinha, P.K.; Budhwar, R.K.; Raj, Kanwar

    2006-01-01

    Indian nuclear power programme is mainly based on pressurized heavy water reactors (PHWRs). In addition we have research reactors namely Apsara, CIRUS, Dhruva at Trombay. The operation and maintenance activities of these reactors generate radioactive liquid waste. These wastes require effective management so that the release of radioactivity to the environment is well within the authorized limits. India is self reliant in the design, erection, commissioning and operation of effluent management system for nuclear reactors. Segregation at source based on nature of effluents and radioactivity content is the first and foremost step in the over all management of liquid effluents. The effluents from the power reactors contain mainly activation products like 3 H. It also contains fission products like 137 Cs. Containment of these radionuclide along with 60 Co, 90 Sr, 131 I plays an important part in liquid waste management. Treatment processes for decontamination of these radionuclide include chemical treatment, ion exchange, evaporation etc. Effluents after treatment are monitored and discharged to the nearby water body after filtration and dilution. The concentrates from the processes are conditioned in cement matrix and disposed in Near Surface Disposal Facilities (NSDFs) co-located at each site. Some times large quantity of effluents with higher radioactivity concentration may get generated from the abnormal operation such as failure of heat exchangers. These effluents are handled on a campaign basis for which adequate storage capacity is provided. The treatment is given taking into consideration the required decontamination factor (DF), capacities of available treatment process, discharge limits and the availability of the dilution water. Similarly large quantities of effluents may get generated during fuel clad failure incident in reactors. In such situation, as in CIRUS large volume of effluent containing higher radioactivity are generated and are managed by delay

  3. Contribution to the study of the exchanges to the interface liquid bubble, resulting from an ejector venturi, for the treatment of dust; Contribution a l'etude des echanges a l'interface bulle liquide, issue d'un ejecteur venturi, horizontal en vue du traitement des poussieres

    Energy Technology Data Exchange (ETDEWEB)

    Giovannacci, D.

    2002-06-15

    A great number of industrial processes generate aerosols that the legislation prohibited to reject too great quantities (Decree no 98-360, 6 may 1998). Among the processes of elimination but also of recovery of these pollutants, washing by means of selective solvent is widespread. This operation is realized in contactors gas-liquid that one can classify out of absorbers with columns and absorbers venturi. Among the latter, one distinguishes the ejector venturi, the venturi high energy and the venturi with emulsion. In this work, we proposed to study the ejector venturi on the plans of hydrodynamics and transfer of matter, in the case of pollutants in the form of dust. At the time of the hydrodynamic study, we determine experimentally using fast camera the characteristics of the interface, the surface of exchange a and the diameter of the bubbles. We then could establish the law of distribution of the diameters of the bubbles. The introduction of a model of evolution in three phases of the current of bubbles enabled us to understand the evolution of the diameter during the course of the bubble and to characterize the influence of coalescence. With regard to the study of transfer of matter, we introduced a new model characterizing the trapping of dust included into bubbles. The dominating mechanism in the trapping is then with the inertial effects with the range of diameter of dust [ 2;4 ] {mu}m for which the trapping is optimum. We measured in experiments the effectiveness of trapping of the ejector, and its variations with the temperature of two effluents, the time of course and the density of the particles. The results from this study make it possible to work out a new type of particle filter, based on the technique of the ejector venturi. (author)

  4. British Nuclear Fuels plc's effluent plant services building

    International Nuclear Information System (INIS)

    Williams, L.

    1990-01-01

    The new Effluent Plant Services building (EPSB) on the Sellafield Nine Acre Site was built by Costain Engineering Limited for British Nuclear Fuels Limited. The EPSB is dedicated to a new generation of nuclear waste treatment plants, aimed at reducing discharges into the Irish Sea and other environmental impacts by removing actinides from liquid effluents and decontaminating waste solvents. This article describes the design, construction and operation of the plant. (UK)

  5. Genotoxicity of swine effluents.

    Science.gov (United States)

    Techio, V H; Stolberg, J; Kunz, A; Zanin, E; Perdomo, C C

    2011-01-01

    This study aimed at the investigation of genotoxic effects of swine effluents from different stages of a treatment system for swine wastes through bioassay of stamen hairs and micronuclei in Tradescantia (clone BNL 4430). No significant differences (p≥0.05) regarding the genic mutations were found in the bioassay of stamen hairs, independently of the effluent analysed. For the genotoxicity test with micronuclei, the plants exposed to raw wastes, to sludge, and to effluent of the biodigester have presented higher rates of chromosomal damages (micronuclei), with significant differences in relation to the control group and other effluent of the waste treatment system (p≤0.05). The association between the chemical parameters and the genotoxicity data have shown that the variables COD and TKN have presented significant correlation (p≤0.05) with the number of mutagenic events in the tetrads.

  6. Facility effluent monitoring plan for the 327 Facility

    International Nuclear Information System (INIS)

    1994-11-01

    The 327 Facility [Post-Irradiation Testing Laboratory] provides office and laboratory space for Pacific Northwest Laboratory (PNL) scientific and engineering staff conducting multidisciplinary research in the areas of post-irradiated fuels and structural materials. The facility is designed to accommodate the use of radioactive and hazardous materials in the conduct of these activities. This report summarizes the airborne emissions and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

  7. CONCAWE effluent speciation project

    Energy Technology Data Exchange (ETDEWEB)

    Leonards, P.; Comber, M.; Forbes, S.; Whale, G.; Den Haan, K.

    2010-09-15

    In preparation for the implementation of the EU REACH regulation, a project was undertaken to transfer the high-resolution analytical method for determining hydrocarbon blocks in petroleum products by comprehensive two-dimensional gas chromatography (GCxGC) to a laboratory external to the petroleum industry (Institute for Environmental Studies (IVM) of the VU University of Amsterdam). The method was validated and used for the analysis of petroleum hydrocarbons extracted from refinery effluents. The report describes the technology transfer and the approaches used to demonstrate the successful transfer and application of the GCxGC methodology from analysing petroleum products to the quantitative determination of hydrocarbon blocks in refinery effluents. The report describes all the methods used for all the determinations on the effluent samples along with an overview of the results obtained which are presented in summary tables and graphs. These data have significantly improved CONCAWE's knowledge of what refineries emit in their effluents. A total of 111 Effluent Discharge Samples from 105 CONCAWE refineries in Europe were obtained in the period June 2008 to March 2009. These effluents were analysed for metals, standard effluent parameters (including COD, BOD), oil in water, BTEX and volatile organic compounds. The hydrocarbon speciation determinations and other hydrocarbon analyses are also reported. The individual refinery analytical results are included into this report, coded as per the CONCAWE system. These data will be, individually, communicated to companies and refineries. The report demonstrates that it is feasible to conduct a research programme to investigate the fate and effects of hydrocarbon blocks present in discharged refinery effluents.

  8. Un nouveau moyen de mesure absolue du taux gazeux des mélanges gaz-liquides : le SMAC A New Absolute Measurement of the Volumetric Gas Ratio of Gas-Liquid Mixture: the Smac

    Directory of Open Access Journals (Sweden)

    Porot P.

    2006-11-01

    Full Text Available Du graphe (P, V de la compression d'un mélange gaz-liquide, on peut tirer la valeur du taux volumique de gaz dans le mélange. La vérification théorique et expérimentale de ce principe ainsi que ses limites d'application comme moyen de mesure sont présentées. Ce résultat a été utilisé pour développer un système de mesure de l'aération de l'huile moteur, le SMAC (Système de Mesure d'Aération par Compressibilité. Des exemples d'application, tels que l'étude de la sensibilité de certaines huiles à l'aération, sont exposés. Oil aeration can be a real problem in engine oil circuit. The involved lubrication power decrease and thermic properties changes can damage the engine. Furthermore, the increased compressibility is very dangerous for hydraulic systems like valve lash adjusters. A first step to control this aeration is to be able to measure it. Gammametry is often used but this measurement needs a very precise calibration and is quite complicated and dangerous. A new absolute measurement has been discovered, based on the difference of compressibility between air and oil. It is absolute because the measurement principle is independant of the conditions, The system does not need a new calibration at each new environment. It is valid for any gas-liquid mixture. From the (P, V graph of a gas-liquid mixture compression, one can derive the gas-liquid volumetric ratio. The log-log graph (P/PO, 1-V/VO of a mixture sample pressurization always shows an inflexion point. The y value of this inflexion point (1-V/VO is equal to the volumetric gas ratio of the sample (before compression. This phenomenon is obvious on hydraulic curves (see Annexe 1. To check it, we have proceeded to a theoretical demonstration and an experimental verification. The theoretical demonstration of this principle concludes that the principle is verified as long as the ration P index 0 / alpha B is small. B is the oil bulk modulus, alpha is the volumetric gas ratio

  9. Arsenic precipitation from metallurgical effluents

    International Nuclear Information System (INIS)

    Navarro, P.; Vargas, C.; Araya, E.; Martin, I.; Alguacil, F. J.

    2004-01-01

    In the mining-metallurgical companies different liquid effluents are produced, which can contain a series of dissolved elements that are considered dangerous from an environmental point of view. One of these elements is the arsenic, especially in the state of oxidation +5 that can be precipitated as calcium or iron arsenate. To fulfil the environmental requests it should have in solution a content of arsenic lower than 0,5 mg/l and the obtained solid product should be very stable under the condition in which it will be stored. this work looks for the best conditions of arsenic precipitation, until achieving contents in solution lower than such mentioned concentration. Also, the stability of the precipitates was studied. (Author) 7 refs

  10. Decision no 2009-DC-0155 of the 15. of September 2009 by the Nuclear Safety Authority specifying the limits of releases in the environment of liquid and gaseous effluents of base nuclear installations n. 18, 35, 40, 49, 50, 72, 77 and 101 operated by the Atomic Energy Commissariat (CEA) in its Saclay Centre, located on the districts of Saclay, Saint-Aubin and Villiers-le-Bacle (Essonne department)

    International Nuclear Information System (INIS)

    2009-01-01

    This document contains references to the different legal and official documents (codes, orders, minister's opinion, public surveys, administrative authorizations, local community opinion) at the root of this specification of limits related to releases in the environment of liquid and gaseous effluents of base nuclear installations of the Saclay Centre operated by the Atomic Energy Commissariat (CEA). Tables present the limits for different radioactive emissions (carbon 14, hydrogen 3, iodine, radioactive rare earths, and other alpha, beta and gamma emitters) from these different installations, but also the maximum admitted concentrations for gaseous chemical effluents (HCl, HF, NOx, CO, and so on), as well as limits for thermal releases

  11. Épuration des eaux usées des villes pour soutenir l'agriculture ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    2 févr. 2011 ... Les eaux usées : manne liquide ? ... Les racines de la plante emprisonnent les matières solides en ... le compostage des déchets ménagers ou l'arrosage des pépinières. ... à la gestion locale de la demande », dans Épuration des eaux usées et l'agriculture urbaine, Editions Enda, Dakar, août 2002. Mbodj ...

  12. Discharge of radionuclides in liquid effluent

    International Nuclear Information System (INIS)

    Duggleby, J.C.

    1985-01-01

    One of the aims of the Radiation Health Committee of the National Health and Medical Research Council, through Council recommendations, is to achieve some degree of uniformity in State legislation applied to the public health aspects of radiation. In developing the recommendation on the discharge of radionuclides to sewerage systems the Committee made use of the comparatively new concept of the Annual Limit on Intake (ALI)

  13. Chromium removal from tanning industries effluents

    International Nuclear Information System (INIS)

    Chaudry, M.A.; Ahmad, S.

    1997-01-01

    Air and water are the basic needs of human being and other living entities on the earth. Tanning industry uses water and some chemicals and so creates environmental problems, depending basically on two principal sources, hide and water. The processes of tanning are based on chromium sulphate and vegetable treatment of hide. According to the national environmental quality standards (NEQS) the effluent or disposed water should contain phenol less than 0.5 ppm, Cr, sulphates, chloride and other salts content. About 30-40 liters of water are used to process one Kg of raw hide into finished goods. Total installed capacity of hides and skins chrome tanning is 53.5 million square meter, earning a large amount of foreign exchange for our country. In the present work, seven tanning industries effluents from the suburbs of Multan city have been collected and analysed. The pH of the liquors have been found to vary from 2.72 to 4.4 and the constituent Cr have been found to be from zero to 8000 ppm from vegetable to chrome tanning industrial effluents studied. The stages involved in tanning and treatment of the effluent water waste including chemical treatment of Cr has been described with a special reference to supported liquid membranes process for removal of chromium ions. (author)

  14. Theoretical and Experimental Aspects of Quenching Variables from Biomedical Samples in Liquid Scintillator Systems; Aspects Theoriques et Experimentaux des Parametres d'Extinction Etudies sur des Echantillons Biomedicaux dans des Systemes a Scintillateur Liquide; Teoreticheskie i ehksperimental'nye aspekty peremennykh gasheniya iz biomeditsinskikh prob v zhidkikh stsintillyatsionnykh sistemakh; Estudio Teorico y Experimental de las Variables de Extincion en el Recuento de Sustancias Biological por Centelleo Liquido

    Energy Technology Data Exchange (ETDEWEB)

    Ross, H. H. [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    1965-10-15

    with the desired isotope. The photons emitted by the standard have the same fluorescence intensity and spectral distribution as those produced in the sample itself. After construction, the isolated internal standard is immersed in a pure liquid scintillator solution and counted. A second count is made with the standard immersed in a sample that exhibits colour quenching. The ratio of these two counts is a measure of the colour quenching in the sample and is unaffected by the presence of fluorescence quenching species. Because this method is straightforward in principle and easy to use, it is ideally suited to routine investigations. The individual quenching effects of various sample systems were evaluated by both correction methods. Specially prepared solutions of dyes and samples of urine, blood, and liver tissue were studied extensively. The results show that the agreement between the two methods is excellent. Also, the quenching effects of most of the urine, blood and liver samples could be determined to {+-}3%. (author) [French] Pendant tres longtemps il a ete impossible de separer les parametres d'extinction dans les systemes a scintillation liquide. Certes, les methodes classiques de correction permettent de determiner l'extinction totale dans un echantillon donne, mais il est impossible de determiner separement l'extinction de la couleur et celle de la fluorescence. Or, ces donnees seraient precieuses pour la conception d'ensembles a scintillation nouveaux et plus perfectionnes et pour l'evaluation critique des appareils actuels en vue de leur amelioration. L'auteur a mis au point deux methodes distinctes pour evaluer separement les parametres d'extinction dans les systemes liquides. La premiere methode permet d'utiliser un modele mathematique general pour predire avec precision le degre d'extinction chromatique dans tout echantillon, en partant de donnees spectro- photometriques. Ce traitement est analogue a celui que l'on utilise pour determiner l

  15. Potentiel et limites d'utilisation, aux températures élevées, des lubrifiants liquides dans les moteurs Potential and Limitations of Use of Liquid Lubricants in Engines At High Temperatures

    Directory of Open Access Journals (Sweden)

    Toulhoat H.

    2006-11-01

    Full Text Available Cet article examine les possibilités de réponse de la formulation des lubrifiants à une élévation des températures dans les moteurs automobiles de la prochaine décennie; l'accroissement des puissances spécifiques des moteurs, et la réduction de leurs dimensions et de leur poids, la pénétration des turbo-compresseurs et des pots catalytiques, et dans une certaine mesure la tendance à réduire les rejets thermiques à l'échappement, sont des forces motrices pour cette évolution. Une augmentation de la température moyenne à la rampe d'environ 15 à 20°C est attendue pour la plupart des moteurs courants, à essence ou Diesel. Les températures en fond de gorge de segment de feu resteront très probablement dans l'intervalle actuel 250-260°C grâce aux systèmes de refroidissement des pistons. L'évolution des moteurs Diesel de camions dans les cinq dernières années est significative de cette tendance. Une telle évolution n'induira pas de bouleversements majeurs dans la formulation des lubrifiants pour automobiles. Cependant, elle déterminera une demande en VI significativement accrue de façon à maintenir les conditions de la lubrification hydrodynamique aux paliers, aussi bien que le comportement au démarrage à froid. Ceci sera obtenu par une meilleure combinaison des bases, avec une mise en oeuvre accrue des bases hydrotraitées et synthétiques, et un renforcement de l'additivation en épaississants ( règle du pouce: 0. 25 % par incrément de 1°C de température moyenne. Une alternative pourrait provenir de progrès réalisés sur le comportement visco-élastique et la stabilité sous cisaillement de ces polymères additifs de viscosité. Une autre exigence sur les propriétés des lubrifiants afin de faire face à cet accroissement apparemment marginal de température de fonctionnement, sera une meilleure résistance à l'oxydation, et dans cette optique, le recours aux bases non conventionnelles sera à nouveau

  16. Voltametric study of formic and dihydroxy malonic acids on platinum for the definition of a process for the electrolytic destruction of carboxylic acids in radioactive aqueous effluents; Etude voltamperometrique des acides formiques et dihydroxymalonique sur platine en vue de la definition d`un procede de destruction electrolytique d`acides carboxyliques d`effluents aqueux radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Le Naour, C.

    1994-05-01

    To limit the amount of nuclear glasses generated by the treatment of the degraded solvent from the PUREX process for reprocessing of nuclear fuels, by solutions of sodium carbonate and caustic soda, it is planned to exploit the complexing power of certain carboxylic acids to return the metallic cations to the aqueous phase. The concept of this new treatment of the solvent by `substitution` reagents demands a process for the decomposition of these reagents, especially to CO{sub 2}. The investigation of the electrochemical behaviour, on platinum, of a substance selected as a model for understanding the interfacial mechanisms (HCOOH), and of dihydroxy malonic acid, revealed two distinct electro-poisoning processes: one is due to the adsorption of CO on the surface sites of platinum, and the second to the formation of a passivating layer of P{dagger}O. The application of 20 kHz ultrasonic flux in the neighbourhood of the platinum / aqueous formic acid solution interface also appears to cause a change in the superficial structure of the electrode used, in a direction that favours the decomposition of this compound. To overcome problems of poisoning of the platinum surface, aqueous solutions of formic, dihydroxy malonic and oxalic acids were electrolysed, in a cell without diaphragm, by applying voltage and current ranges, at levels adapted to each of the species. It is necessary to bring the working electrode to a higher potential than the oxidation potential for formic acid, and to a lower potential for dihydroxy malonic and oxalic acids. The frequent modifications of the electrode potentials helped to achieve quantitative destruction of these species, to CO{sub 2} (and to water) with an electrochemical efficiency approaching 100 %. This wet oxidation process also offers the advantage of not raising the energy potential of the effluents to be treated, because it takes place in mild conditions (ambient temperature and pressure). (author). 131 refs., 90 figs., 48 tabs.

  17. Influence of extranuclear fields on angular correlations; Influence des champs extranucleaires sur les correlations angulaires

    Energy Technology Data Exchange (ETDEWEB)

    Abragam, A [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    A general formalism is given for the description of the perturbation of angular correlations by extranuclear fields. An application is made to the case of static interactions in solids and time dependent interactions in liquids. (author) [French] On donne un formalisme general pour la description de la perturbation des correlations angulaires par des champs extranucleaires. Ce formalisme est applique aux cas des interactions statiques dans les solides et des interactions dependantes du temps dans les liquides. (auteur)

  18. Richards Bay effluent pipeline

    CSIR Research Space (South Africa)

    Lord, DA

    1986-07-01

    Full Text Available of major concern identified in the effluent are the large volume of byproduct calcium sulphate (phosphogypsum) which would smother marine life, high concentrations of fluoride highly toxic to marine life, heavy metals, chlorinated organic material... ........................ 9 THE RICHARDS BAY PIPELINE ........................................ 16 Environmental considerations ................................... 16 - Phosphogypsum disposal ................................... 16 - Effects of fluoride on locally occurring...

  19. Ion exchange for treatment of industrial effluents

    International Nuclear Information System (INIS)

    Moreno Daudinot, Aurora Maria; Ge Leyva, Midalis

    2016-01-01

    The acid leaching and ammoniacal carbonate technologies of laterite respectively, are responsible for the low quality of life of the local population, the big deforested areas due to the mining tilling, the elevated contents of solids in the air and waters, as well as the chemical contamination by metals presence, the acidity or basicity of the effluents of both industries, that arrive through the river and the bay to aquifer's mantle. The ion exchange resins allow ions separation contained in low concentrations in the solutions, where the separation of these elements for solvents, extraction or another chemical methods would be costly. Technological variants are proposed in order to reduce the impact produced on the flora and the fauna, by the liquid effluents of nickel industry, by means of ion exchange resins introduction as well as the recuperation of metals and their re incorporation to the productive process. (Author)

  20. Decision no 2009-DC-0156 of the 15. of September 2009 by the Nuclear Safety Authority specifying instructions related to modalities of water sampling and consumption, and of release in the environment of liquid and gaseous effluents from the base nuclear installations n. 18, 35, 40, 49, 50, 72, 77 and 101 operated by the Atomic Energy Commissariat (CEA) in its Saclay Centre, located on the districts of Saclay, Saint-Aubin and Villiers-le-Bacle (Essonne department)

    International Nuclear Information System (INIS)

    2009-01-01

    After references to the different legal and official documents (codes, orders, minister's opinion, public surveys, administrative authorizations, local community opinion), this document specifies the instructions related to modalities of water sampling and consumption, and of release in the environment of liquid and gaseous effluents from some specific base nuclear installations. These instructions and provisions concern the general means implemented by the operator, records, the control by authorities, the limits of water sampling and consumption, the water sampling process, the sampling works and their maintenance and control, the release of liquid, gaseous and radioactive effluents, their control and their transfer, the limit values for different compounds and species, the control of environment around the site, the information of authorities and of population

  1. Decision no 2010-DC-0189 by the Nuclear Safety Authority on the 7. of July 2010 specifying to Electricite de France-Societe Anonyme (EDF-SA) instructions related to modalities of water sampling and consumption, and of release in the environment of liquid and gaseous effluents for the operation of the Flamanville 1 (IBN n 108), Flamanville 2 (INB n 109) and Flamanville 3 (INB n 167) reactors

    International Nuclear Information System (INIS)

    2010-01-01

    After references to the different legal and official documents (codes, orders, minister's opinion, public surveys, administrative authorizations, local community opinion), this document specifies the instructions related to modalities of water sampling and consumption, and of release in the environment of liquid and gaseous effluents from three nuclear reactors. These instructions and provisions concern the general means implemented by the operator, records, the control by authorities, the limits of water sampling and consumption, the water sampling process, the sampling works and their maintenance and control, the release of liquid, gaseous and radioactive effluents, their control, the control of the environment (air, soil, surface and underground water, sampling point implantation), the information of authorities and of population

  2. Order of the 15. of September 2010 approving the decision no 2010-DC-0188 by the Nuclear Safety Authority on the 7. of July 2010 specifying to Electricite de France-Societe Anonyme (EDF-SA) the limits of releases in the environment of liquid and gaseous effluents for the operation of Flamanville 1 (INB n 108), Flamanville 2 (INB n 109) and Flamanville 3 (INB n 167) reactors

    International Nuclear Information System (INIS)

    2010-01-01

    This legal publication contains references to the different legal and official documents (codes, orders, minister's opinion, public surveys, administrative authorizations, local community opinion) at the root of this specification of limits related to releases in the environment of liquid and gaseous effluents by the three Flamanville nuclear reactors operated by Electricite de France-Societe Anonyme (EDF-SA). Tables present the limits for different gaseous and liquid radioactive emissions (carbon 14, hydrogen 3, iodine, radioactive rare earths, and other beta and gamma emitters) from these different installations, but also the maximum admitted concentrations for gaseous chemical effluents (boric acid, hydrazine hydrate, morpholine, phosphates, nitrates, various metals, and so on). The limits for thermal releases are also specified

  3. Dynamique de structuration spatio-temporelle des populations de ...

    African Journals Online (AJOL)

    Dynamique de structuration spatio-temporelle des populations de familles de macroinvertébrés dans un continuum lac de barrage-effluent-fleuve issu de périmètre irrigué. Bassin de la Volta (Burkina Faso)

  4. Detoxification of kraft pulp ECF bleaching effluents by catalytic hydrotreatment.

    Science.gov (United States)

    Calvo, L; Gilarranz, M A; Casas, J A; Mohedano, A F; Rodríguez, J J

    2007-02-01

    Two different effluents from the D(1) and E(1) stages of the ECF bleaching of Eucalyptus globulus kraft pulp were treated by catalytic hydrogenation in a trickle bed reactor using commercial and homemade Pd/AC catalysts. The reactor was fed with the bleaching effluent and a H(2)/N(2) gas stream. The variables studied were space-time (1.4-5g(cat)min/mL), gas to liquid flow ratio (286-1000vol.), gas feed concentration (H(2):N(2), 1:1-1:7.3vol.), temperature (25-100 degrees C) and pressure (1-11bar). Hydrotreatment performance was evaluated in terms of ecotoxicity, adsorbable organic halogen (AOX), chemical oxygen demand (COD), biological oxygen demand (BOD(5)) and colour removal. In all the runs, the ecotoxicity of the effluents decreased as a result of the treatment, achieving reductions that ranged from 70% to 98%. Simultaneously to the reduction of toxicity, the hydrotreatment led to a decrease of the colour of the effluents, being the decrease significantly higher in the case of E(1) effluent. The AOX content was reduced by 85% and 23% for E(1) and D(1) effluents, respectively. In the case of D(1) effluent the removal of ecotoxicity was significantly higher than that of AOX, which indicates that much of the toxicity of the effluent must be associated to non-chlorinated organics. In spite of the important reduction of ecotoxicity, the biodegradability of the effluents only increased slightly. The homemade catalysts, prepared from activated carbons with a high external or non-microporous surface area and mesopore volume and a convenient surface chemistry showed a higher efficiency than the commercial one.

  5. Facility Effluent Monitoring Plan for the N Reactor

    International Nuclear Information System (INIS)

    Watson, D.J.; Brendel, D.F.; Shields, K.D.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP- 0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The primary purpose of the N Reactor Facility Effluent Monitoring Plan (FEMP), during standby, is to ensure that the radioactive effluents are properly monitored and evaluated for compliance with the applicable DOE orders and regulatory agencies at the federal, state, and local levels. A secondary purpose of the FEMP is to ensure that hazardous wastes are not released, in liquid effluents, to the environment even though the potential to do so is extremely low. The FEMP is to provide a monitoring system that collects representative samples in accordance with industry standards, performs analyses within stringent quality control (QC) requirements, and evaluates the data through the use of comparative analysis with the standards and acceptable environmental models

  6. Chemical and microbiological water quality of subsurface agricultural drains during a field trial of liquid dairy manure effluent application rate and varying tillage practices, Upper Tiffin Watershed, southeastern Michigan

    Science.gov (United States)

    Haack, Sheridan Kidd; Duris, Joseph W.

    2008-01-01

    A field trial was done in the Upper Tiffin River Watershed, in southeastern Michigan, to determine the influence of liquid dairy manure effluent (LDME) management practices on the quality of agricultural subsurface-drain water. Samples from subsurface drains were analyzed for nutrients, fecal-coliform and Escherichia coli (E. coli) bacteria, antibiotics, chemicals typically detected in wastewater, and the occurrence of genes indicating the presence of shiga-toxin-producing E. coli, or of bovine-specific Bacteroidetes bacteria. Samples were collected from November 2, 2006, to March 20, 2007, from eight subsurface drains under field plots that received no LDME and no tillage (controls) or received 4,000 or 8,000 gallons per acre (gal/acre) of LDME and either no tillage or two different types of tillage. The two types of tillage tested were (1) ground-driven, rotary, subsurface cultivation and (2) rolling-tine aeration. Samples were collected before LDME application and at 4 hours, and 1, 2, 6, 7, and 14 days post-application. Nutrient concentrations were high in subsurface-drain water throughout the field-trial period and could not be attributed to the field-trial LDME application. Of the 59 drain-water samples, including those collected before LDME application and control samples for each date, 56 had concentrations greater than the U.S. Environmental Protection Agency (USEPA), Ecoregion VI recommended surface-water criterion for total phosphorus, and all samples had concentrations greater than the recommended total nitrogen criterion. Nitrate + nitrite nitrogen concentration exceeded 20 milligrams per liter for every sample and contributed most to the total nitrogen concentrations. Substantial increases in drain-water concentrations of organic and ammonia nitrogen and total phosphorus were found for all treatments, including controls, at 14 days post-application after 0.84 inch of rainfall over 2 days. E. coli concentrations exceeded the USEPA recreational

  7. Nuclear plant refurbishment calls for patience. [Construction of radioactive effluent plant

    Energy Technology Data Exchange (ETDEWEB)

    Henly, Anna

    1989-08-01

    All nuclear power plants produce a small quantity of liquid effluent from wash hand basins, showers and surface drains on the site. The effluent is termed low-level radioactive waste and under the 'Radioactive Substances Act' can be discharged into estuaries or the sea. Before a controlled discharge can be made the effluent has to be chemically treated and have any radioactive particulate matter removed. The replacing of the radioactive effluent plant at the Berkeley nuclear power station in the United Kingdom is described, with particular reference to the vigorous safety standards and quality assurance programme operated by the Central Electricity Generating Board. (author).

  8. Palisades Nuclear Plant. Radioactive effluents and environmental monitoring sections to second annual operating report

    International Nuclear Information System (INIS)

    1977-01-01

    A total of 0.435 Ci of radioactive liquid effluent less tritium was released with 19.63 Ci of tritium. Both liquid and gaseous releases were within permissible limits. There were 8 Ci of solid wastes stored on the site as of 12/31/76. Data clearly shows there was no detectable increase in radioactivity levels in the environmental media that can be attributed to plant effluents. Monitoring reports are presented concerning fish, meteorology, noise, and cooling tower drift

  9. Liquid Scintillation Detection of Tritium and other Radioisotopes in Insoluble or Quenching Organic Samples; Detection par compteur a scintillations a liquides du tritium et des autres radioelements contenus dans des echantillons organiques insolubles ou coupeurs; Obnaruzhenie tritiya metodom zhidkostnoj stsintillyatsii v nerastvorimykh ili sposo'nykh gasit' izluchenie organicheskikh o'raztsakh; Deteccion del tritio u otros radioisotopos por centelleo liquido en muestras organicas insolubles o que provocan extincion

    Energy Technology Data Exchange (ETDEWEB)

    Eastham, J F; Westbrook, H L; Gonzales, D [University of Tennessee, Knoxville, TN (United States)

    1962-01-15

    To facilitate a study of the H{sup 1}/H{sup 3} isotope effect in the reduction of organic compounds, it has been necessary to develop procedures to overcome the two major limitations of the most convenient general method of radioassaying organic material, liquid scintillation counting. These limitations, which are scintillation-quenching by many organic samples and limited solubility of others, are particularly common with material of biological significance: The procedures developed involve combustion of the sample wrapped in filter paper in art oxygen-filled flask, formation of a solution of the combustion products in a suitable solvent added to the flask before combustion, and scintillation-counting of the solution. Advantages of the developed, procedures, in addition to overcoming the indicated limitations, include efficacy with samples with a great range of activity (some as low as 1{mu}c/mole), good precision (as great as any other general method of radio-assaying H{sup 3}), and applicability to other soft beta emitters (C{sup 14} and S{sup 35}). With a scintillation spectrometer and the techniques developed, samples triply labelled with H{sup 3}, C{sup 14} and S{sup 35} can be differentially radio assayed. Details of the solvent systems and techniques developed are reported. Analytical results are reported for such quenching material as 2.4-dinitrophenyl-hydrazones dyes and for such insoluble materials as proteins and carbohydrates. Application of the techniques to evaluation of H{sup 1}/H{sup 3} isotope effects in certain reduction reactions are discussed. (author) [French] Pour faciliter l'etude de l'effet isotopique ''1H/''3H dans la reduction des composes organiques, il a fallu mettre au point des procedes permettant d'elargir le champ d'application de la methode generale la plus pratique de radioanalyse des matieres organiques, savoir l'analyse au moyen d'un compteur a scintillations a liquides. En effet, ce champ d'application est limite pour deux

  10. Effluent management practices at the AAEC Research Establishment

    International Nuclear Information System (INIS)

    Khoe, G.

    1978-02-01

    A technical description is given of the facilities and operation of the waste water and liquid waste management system at the Australian Atomic Energy Commission Research Establishment at Lucas Heights. Also described are practices and principles involved in the control and recording of radioactivity in the effluents. (Author)

  11. Facility effluent monitoring plan for the 300 Area Fuels Fabrication Facility

    International Nuclear Information System (INIS)

    Nickels, J.M.; Brendel, D.F.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP- 0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring system by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The Fuel Fabrication Facility in the Hanford 300 Area supported the production reactors from the 1940's until they were shut down in 1987. Prior to 1987 the Fuel Fabrication Facility released both airborne and liquid radioactive effluents. In January 1987 the emission of airborne radioactive effluents ceased with the shutdown of the fuels facility. The release of liquid radioactive effluents have continued although decreasing significantly from 1987 to 1990

  12. Zero effluent; Efluente zero

    Energy Technology Data Exchange (ETDEWEB)

    Monteiro, Silvio Rogerio; Santos, Angelo Francisco dos [Liquigas Distribuidora S.A., Sao Paulo, SP (Brazil)

    2008-07-01

    A scenery of water shortage and the search for profitability improvement obligate the companies to exercise their creativity and to adopt alternative methods to the conventional ones to preserve the environmental resources. The 'Effluent Zero' project comes from a paradigms changing that the environmental preservation is a necessary cost. It brings a new analysis approach of this problem with the purpose to adapt the investments and operational costs with the effluents treatment to the demands of the productive processes. In Liquigas, the project brought significant results; made a potential reduction of nearly 90% in the investments of the effluents treatment systems. That means nearly 13% in reduction in the total investments in modernization and upgrade of the existents companies installations and of 1,6% in the total operational costs of the Company. Further more, it has contributed for a reduction of until 43% of the water consumption in the bottling process of the Liquefied Petroleum Gas (LPG). This way, the project resulted in effective actions of environmental protection with relevant economic benefits. (author)

  13. A history of effluent releases from the Texas A and M University reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bates, E F; Neff, R D; Sandel, P S; Schoenbucher, B [Texas A and M University (United States)

    1974-07-01

    Since 1966 records of radioactive effluents releases from the Texas A and M University Research Reactor have been compiled. These data include particulate activity, noble gases, and liquid effluent releases. Particulate activity releases with half-lives greater than eight days were negligible and are not included in this presentation. Conversion from an MTR plate reactor to a TRIGA fueled reactor was completed in August 1968. Records of effluent releases of Argon-4l and liquids for the past, five years are summarized, in this presentation. These release data are compared to the current limits specified: in 10 CPR 20 and the limits appearing in proposed Appendix.

  14. Silver precipitation from electrolytic effluents

    International Nuclear Information System (INIS)

    Rivera, I.; Patino, F.; Cruells, M.; Roca, A.; Vinals, J.

    2004-01-01

    The recovery of silver contained in electrolytic effluents is attractive due to its high economic value. These effluents are considered toxic wastes and it is not possible to dump them directly without any detoxification process. One of the most important way for silver recovery is the precipitation with sodium ditionite, sodium borohidride or hydrazine monohidrate. In this work, the most significant aspects related to the use of these reagents is presented. Results of silver precipitation with sodium ditionite from effluents containing thiosulfate without previous elimination of other species are also presented. silver concentration in the final effluents w <1 ppm. (Author) 15 refs

  15. ANCCLI Scientific Committee - Opinion related to the modification request for the authorisation of water takings and releases of liquid and gaseous effluents of the Cruas-Meysse CNPE made by EDF under Article 26 of Decree nr 2007-1557 of the 2 November 2007. Study performed at the request of the Cruas-Meysse CLI

    International Nuclear Information System (INIS)

    2012-01-01

    This report first makes some comments on modification requests made by the operator (EDF) and on the related prescription projects. Five modifications have been proposed: 1) the implementation of an anti-tartar treatment for condenser cooling circuits by continuous acid vaccination and by complementary point acid injection, 2) the implementation of a treatment against biofouling and pathogen micro-organisms in condenser cooling circuits by massive chlorination under controlled pH, 3) the evolution of the secondary circuit chemical conditioning with the implementation of an 'intermediate pH'-type conditioning and/or an ethanolamine-based conditioning, 4) the taking of head-race channel dredging and pumping station de-silting operations into account, 5) other modifications related to effluent release authorisations (tritium volume activity in tanks, low limit of Rhone flow rate for the release of liquid radioactive effluents, limits of copper and zinc releases due to condenser wear). Some comments are then made about the monitoring of the environment, and about some prescription projects which are beyond the operator's request regarding release limits and the follow-up procedure related to the modification of release authorisations

  16. Volatile liquid storage system

    International Nuclear Information System (INIS)

    Laverman, R.J.; Winters, P.J.; Rinehart, J.K.

    1992-01-01

    This patent describes a method of collecting and abating emission from a volatile liquid in an above ground storage tank. It comprises the liquid storage tank having a bottom, a vertical cylindrical circular wall having a lower edge portion joined to the bottom, and an external fixed roof, the tank having an internal floating roof floating on a volatile liquid stored in the tank, and air vent means in the tank in communication with a vapor space in the tank constituting at least the space above the floating roof when the floating roof floats on a predetermined maximum volume of volatile liquid in the tank; permitting ambient air; pumping emission laden air from the tank vapor space above the floating roof; and by means of the emissions abatement apparatus eliminating most of the emission from the emissions laden air with formation of a gaseous effluent and then discharging the resulting gaseous effluent to the atmosphere

  17. The use of magnetite for decontaminating alpha containing effluents

    International Nuclear Information System (INIS)

    Ivens, R.

    1988-06-01

    The feasibility of retention of precipitated magnetite by magnetic filtration followed by direct cementation offered an attractive alternative to conventional ferric hydroxide treatment of radioactive liquid effluents. The magnetically-assisted dewatering of laboratory-prepared magnetite was examined in a number of ways, none of which achieved the desired optimum solids content for cementation. Attempts to prepare magnetite in situ from typical effluents containing iron were unsuccessful owing to the presence of interfering ions. Preformed magnetite was reasonably effective at absorbing actinides from solution but did not appear to offer any significant advantage over ferric hydroxide. (author)

  18. Cleanup Verification Package for the 116-K-2 Effluent Trench

    International Nuclear Information System (INIS)

    Capron, J.M.

    2006-01-01

    This cleanup verification package documents completion of remedial action for the 116-K-2 effluent trench, also referred to as the 116-K-2 mile-long trench and the 116-K-2 site. During its period of operation, the 116-K-2 site was used to dispose of cooling water effluent from the 105-KE and 105-KW Reactors by percolation into the soil. This site also received mixed liquid wastes from the 105-KW and 105-KE fuel storage basins, reactor floor drains, and miscellaneous decontamination activities

  19. Treating radioactive effluent

    International Nuclear Information System (INIS)

    Kirkham, I.A.

    1981-01-01

    In the treatment of radioactive effluent it is known to produce a floc being a suspension of precipitates carrying radioactive species in a mother liquor containing dissolved non-radioactive salts. It is also known and accepted practice to encapsulate the floc in a solid matrix by treatment with bitumen, cement and the like. In the present invention the floc is washed with water prior to encapsulation in the solid matrix whereby to displace the mother liquor containing the dissolved non-radioactive salts. This serves to reduce the final amount of solidified radioactive waste with consequent advantages in the storage and disposal thereof. (author)

  20. Decentralised wastewater treatment effluent fertigation: preliminary ...

    African Journals Online (AJOL)

    Decentralised wastewater treatment effluent fertigation: preliminary technical assessment. ... living in informal settlements with the effluent produced being used on agricultural land. ... Banana and taro required 3 514 mm of irrigation effluent.

  1. Epuration des effluents industriels par électroflottation Belkacem ...

    African Journals Online (AJOL)

    étudié la séparation de quelques métaux lourds tels que le fer, le nickel, ... the separation of some heavy metals such as iron, nickel, copper, zinc, lead and ... généralement basées sur l'adsorption (par ... Différents essais de concentration en.

  2. Decision no 2010-DC-0182 by the Nuclear Safety Authority on the 18. of May 2010 specifying the limits of releases in the environment of liquid and gaseous effluents of civil base nuclear installations no 46, no 74 and no 100 operated by Electricite de France-Societe Anonyme (EDF-SA) on the district of Saint-Laurent-Nouan (Loir-et-Cher department)

    International Nuclear Information System (INIS)

    2010-01-01

    This document contains references to the different legal and official documents (codes, orders, minister's opinion, public surveys, administrative authorizations, local community opinion) at the root of this specification of limits related to releases in the environment of liquid and gaseous effluents of civil base nuclear installations operated by Electricite de France-Societe Anonyme (EDF-SA) on the district of Saint-Laurent-Nouan. Commented tables in appendix present the limits for different radioactive emissions (carbon 14, hydrogen 3, iodine, radioactive rare earths, and other alpha, beta and gamma emitters) from these different installations, but also the maximum admitted concentrations for gaseous chemical effluents (boric acid, hydrazine, morpholine, phosphates, nitrates, various metals, and so on). The limits for thermal releases are also specified

  3. Order of the 17. of June 2010 approving the decision no 2010-DC-0182 by the Nuclear Safety Authority on the 18. of May 2010 specifying the limits of releases in the environment of liquid and gaseous effluents of civil base nuclear installations no 46, 74 and 100 operated by Electricite de France-Societe Anonyme (EDF-SA) on the district of Saint-Laurent-Nouan (Loir-et-Cher department)

    International Nuclear Information System (INIS)

    2010-01-01

    This legal publication contains references to the different legal and official documents (codes, orders, minister's opinion, public surveys, administrative authorizations, local community opinion) at the root of this specification of limits related to releases in the environment of liquid and gaseous effluents of civil base nuclear installations operated by Electricite de France-Societe Anonyme (EDF-SA) on the district of Saint-Laurent-Nouan. Tables present the limits for different radioactive emissions (carbon 14, hydrogen 3, iodine, radioactive rare earths, and other alpha, beta and gamma emitters) from these different installations, but also the maximum admitted concentrations for gaseous chemical effluents (boric acid, hydrazine, morpholine, phosphates, nitrates, various metals, and so on). The limits for thermal releases are also specified

  4. ANALYSE DES PERCEPTIONS LOCALES ET DES FACTEURS ...

    African Journals Online (AJOL)

    AISA

    1Faculté des Sciences Agronomiques (FSA), Université d'Abomey-Calavi (UAC), 01 BP 526 Cotonou Bénin. Email : cgbemavo@yahoo.fr. 2Institut National des Recherches Agricoles du Bénin, Centre de Recherches Agricoles d'Agonkanmey (CRA-A),. Laboratoire des Sciences du Sol, Eau et Environnement (LSSEE).

  5. Liquid aerosol filtration by fibrous filters in interception and inertial regimes; Filtration des aerosols liquides par les filtres a fibres en regimes d`interception et d`inertie

    Energy Technology Data Exchange (ETDEWEB)

    Gougeon, R

    1994-09-26

    In most previous studies of aerosol filtration, attention is focused on the maximum penetrating particle size region where the predominant mechanisms for collection are brownian diffusion and interception. In contrary the inertial regime remains poorly understood. Therefore, the aim of this study was to improve understanding of the behaviour of fibrous filters with liquid aerosols ar high frontal velocities both in the stationary and nonstationary filtration. Stationary filtration is first investigated. Experiments are done with special filters called `formettes` which have well defined structural characteristics. Precise results obtained with those filters allow us to select two relations quoted in the literature in order to describe the diffusion and the interception and to determine an empirical correlation describing the inertial impaction. Then this correlation with an industrial filter. In the second part, the evolution of the performances of fibrous filters loaded with liquid aerosols is studied experimentally and theoretically. We show that, in the inertial regime the filter efficiency first decreases and then increases rapidly with the loading rate. This increase is particularly important at high frontal velocities and with big particles. Macroscopic observations of high loaded filters show that the liquid is located in the fibre`s intersections to form big flat surfaces. A tentative of describing the evolution of the filter efficiency in modifying our stationary filtration model in order to take into account those liquid surfaces in the filter gives encouraging results. (authors). 92 refs., 93 figs., 11 tabs., 4 appends.

  6. Simulation of complete neutron scattering experiments: from model systems to liquid germanium; Simulation complete d'une experience de diffusion de neutrons: des systemes modeles au germanium liquide

    Energy Technology Data Exchange (ETDEWEB)

    Hugouvieux, V

    2004-11-15

    In this thesis, both theoretical and experimental studies of liquids are done. Neutron scattering enables structural and dynamical properties of liquids to be investigated. On the theoretical side, molecular dynamics simulations are of great interest since they give positions and velocities of the atoms and the forces acting on each of them. They also enable spatial and temporal correlations to be computed and these quantities are also available from neutron scattering experiments. Consequently, the comparison can be made between results from molecular dynamics simulations and from neutron scattering experiments, in order to improve our understanding of the structure and dynamics of liquids. However, since extracting reliable data from a neutron scattering experiment is difficult, we propose to simulate the experiment as a whole, including both instrument and sample, in order to gain understanding and to evaluate the impact of the different parasitic contributions (absorption, multiple scattering associated with elastic and inelastic scattering, instrument resolution). This approach, in which the sample is described by its structure and dynamics as computed from molecular dynamics simulations, is presented and tested on isotropic model systems. Then liquid germanium is investigated by inelastic neutron scattering and both classical and ab initio molecular dynamics simulations. This enables us to simulate the experiment we performed and to evaluate the influence of the contributions from the instrument and from the sample on the detected signal. (author)

  7. Rework of process effluents from the fabrication of HTR fuel

    Energy Technology Data Exchange (ETDEWEB)

    Lasberg, Ingo; Braehler, Georg [NUKEM Technologies GmbH (Germany); Boyes, David [Pebble Bed Modular Reactor (Pty) Ltd., Centurion (South Africa)

    2008-07-01

    HTR fuel facilities require the application of several liquid chemicals and accordingly they produce significant amounts of Uranium contaminated/potentially contaminated effluents. The main effluents are (amounts for a 3 t Uranium/a plant): aqueous solutions including tetrahydrofurfuryl alcohol THFA, ammonium hydroxide NH4OH, and ammonium nitrate NH4NO3 (180 m{sup 3}/a), isopropanol IPA/water mixtures (130 m{sup 3}/a); Non-Process Water NPW (300 m{sup 3}/a); methanol (7m{sup 3}/a); additionally off-gas streams, containing ammonia (9 t/a) have to be treated. In an industrial scale facility all such effluents/gases need to be processed for recycling, decontamination prior to release to the environment (as waste or as valuable material). Thermal decomposition is applied to dispose of burnable residues.

  8. Rework of process effluents from the fabrication of HTR fuel

    International Nuclear Information System (INIS)

    Lasberg, Ingo; Braehler, Georg; Boyes, David

    2008-01-01

    HTR fuel facilities require the application of several liquid chemicals and accordingly they produce significant amounts of Uranium contaminated/potentially contaminated effluents. The main effluents are (amounts for a 3 t Uranium/a plant): aqueous solutions including tetrahydrofurfuryl alcohol THFA, ammonium hydroxide NH4OH, and ammonium nitrate NH4NO3 (180 m 3 /a), isopropanol IPA/water mixtures (130 m 3 /a); Non-Process Water NPW (300 m 3 /a); methanol (7m 3 /a); additionally off-gas streams, containing ammonia (9 t/a) have to be treated. In an industrial scale facility all such effluents/gases need to be processed for recycling, decontamination prior to release to the environment (as waste or as valuable material). Thermal decomposition is applied to dispose of burnable residues.

  9. Facility effluent monitoring plan for the 324 Facility

    International Nuclear Information System (INIS)

    1994-11-01

    The 324 Facility [Waste Technology Engineering Laboratory] in the 300 Area primarily supports the research and development of radioactive and nonradioactive waste vitrification technologies, biological waste remediation technologies, spent nuclear fuel studies, waste mixing and transport studies, and tritium development programs. All of the above-mentioned programs deal with, and have the potential to, release hazardous and/or radioactive material. The potential for discharge would primarily result from (1) conducting research activities using the hazardous materials, (2) storing radionuclides and hazardous chemicals, and (3) waste accumulation and storage. This report summarizes the airborne and liquid effluents, and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterizing effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

  10. Application of crown ethers to selective extraction and quantitative analysis of technetium 99, iodine 129 and cesium 135 in effluents

    International Nuclear Information System (INIS)

    Paviet, P.

    1992-01-01

    Properties of crown ethers are first recalled. Then extraction of technetium 99 is studied in actual radioactive effluents. Quantitative analysis is carried out by liquid scintillation and interference of tritium is corrected. Iodine 129 is extracted from radioactive effluents and determined by gamma spectrometry. Finally cesium 135 is extracted and determined by thermo ionization mass spectroscopy

  11. Dose apportionment using statistical modeling of the effluent release

    International Nuclear Information System (INIS)

    Datta, D.

    2011-01-01

    Nuclear power plants are always operated under the guidelines stipulated by the regulatory body. These guidelines basically contain the technical specifications of the specific power plant and provide the knowledge of the discharge limit of the radioactive effluent into the environment through atmospheric and aquatic route. However, operational constraints sometimes may violate the technical specification due to which there may be a failure to satisfy the stipulated dose apportioned to that plant. In a site having multi facilities sum total of the dose apportioned to all the facilities should be constrained to 1 mSv/year to the members of the public. Dose apportionment scheme basically stipulates the limit of the gaseous and liquid effluent released into the environment. Existing methodology of dose apportionment is subjective in nature that may result the discharge limit of the effluent in atmospheric and aquatic route in an adhoc manner. Appropriate scientific basis for dose apportionment is always preferable rather than judicial basis from the point of harmonization of establishing the dose apportionment. This paper presents an attempt of establishing the discharge limit of the gaseous and liquid effluent first on the basis of the existing value of the release of the same. Existing release data for a few years (for example 10 years) for any nuclear power station have taken into consideration. Bootstrap, a resampling technique, has been adopted on this data sets to generate the population which subsequently provide the corresponding population distribution of the effluent release. Cumulative distribution of the population distribution obtained is constructed and using this cumulative distribution, 95th percentile (upper bound) of the discharge limit of the radioactive effluents is computed. Dose apportioned for a facility is evaluated using this estimated upper bound of the release limit. Paper describes the detail of the bootstrap method in evaluating the

  12. Disposal of tritiated effluents

    International Nuclear Information System (INIS)

    Hartmann, K.; Bruecher, H.

    1981-06-01

    After some introductory remarks on the origin of tritium, its properties and its behaviour in a reprocessing plant three alternative methods for the disposal of tritiated effluents produced during reprocessing are described (deep well injection, in-situ solidification, deep-sea dumping) and compared with each other under various aspects. The study is based on the concept of a 1400 t/a reprocessing plant for LWR fuel, which annually produces 3000 m 3 of tritiated waste water with a tritium content of 6.5 x 10 12 Bq/m 3 as well as a residual fission product and actinide content. An assessment of the three methods under the aspects of simplicity, reliability, safety, costs, state of development and materials handling revealed advantages in favour of 'injection', followed by 'dumping' and 'in-situ solidification'. (orig./HP) [de

  13. Complete physico-chemical treatment for coke plant effluents.

    Science.gov (United States)

    Ghose, M K

    2002-03-01

    Naturally found coal is converted to coke which is suitable for metallurgical industries. Large quantities of liquid effluents produced contain a large amount of suspended solids, high COD, BOD, phenols, ammonia and other toxic substances which are causing serious pollution problem in the receiving water to which they are discharged. There are a large number of coke plants in the vicinity of Jharia Coal Field (JCF). Characteristics of the effluents have been evaluated. The present effluent treatment systems were found to be inadequate. Physico-chemical treatment has been considered as a suitable option for the treatment of coke plant effluents. Ammonia removal by synthetic zeolite, activated carbon for the removal of bacteria, viruses, refractory organics, etc. were utilized and the results are discussed. A scheme has been proposed for the complete physico-chemical treatment, which can be suitably adopted for the recycling, reuse and safe disposal of the treated effluent. Various unit process and unit operations involved in the treatment system have been discussed. The process may be useful on industrial scale at various sites.

  14. Facility effluent monitoring plan for WESF

    Energy Technology Data Exchange (ETDEWEB)

    SIMMONS, F.M.

    1999-09-01

    The FEMP for the Waste Encapsulation and Storage Facility (WESF) provides sufficient information on the WESF effluent characteristics and the effluent monitoring systems so that a compliance assessment against applicable requirements may be performed. Radioactive and hazardous material source terms are related to specific effluent streams that are in turn, related to discharge points and, finally are compared to the effluent monitoring system capability.

  15. Modelisation des effets physico-techniques pour la conception des ...

    African Journals Online (AJOL)

    automatisation dans les installations industrielles a besoin d'une régulation automatique des commandes des processus technologiques pour lesquelles certaines contraintes sont à relever compte tenu des exigences des innovations scientifiques de ...

  16. Superconducting materials at temperature higher than liquid nitrogen of the YBaCuO type. Materiaux supraconducteurs jusqu'a des temperatures superieures a celles de l'azote liquide, appartenant au systeme Y-Ba-Cu-O

    Energy Technology Data Exchange (ETDEWEB)

    Gupta, R; Gegnier, P; Truchot, P

    1990-02-09

    The invention concerns new superconducting materials with the formula Zr{sub x} Hf{sub y} Ti{sub z} Y{sub 1-x-y-z} Ba{sub 2}Cu{sub 3}O{sub 7-{delta}} where 0liquid nitrogen and can be used as wire, solid parts, thin or thick layers.

  17. Quantification of effluents in the production of nuclear fuel

    Energy Technology Data Exchange (ETDEWEB)

    Sakai, Mayara C.C.B.; Riella, Humberto G.; Carvalho, Elita F.U. de, E-mail: mcostac@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2017-07-01

    At the Instituto de Pesquisa Energéticas e Nucleares (IPEN), the Centro de Combustível Nuclear (CCN), Sao Paulo, SP, Brazil, is responsible for manufacturing fuels for the IEA-R1 reactor and, possibly, the multipurpose reactor fuels. In order to meet the demand for both reactors, the CCN developed a new plant. The production process of the fuel generates several types of effluents - containing uranium or not - being solid, liquid and gaseous with varied physical and chemical characteristics. The objective of this work is to follow the nuclear fuel production process and to identify, quantify and characterize the effluents, especially the liquid ones, to later elaborate a plan of management of these and eventually dispose in a responsible way in the environment. (author)

  18. Quantification of effluents in the production of nuclear fuel

    International Nuclear Information System (INIS)

    Sakai, Mayara C.C.B.; Riella, Humberto G.; Carvalho, Elita F.U. de

    2017-01-01

    At the Instituto de Pesquisa Energéticas e Nucleares (IPEN), the Centro de Combustível Nuclear (CCN), Sao Paulo, SP, Brazil, is responsible for manufacturing fuels for the IEA-R1 reactor and, possibly, the multipurpose reactor fuels. In order to meet the demand for both reactors, the CCN developed a new plant. The production process of the fuel generates several types of effluents - containing uranium or not - being solid, liquid and gaseous with varied physical and chemical characteristics. The objective of this work is to follow the nuclear fuel production process and to identify, quantify and characterize the effluents, especially the liquid ones, to later elaborate a plan of management of these and eventually dispose in a responsible way in the environment. (author)

  19. Closure report for CAU 93: Area 6 steam cleaning effluent ponds, Nevada Test Site. Volume 2

    International Nuclear Information System (INIS)

    1997-11-01

    The Steam Cleaning Effluent Ponds (SCEP) waste unit is located in Area 6 at the Nevada Test Site. The SCEPs are evaporation basins formerly used for the disposal of untreated liquid effluent discharged from steam cleaning activities associated with Buildings 6-623 and 6-800. This report contains Appendix B which provides all of the laboratory summary data sheets for the Area 6 SCEPs closure activities

  20. Closure report for CAU 93: Area 6 steam cleaning effluent ponds, Nevada Test Site. Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-11-01

    The Steam Cleaning Effluent Ponds (SCEP) waste unit is located in Area 6 at the Nevada Test Site. The SCEPs are evaporation basins formerly used for the disposal of untreated liquid effluent discharged from steam cleaning activities associated with Buildings 6-623 and 6-800. This report contains Appendix B which provides all of the laboratory summary data sheets for the Area 6 SCEPs closure activities.

  1. Hydric effluents; Os efluentes hidricos

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This chapter gives a general overview on the general effects of the hydric pollution, the principal pollutants emitted by the oil refineries, control actions for the hydric emissions, the minimization actions, and the effluent treatment.

  2. Facility effluent monitoring plan for K Area Spent Fuel. Revision 1

    International Nuclear Information System (INIS)

    Hunacek, G.S.

    1995-09-01

    The scope of this document includes program plans for monitoring and characterizing radioactive and nonradioactive hazardous materials discharged in the K Area effluents. This FEMP includes complete documentation for both airborne and liquid effluent monitoring systems that monitor radioactive and nonradioactive hazardous pollutants that could be discharged to the environment under routine and/or upset conditions. This documentation is provided for each K Area facility that uses, generates, releases, or manages significant quantities of radioactive and nonradioactive hazardous materials that could impact public and employee safety and the environment. This FEW describes the airborne and liquid effluent paths and the associated sampling and monitoring systems of the K Area facilities. Sufficient information is provided on the effluent characteristics and the effluent monitoring systems so that a compliance assessment against requirements may be performed. Adequate details are supplied such that radioactive and hazardous material source terms may be related to specific effluent streams which are, in turn, related to discharge points and finally compared to the effluent monitoring system capability

  3. NMR study of hyper-polarized {sup 129}Xe and applications to liquid-phase NMR experiments; Etude de la resonance magnetique nucleaire du Xenon{sup 129} hyperpolarise et applications en RMN des liquides

    Energy Technology Data Exchange (ETDEWEB)

    Marion, D

    2008-07-15

    In liquid samples where both nuclear polarization and spin density are strong, the magnetization dynamics, which can be analysed by NMR (nuclear magnetic resonance) methods, is deeply influenced by the internal couplings induced by local dipolar fields. The present thesis describes some of the many consequences associated to the presence in the sample of concentrated xenon hyper-polarized by an optical pumping process. First, we deal with the induced modifications in frequency and line width of the proton and xenon spectra, then we present the results of SPIDER, a coherent polarization transfer experiment designed to enhance the polarization of protons, in order to increase their NMR signal level. A third part is dedicated to the description of the apparition of repeated chaotic maser emissions by un unstable xenon magnetization coupled to the detection coil tuned at the xenon Larmor frequency (here 138 MHz). In the last part, we present a new method allowing a better tuning of any NMR detection probe and resulting in sensible gains in terms of sensitivity and signal shaping. Finally, we conclude with a partial questioning of the classical relaxation theory in the specific field of highly polarized and concentrated spin systems in a liquid phase. (author)

  4. Facilities for Waste Management at Chalk River, Canada; Les Installations d'Elimination et d'Utilisation des Dechets a Chalk River, Canada; 041e 0411 041e 0420 0423 0414 041e 0412 ; Instalaciones Utilizadas para el Provechamiento y Evacuacion de Desechos Radiactivos en Chalk River, Canada

    Energy Technology Data Exchange (ETDEWEB)

    Mawson, C. A.; Russell, A. E. [Environmental Research Branch, Atomic Energy of Canada Ltd. (Canada)

    1960-07-01

    The waste disposal areas used by the Atomic Energy of Canada Limited are situated in a rock basin filled with glacial till and sand, draining into the Ottawa River. Low-activity liquid effluent is run into pits in the sand, which are filled with small rocks to prevent contact of liquid with the air. Medium- level liquid is mixed with cement in drums which are stacked and totally enclosed in concrete trenches; medium-level solids are buried in concrete-lined trenches; high-level solids are placed in holes lined with steel or concrete piping. Special facilities are provided for organic liquids and bottled wastes. Details will be given of the structural work and procedures, with an outline of the results of environmental monitoring. (author) [French] Les zones d'elimination utilisees par l'Atomic Energy of Canada Limited sont situees dans un bassin rocheux, rempli de blocs erratiques et'de sable, dont les eaux s'ecoulent dans la riviere Ottawa. Les effluents liquides de faible activite sont verses dans des puits creuses dans le sable, qui sont ensuite remplis de petites pierres pour prevenir le contact du liquide avec l'air. Les dechets liquides d'activite moyenne sont melanges a du ciment dans des barils qui sont entasses et completement enfermes dans des tranchees betonnees; les dechets solides d'activite moyenne sont enfouis dans des tranchees bordees de beton; les dechets solides de haute activite sont places dans des trous bordes de conduites d'acier ou de ciment. Des installations speciales sont prevues pour les liquides organiques et les dechets enfermes dans des recipients en forme de bouteilles. Le memoire expose en detail les travaux d'amenagement et les methodes suivies; il donne un apercu des resultats du controle du milieu ambiant. (author) [Spanish] Las zonas utilizadas por la Atomic Energy of Canada Limited para la evacuacion de desechos radiactivos estan situadas en una cuenca rocosa recubierta de limo y arena del periodo glacial, que desemboca en el

  5. variabilite des productions et des revenus des exploitations

    African Journals Online (AJOL)

    3Centre de coopération internationale en recherche agronomique pour le développement (CIRAD), UMR Innovation,. Montpellier, France. Doubangolo COULIBALY, Email kone_b@yahoo.fr. RESUME. La durabilité des systèmes de production à base de coton dans un contexte de variabilité des prix aux producteurs et de ...

  6. A project for storing the radioactive sludges from Marcoule in the soil (1960); Une solution de stockage dans le sol des boues radioactives de Marcoule (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Cohen, P; Gailledreau, C [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    A study of the feasibility of storing radioactive sludges in the soil. Special attention is paid to the case of the Marcoule plant, producing three kinds of sludges. The movement of the different fission products is given. (author) [French] Etude de la possibilite de stocker dans le sol des boues radioactives. Le cas de la station de traitement des effluents de Marcoule, produisant trois types de boues, est etudie plus specialement. Le mouvement des divers produits de fission est precise. (auteur)

  7. impacts des rejets industriels sur les eaux souterraines

    African Journals Online (AJOL)

    USER

    pollution et sont nombreuses, notamment les usines sidérurgiques, métalliques et pétrochimiques. Leurs rejets ont des effets néfastes sur les eaux de la région. Actuellement, les effluents industriels situés dans la région de Berrahal, contiennent d'importantes quantités de produits chimiques organiques et inorganiques et ...

  8. Avaliação de parâmetros indicadores de poluição por efluente líquido de um aterro sanitário Evaluation of indicative parameters of pollution for liquid effluent of a sanitary landfill

    Directory of Open Access Journals (Sweden)

    Selene de Oliveira

    2004-09-01

    Full Text Available O presente trabalho consistiu em determinar alguns parâmetros, químicos (metais pesados e DQO e físico-químico (pH, indicadores de poluição/contaminação do efluente líquido do aterro sanitário municipal de Botucatu/SP, visando a avaliação da qualidade das águas subterrâneas do Aqüífero Botucatu. Os resultados obtidos na determinação dos parâmetros indicam poluição ambiental por metais pesados: cádmio, chumbo, cromo, níquel e zinco. Conseqüentemente, contaminação do lençol freático por cádmio e chumbo; da solução do solo por cádmio, chumbo e cromo; e da água superficial por níquel. Também, foi realizada uma estimativa de produção do efluente líquido para registrar a necessidade de redimensionamento dos drenos horizontais, observando a necessidade de priorizar estudos que controlem os processos construtivos e operacionais de aterros sanitários eficientes e de baixo custo.The present work consisted in to determine some parameters, chemical (heavy metals and COD and physiochemical (pH, pollution/contamination indicative of the liquid effluent of the municipal sanitary landfill of Botucatu/SP, seeking the evaluation of the quality of groundwater of the Botucatu Aquifer.The results obtained in the determination of the parameters indicate environmental pollution of the heavy metals: cadmium, lead, chromium, nickel and zinc. Consequently, contamination of the water table for cadmium and lead; of the solution of soil for cadmium, lead, and chromium; and of the surface water for nickel. Also, an estimate of production of the liquid effluent was accomplished to register the need of new dimensioning of the horizontal drains, observing the need to prioritize studies to control the constructive and operational processes of efficient sanitary landfill and of low cost.

  9. Facility effluent monitoring plan for the uranium trioxide facility

    International Nuclear Information System (INIS)

    Thompson, R.J.; Sontag, S.

    1991-11-01

    A facility effluent monitoring plant is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The UO 3 Plant is located in the south-central portion of the 200 West Area of the Hanford Site. The plant consists of two primary processing buildings and several ancillary facilities. The purpose of the UO 3 Plant is to receive uranyl nitrate hexahydrate (UNH) from the Plutonium-Uranium Extraction (PUREX) Plant, concentrate it, convert the UNH to uranium trioxide (UO 3 ) powder by calcination and package it for offsite shipment. The UO 3 Plant has been placed in a standby mode. There are two liquid discharges, and three gaseous exhaust stacks, and seven building exhausters that are active during standby conditions

  10. Facility effluent monitoring plan for the tank farms facilities

    International Nuclear Information System (INIS)

    Crummel, G.M.; Gustavson, R.D.; Kenoyer, J.L.; Moeller, M.P.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP-0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum three years. A variety of liquid wastes are generated in processing treatment, and disposal operations throughout the Hanford Site. The Tank Farms Project serves a major role in Hanford Site waste management activities as the temporary repository for these wastes. Stored wastes include hazardous components regulated under the Resource Conservation and Recovery Act of 1976 (RCRA) and as by-product material regulated under the Atomic Energy Act of 1954. A total of 177 single- and double-shell tanks (SST and DST) have been constructed in the 200 East and 200 West Areas of the Hanford Site. These facilities were constructed to various designs from 1943 to 1986. The Tank Farms Project is comprised of these tanks along with various transfer, receiving, and treatment facilities

  11. Anaerobic treatment of effluents from slaughterhouse and catering wastes; Production de biogaz a partir de dechets organiques humides - Optimalisation de la digestion de la phase liquide et de la valorisation matiere en affouragement porcin (projet 'GAZOPORC')

    Energy Technology Data Exchange (ETDEWEB)

    Membrez, Y. [Erep SA, Aclens (Switzerland); Descloux, D. [Provimi-Kliba SA, Cossonay-Gare (Switzerland); Dubois, B.; Schwitzguebel, J.P. [Swiss Federal Institute of Technology (EPFL), Laboratory for Environmental Biotechnology, Lausanne (Switzerland); Wellinger, A. [Nova Energie GmbH, Ettenhausen (Switzerland)

    2000-07-01

    This Swiss Federal Office of Energy (SFOE) final report describes the results of a research project concerning the development of a new concept for the treatment of wastes from slaughterhouses and catering. The goals of the project, which was to provide laboratory and pilot-scheme testing of an industrial system, are discussed. The principles of the treatment of these organic wastes are described, including the separation of solid and liquid phases. The production and use of the biogas produced by the anaerobic digestion of the liquid phase in hybrid bio-reactors is discussed and the use of the solid phase for animal feeding is described. The results of estimations made concerning the technical and economical feasibility of the system are discussed. Estimates on the reduction of energy consumption of the slaughterhouse and meat-processing industry thus to be achieved are presented.

  12. 40 CFR 427.43 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS ASBESTOS MANUFACTURING POINT SOURCE CATEGORY Asbestos Paper (Elastomeric Binder) Subcategory § 427.43 Effluent limitations guidelines representing the degree of effluent...

  13. 40 CFR 427.33 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS ASBESTOS MANUFACTURING POINT SOURCE CATEGORY Asbestos Paper (Starch Binder) Subcategory § 427.33 Effluent limitations guidelines representing the degree of effluent...

  14. 40 CFR 426.113 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS GLASS MANUFACTURING POINT SOURCE CATEGORY Television Picture... applicable to the abrasive polishing and acid polishing waste water streams. Effluent characteristic Effluent...

  15. 40 CFR 426.112 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... AGENCY (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS GLASS MANUFACTURING POINT SOURCE CATEGORY Television... stream): Effluent characteristic Effluent limitations Maximum for any 1 day Average of daily values for...

  16. Treatment and processing of the effluents and wastes (other than fuel) produced by a 900 MWe nuclear power plant

    International Nuclear Information System (INIS)

    Giraud

    1983-01-01

    Effluents produced by a 900 MWe power plant, are of three sorts: gaseous, liquid and solid. According to their nature, effluents are either released or stored for decaying before being released to the atmosphere. The non-contaminated reactor coolant effluents are purified (filtration, gas stripping) and treated by evaporation for reuse. Depending upon their radioactive level, liquid waste is either treated by evaporation or discharged after filtration. Solid waste issuing from previous treatments (concentrates, resins, filters) is processed in concrete drums using an encapsulation process. The concrete drum provides biological self-protection consistent with the national and international regulations pertaining to the transport of radioactive substance. Finally, the various low-level radioactive solid waste collected throughout the plant, is compacted into metal drums. Annual estimates of the quantity of effluents (gaseous, liquid) released in the environment and the number of drums (concrete, metal) produced by the plant figure in the conclusion

  17. Civili, langue des Baloango

    DEFF Research Database (Denmark)

    Mavoungou, Paul Achille; Ndinga-Koumba-Binza, Hugues Steve

    , Congo, Angola, etc.) issus de la décolonisation. Il présente de façon succincte quelques phénomènes historiques, phonologiques, morphosyntaxiques, homonymiques et analogiques de la langue. Des faits sémantiques des emprunts linguistiques y sont également décrits dans le cadre des changements...

  18. TBP production plant effluent treatment process

    International Nuclear Information System (INIS)

    Sriniwas, C.; Sugilal, G.; Wattal, P.K.

    2004-06-01

    TBP production facility at Heavy Water Plant, Talcher generates about 2000 litres of effluent per 200 kg batch. The effluent is basically an aqueous solution containing dissolved and dispersed organics such as dibutyl phosphate, butanol etc. The effluent has high salinity, chemical oxygen demand (30-80 g/L) and pungent odour. It requires treatment before discharge. A chemical precipitation process using ferric chloride was developed for quantitative separation of organics from the aqueous part of the effluent. This process facilitates the discharge of the aqueous effluent. Results of the laboratory and bench scale experiments on actual effluent samples are presented in this report. (author)

  19. Des racines et des ailes

    Directory of Open Access Journals (Sweden)

    Stéphanie Vincent-Geslin

    2012-05-01

    Full Text Available Les mobilités pendulaires semblent être en augmentation en Europe depuis une dizaine d’années. Cette croissance du temps passé à se déplacer amène à remettre en question la conjecture de Zahavi et apparaît relativement inexplicable en regard du paradigme classique de l’acteur rationnel traditionnellement utilisé dans le champ des transports. Si, dans la littérature, les temps de déplacements sont principalement expliqués par le contexte résidentiel, la forme urbaine et le travail, ce cadre explicatif ne dit rien des processus de décision eux-mêmes qui amènent aux pendularités intensives.À partir d’une enquête qualitative menée auprès de pendulaires français, suisses et belges, cette contribution propose d’analyser les arbitrages et les éléments déterminants des processus de la grande pendularité. Les mobilités quotidiennes pendulaires apparaissent comme le résultat de compromis entre activité professionnelle, attachement résidentiel et choix de vie et prennent ainsi la forme de stratégies de conciliation entre vie privée et vie professionnelle. Ces mobilités spatiales permettent alors paradoxalement la préservation des ancrages résidentiels, sociaux et familiaux.Roots and wings. Long-distance commuting patterns, or how to conciliate professional and personal lifeLong-distance commuting patterns appear to be increasing in Europe over the last ten years. These raising mobility patterns lead to reappraise the Zahavi conjecture and appear largely inexplicable by the classical rational actor paradigm traditionally used in transportation research. In literature, commuting is mainly explained by residential contexts, urban forms and job. Nevertheless this theoretical frame says little about the decision-making processes themselves. Based on a qualitative survey conducted in three European countries - France, Belgium and Switzerland – among a population of high commuters, this paper proposes an analysis of

  20. Etude des répercussions de la pollution industrielle sur la riziculture ...

    African Journals Online (AJOL)

    Les industries spécialisées dans le textile déversent leurs eaux usées dans le ... sur les sols, les compositions chimiques des plants de riz et sur la production. ... The effluents quality varies on day, the pH from 3.9 to 10.6 and the electrical ...

  1. Studies on the dilution behaviour of effluent discharged into the CCW channel at KGS

    International Nuclear Information System (INIS)

    Sivasubramanian, K.; Srinivasan, S.; Ponraju, D.; Meenakshisundaram, V.; Munusamy, N.

    2003-01-01

    The dilution behaviour of the liquid effluent discharged into condenser cooling water channel of Kaiga Power Plant has been studied using salt addition and dye addition methods. Dilution factors determined experimentally showed that the discharged liquid effluent gets thoroughly mixed with stream of water at the weir and further diluted in the down stream. This paper describes both salt and dye addition methods for determining the dilution factor. The velocity of the stream at various locations were measured and compared with reported values. The selection of representative sampling point for routine analysis of water was identified from this experiment. (author)

  2. Experiment of decontamination of radioactive liquid by a biological method

    International Nuclear Information System (INIS)

    Wormser, G.

    1962-01-01

    The author reports experiments of treatment of radioactive liquid effluents by percolation on a bacterial bed like the one used for the treatment of sewer wastewaters. He also reports results obtained in other countries in terms of reduction of effluent radioactivity for various radioactive ions. The installation is described and results are presented in terms of variation of contamination of an effluent with respect to its recycling on a bacterial bed [fr

  3. Automated system for the safe management of the radioactive wastes and liquid effluents in a Radiopharmaceutical an labelled compounds production center; Sistema automatizado para la gestion segura de los desechos radiactivos y efluentes liquidos en un centro de produccion de radiofarmacos y compuestos marcados

    Energy Technology Data Exchange (ETDEWEB)

    Amador B, Z.H. [Centro de Isotopos, Ave. Monumental y Carretera La Rada, Km. 3, Guanabacoa, Apartado 3415, Ciudad de La Habana (Cuba); Guerra V, R. [Centro de Gestion de Informacion y Desarrollo de la Energia, Calle 20 No. 4111 e/47 y 18A, Playa, Ciudad La Habana (Cuba)]. e-mail: zabalbona@centis.edu.cu

    2006-07-01

    The Center of Isotopes of the Republic of Cuba is a radioactive installation of first category that executes the administration of their radioactive waste under authorization of the National Regulatory Authority. The principles of the design and operation of the 'SADR' system for the safe administration of the radioactive waste and liquid effluents are presented. The Visual Basic 6 platform for the programming of the SADR is used and through of their schematic representation, the control flows and of data of the 7 modules that conform it are shown. For each module the functions are described and it presents an image of the corresponding interface. With the SADR its can be carried out the one registration and the upgrade of the inventory of radioactive waste, the planning of those disqualification operations, the annual consolidation of the volumes of waste generated and disqualified, the evaluation of specific and general indicators and the one tendencies analysis. The handling of the system through the intranet allows the enter of data from the operations place with the radioactive wastes. The results of the operation of the SADR show the utility of this work to elevate the efficiency of the administration of the radioactive wastes. (Author)

  4. Gestion des déchets et inégalités à Lima (Pérou)

    OpenAIRE

    Mathieu Durand

    2011-01-01

    L’étude de la gestion des déchets met en évidence des logiques spatiales permettant de mieux comprendre le fonctionnement des villes. Cette thèse de doctorat en offre l’illustration à travers le cas des villes d’Amérique latine, plus particulièrement de Lima. Nous y interprétons la gestion des déchets solides et liquides sous l’angle des inégalités environnementales et écologiques afin de mieux comprendre les enjeux en termes de vulnérabilité et de durabilité.

  5. Source terms for airborne effluents

    International Nuclear Information System (INIS)

    Blomeke, J.O.; Perona, J.J.

    1976-01-01

    The origin and nature of fuel cycle wastes are discussed with regard to high-level wastes, cladding, noble gases, iodine, tritium, 14 C, low-level and intermediate-level transuranic wastes, non-transuranic wastes, and ore tailings. The current practice for gaseous effluent treatment is described for light water reactors and high-temperature gas-cooled reactors. Other topics discussed are projections of nuclear power generation; projected accumulation of gaseous wastes; the impact of nuclear fuel cycle centers; and global buildup of airborne effluents

  6. Facility Effluent Monitoring Plan for the 3720 Building

    Energy Technology Data Exchange (ETDEWEB)

    Shields, K.D.; Ballinger, M.Y.

    1999-04-02

    This Facility Effluent Monitoring Plan (FEMP) has been prepared for the Environmental Science Laboratory (3720 Facility) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs'' This FEMP has been prepared for the 3720 Facility primarily because it has a major (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The 3720 Facility provides office and laboratory space for PNNL scientific and engineering staff conducting multidisciplinary research in the areas of materials characterization and testing and waste management. The facility is designed to accommodate the use of radioactive and hazardous materials to conduct these activities. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, and dispersible particulate. The facility is in the process of being vacated for shutdown, but is considered a Major Emission Point as of the date of this document approval.

  7. Facility effluent monitoring plan for the 325 Facility

    International Nuclear Information System (INIS)

    1998-01-01

    The Applied Chemistry Laboratory (325 Facility) houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and mixed hazardous waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials, and a waste treatment facility for processing hazardous, mixed, low-level, and transuranic wastes generated by Pacific Northwest Laboratory. Radioactive material storage and usage occur throughout the facility and include a large number of isotopes. This material is in several forms, including solid, liquid, particulate, and gas. Some of these materials are also heated during testing which can produce vapors. The research activities have been assigned to the following activity designations: High-Level Hot Cell, Hazardous Waste Treatment Unit, Waste Form Development, Special Testing Projects, Chemical Process Development, Analytical Hot Cell, and Analytical Chemistry. The following summarizes the airborne and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

  8. Environmental and Effluent Monitoring at ANSTO Sites, 2002-2003

    Energy Technology Data Exchange (ETDEWEB)

    Hoffmann, E L; Ferris,; Markich, S J

    2004-10-01

    This report presents the results of environmental and effluent monitoring at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC) from January 2002 to June 2003. Potential effective dose rates to the general public from airborne discharges from the LHSTC site were less than 0.01 mSv/year, well below the 1 mSv/year dose rate limit for long term exposure that is recommended by the Australian National Occupational Health and Safety Commission. The effective dose rates to hypothetical individuals potentially exposed to radiation in routine liquid effluent discharges from the LHSTC were recently calculated to be less than 0.001 mSv/year. This is much less than dose rates estimated for members of public potentially exposed to airborne emissions. The levels of tritium detected in roundwater and stormwater at the LHSTC were less than the Australian drinking water guidelines. The airborne and liquid effluent emissions from the NMC were below the ARPANSA-approved notification levels and NSW EPA limits, respectively. ANSTO's routine operations at the LHSTC and the NMC make only a very small addition to the natural background radiation dose experienced by members of the Australian public. (authors)

  9. Treatment of effluents from the nuclear fuel cycle reconversion stage

    International Nuclear Information System (INIS)

    Ladeira, Ana C.Q.; Morais, Carlos A.; Goncalves, Joao S.; Souza, Pedro de

    2007-01-01

    The conversion of uranium hexafluoride (UF 6 ) into uranium dioxide (UO 2 ) takes place in Resende (RJ) at the Nuclear Fuel Factory - FCN. The process generates liquid effluents with significant concentrations of uranium which might be treated before being discharged into the environment. This work is aimed at the recovery of uranium from two distinct liquid effluents; one with high carbonate content and the other with elevated fluoride concentration. It is also presented a study about carbonate removal from an effluent that consists of water - methanol solution generated during the filtration step of the ammonium uranyl tricarbonate (AUT). The results showed that (1) the uranium from the carbonated solution can be recovered through the ion exchange technique using the strong base anionic resin IRA 910-U since carbonate has been removed as CO 2 after heating; (2) the most suitable technique to recover uranium from the fluoride solution is by precipitation as (NH 4 ) 2 UO 4 F 2 - ammonium fluorouranate peroxide (APOFU), (3) the solution free of carbonate can be added to the fluoride solution and the uranium from the final solution can be recovered by precipitation as ammonium fluorouranate peroxide as well; (4) the carbonate from the water-methanol solution can be recovered as calcium carbonate through the addition of calcium chloride or it can be removed through the addition of sulfuric acid. The product formed by adding sulfuric acid is ammonium sulfate and might be used as fertilizer. (author)

  10. Feasibility of using of the second gradient theory for the direct numerical simulation of liquid-vapor flows with phase-change; Etude des potentialites de la theorie du second gradient pour la simulation numerique directe des ecoulements liquide-vapeur avec changement de phase

    Energy Technology Data Exchange (ETDEWEB)

    Jamet, D. [CEA Grenoble, 38 (France). Dept. de Thermohydraulique et de Physique]|[Ecole Centrale de Paris, 75 (France)

    1998-12-31

    One on the main difficulties encountered in the direct numerical simulation of two-phase flows in general and of liquid-vapor flows with phase-change in particular, is the interface tracking. The idea developed in this work consists in modeling a liquid-vapor interface as a volumetric zone across which physical properties vary continuously instead of a discontinuous surface. The second gradient theory allows to establish the evolution equations of the fluid in the whole system: bulk phases and interfaces. That means that the resolution of a unique system of partial differential equations is necessary to determine the whole two-phase flow, the interfaces and their evolution in time being a part of the solution of this unique system. We show in this work that it is possible to artificially enlarge an interface without changing its surface tension and the latent heat of vaporization. That means than it is possible to track all the interfaces of a liquid-vapor two-phase flow with phase-change on a mesh the size of which is imposed by the smallest Kolmogorov scale of the bulk phases for example. The artificial enlargement of an interfacial zone is obtained by modifying the thermodynamic behavior of the fluid within the binodal. We show that this modification does not change the dynamics of an interface. However, although the thickness of an interface and its surface tension vary with the mass and heat fluxes that go though it, the thermodynamic modification necessary to the artificial enlargement of an interface drastically increases these variations. Consequently, the artificial enlargement of an interface must be made carefully to avoid a too much important variation of its surface tension during dynamic situations. (author) 60 refs.

  11. Treatment of liquid wastes from uranium hydrometallurgy

    International Nuclear Information System (INIS)

    Moraga G, J.C.

    1988-01-01

    Different treatments for low activity liquid wastes, generated by the hidromettalurgy of uranium ore are studied. A process of treatment was chosen which includes a neutralization with lime and limestone and a selective removal of Ra-226, through ion-exchange resins. A plant, with a capacity of treatment of 1 m 3 /h of liquid effluents was scoped. (author)

  12. Effluent information system (EIS)/onsite discharge information system (ODIS) 1985 executive summary

    International Nuclear Information System (INIS)

    Watanabe, T.

    1986-09-01

    The Effluent Information System (EIS) and Onsite Discharge Information System (ODIS) are Department of Energy (DOE) data base systems that aid DOE-Headquarters and Field Offices in managing the radioactive air and liquid effluents from DOE facilities. Data on effluents released offsite are entered into EIS and data on effluents discharged onsite and retained onsite are entered into ODIS. This document is a summary of information obtained from the CY 1985 effluent data received from all DOE and DOE contractor facilities and entered in the data bases. Data from previous years are also included. The summary consists of two parts. The first part summarizes information for effluents released offsite, and the second part summarizes information for effluents retained onsite. These summaries are taken from the routine annual reports sent to each DOE Operations Office. Special tabulations or specific data can be supplied upon request. Explanations of the significant changes are included in the EIS and ODIS graphic sections. Only those changes in activity greater than a factor of two and having a magnitude greater than 0.1 Ci are considered significant and are addressed in the explanation

  13. Characterisation of potential aquaculture pond effluents, and ...

    African Journals Online (AJOL)

    Conventional treatment of effluents from these small-scale, low-volume operations, which discharge relatively dilute effluents infrequently, might not be cost-effective. Keywords: aquaculture–environment interaction, earthen ponds, effluent characterisation, K-means clustering, t ilapia, water quality. African Journal of Aquatic ...

  14. Facility effluent monitoring plan for WESF

    International Nuclear Information System (INIS)

    SIMMONS, F.M.

    1999-01-01

    The FEMP for the Waste Encapsulation and Storage Facility (WESF) provides sufficient information on the WESF effluent characteristics and the efferent monitoring systems so that a compliance assessment against applicable requirements may be performed. Radioactive and hazardous material source terms are related to specific effluent streams that are in turn, related to discharge points and, finally are compared to the effluent monitoring system capability

  15. Liquid-liquid transfer phenomena studies coupled with redox reactions: back-extraction of nitrous acid in the presence of scavengers in aqueous phase; Etude de reactions d`oxydoreduction couplees a des phenomenes de transfert liquide-liquide: cas de la desextraction de l`acide nitreux en presence de composes antinitreux en phase aqueuse

    Energy Technology Data Exchange (ETDEWEB)

    K`zerho, R

    1998-12-31

    This work deals with the investigation of redox reaction contribution to the kinetics of liquid-liquid transfer, in relation with PUREX reprocessing of spent nuclear fuel. The chemical system chosen concerns the tripping of nitrous acid from tributylphosphate organic phase into a nitric acid aqueous solution containing an `anti-nitrous` component, namely hydrazinium nitrate. According to the abundant literature, a major attention is devoted to the very important role of interfacial phenomena on the kinetics of solvent extraction with tributylphosphate. Although, a suitable experimental technique is chosen, using a constant interfacial area cell of the ARMOLLEX-type. Furthermore, the effects of the hydrodynamical and the physico-chemical parameters on the extraction rate led to the identification of the extraction regime nature: diffusional, then chemical limitation. When no `anti-nitrous` component is used, the diffusional resistance is found to be mainly located in the aqueous diffusion layer. The presence of hydrazinium nitrate into the aqueous solution has an overall accelerating effect on the rate of extraction, related to both a complete suppression of the aqueous diffusional resistance, and a very significant enhancement of the interfacial transfer of the nitrous acid, as a function of hydrazinium concentration. If the first effect could be expected because of the well known fast redox reaction in aqueous phase, the second phenomenon represents a quite original and new result which has never been explored before, to the best of our knowledge. A reaction mechanism is postulated and validated, taking into account the reactive effect of hydrazinium on the interfacial step. In order to support the drawn general patterns, different complementary studies were attempted. When hydroxyl-ammonium nitrate is used, a surprising interfacial transfer blockage is observed, pointing out the extreme performance and specificity of the common hydrazinium component. (author) 99

  16. Low and medium level liquid waste processing at the new La Hague reprocessing plant

    International Nuclear Information System (INIS)

    Alexandre, D.

    1986-05-01

    Reprocessing of spent nuclear fuels produces low and medium activity liquid wastes. These radioactive wastes are decontamined before release in environment. The new effluent processing plant, which is being built at La Hague, is briefly described. Radionuclides are removed from liquid wastes by coprecipitation. The effluent is released after decantation and filtration. Insoluble sludges are conditioned in bitumen [fr

  17. Multi-dimensional modeling of gas-liquid two-phase flows. Application to the simulation of ascending bubble flows in vertical ducts; Modelisation multidimensionnelle des ecoulements diphasiques gaz-liquide. Application a la simulation des ecoulements a bulles ascendants en conduite verticale

    Energy Technology Data Exchange (ETDEWEB)

    Morel, Ch

    1997-10-31

    The aim of this thesis is the 3-D modeling and numerical simulation of liquid/gas (water/vapor or water/air) two-phase flows in cooling circuits of nuclear power plants during normal and accidental situations. The development of a multidimensional dual-fluid model encounters two problems: the statistical effects of turbulence and the interface mass, momentum and energy transfers. The models developed in this study were introduced in the 3-D module of the CATHARE code developed by the CEA and the results were compared to experimental results available in the literature. The first chapter describes the equations of the local dual-fluid model for the 3-D description of two-phase flows. Closing relations adapted to dispersed flows with isothermal bubbles and without phase transformation are proposed and focus on the momentum transfer at the interfaces. The theoretical study of turbulence in the liquid phase of a bubble flow is modelled in chapter 2. Chapter 3 deals with the voluminal interface area used in the interface mass, momentum and energy transfers, and chapters 4 and 5 concern the application of the developed models to concrete situations. Chapter 4 describes in details the 3-D module of the CATHARE code while chapter 5 gives a comparison of numerical results obtained using the CATHARE code with other experimental results obtained at EdF. (J.S.) 109 refs.

  18. Experimental study and modelling of competitive adsorption equilibria of aromatics in liquid phase on X and Y faujasites; Etude experimentale et modelisation des equilibres d'adsorption competitive d'aromatiques en phase liquide sur des faujasites X et Y

    Energy Technology Data Exchange (ETDEWEB)

    Tournier, H.

    2000-10-13

    The separation of p-xylene from C{sub 8} aromatics is performed industrially by selective adsorption on zeolitic molecular sieves. The aim of this work is to study and model adsorption equilibria of C{sub 8} and C{sub 10} aromatics on X and Y zeolites. The experimental data are obtained by an entirely automated equipment allowing to work in a large range of temperature (50 deg. C - 250 deg. C). With this equipment, we can follow the evolution of the composition of the liquid phase and determine the composition of the adsorbed phase at equilibrium by a mass balance calculation and with an inert component. Two analytical techniques are used to determine the composition of the liquid phase: (1) a classical method using a gas chromatograph (GC) allowed to measure selectivities in the concentration range (3%-97%) in a component; (2) an original method based on the use and on the measure of {sup 13}C labelled xylenes was developed to investigate the ranges of strongly contrasting concentrations [0-3%] and [97%-100%] in a component, which are representative of high purity domains. Lastly, three thermodynamic models are used to describe the adsorption equilibria: the Langmuir-Freundlich model, the quasi-chemical model and the statistical model. The last model is the more interesting, because it is based on physical considerations. A new statistical model has been developed with taking into account some observations coming from adsorption phenomenon in zeolites. (author)

  19. Environmental and effluent monitoring at Lucas Heights Research Laboratories, 1994

    International Nuclear Information System (INIS)

    Hoffmann, E.L.; Camilleri, A.; Loosz, T.; Farrar, Y.

    1995-12-01

    Results are presented of environmental and effluent monitoring conducted in the vicinity of the Lucas Heights Research Laboratories (LHRL) during 1994. All low level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from controlled airborne discharges during this period, were estimated to be less than 0.015 mSv/year for receptor locations on the 1.6 km buffer zone boundary around HIFAR. This value represents 1.5 % of the 1 mSv/year dose limit for long term exposure that is recommended by the National Health and Medical Research Council, and 5 % of the site dose constraint of 0.3 mSv/year adopted by ANSTO. 27 refs., 22 tabs., 6 figs

  20. Environmental and effluent monitoring at Lucas Heights Research Laboratories, 1994

    Energy Technology Data Exchange (ETDEWEB)

    Hoffmann, E L; Camilleri, A; Loosz, T; Farrar, Y

    1995-12-01

    Results are presented of environmental and effluent monitoring conducted in the vicinity of the Lucas Heights Research Laboratories (LHRL) during 1994. All low level liquid and gaseous effluent discharges complied with existing discharge authorisations and relevant environmental regulations. Potential effective doses to the general public from controlled airborne discharges during this period, were estimated to be less than 0.015 mSv/year for receptor locations on the 1.6 km buffer zone boundary around HIFAR. This value represents 1.5 % of the 1 mSv/year dose limit for long term exposure that is recommended by the National Health and Medical Research Council, and 5 % of the site dose constraint of 0.3 mSv/year adopted by ANSTO. 27 refs., 22 tabs., 6 figs.

  1. Graphic overview system for DOE's effluent and environmental monitoring programs

    International Nuclear Information System (INIS)

    Burson, Z.G.; Elle, D.R.

    1980-03-01

    The Graphic Overview System is a compilation of photos, maps, overlays, and summary information of environmental programs and related data for each DOE site. The information consists of liquid and airborne effluent release points, on-site storage locations, monitoring locations, aerial survey results, population distributions, wind roses, and other related information. The relationships of different environmental programs are visualized through the use of colored overlays. Trends in monitoring data, effluent releases, and on-site storage data are also provided as a corollary to the graphic display of monitoring and release points. The results provide a working tool with which DOE management (headquarters and field offices) can place in proper perspective key aspects of all environmental programs and related data, and the resulting public impact of each DOE site

  2. Effluent and environmental monitoring of Chalk River Laboratories

    Energy Technology Data Exchange (ETDEWEB)

    Pilgrim, T.; De Waele, C.; Gallagher, C. [Atomic Energy of Canada Limited, Chalk River, ON (Canada)

    2014-07-01

    Atomic Energy of Canada Limited's (AECL's) Environmental Protection Program has been gathering environmental monitoring data at its Chalk River Laboratories (CRL) for over 60 years. The comprehensive effluent and environmental monitoring program at CRL consists of more than 600 sampling locations, including the Ottawa River, with approximately 60,000 analyses performed on air and liquid effluent parameters each year. Monitoring for a variety of radiological and non-radiological parameters is regularly conducted on various media, including ambient air, foodstuff (e.g. milk, fish, garden produce, large game, and farm animals), groundwater, Ottawa River water and other surface water on and off-site. The purpose of the monitoring program is to verify that past and current radiological and non-radiological emissions derived from AECL operations and activities, such as process water effluent into the Ottawa River, are below regulatory limits and demonstrate that CRL operations do not negatively affect the quality of water on or leaving the site. In fact, ongoing program reports demonstrate that radiological emissions are well below regulatory limits and have been declining for the past five years, and that non-radiological contaminants do not negatively affect the quality of water on and off the site. Two updated Canadian Standards Association (CSA) standards for Effluent and Environmental monitoring have come into effect and have resulted in some changes to the AECL Program. This presentation will discuss effluent and surface water monitoring results, the observed trends, the changes triggered by the CSA standards, and a path forward for the future. (author)

  3. Removal of novel antiandrogens identified in biological effluents of domestic wastewater by activated carbon.

    Science.gov (United States)

    Ma, Dehua; Chen, Lujun; Liu, Rui

    2017-10-01

    Environmental antiandrogenic (AA) contaminants in effluents from wastewater treatment plants have the potential for negative impacts on wildlife and human health. The aim of our study was to identify chemical contaminants with likely AA activity in the biological effluents and evaluate the removal of these antiandrogens (AAs) during advanced treatment comprising adsorption onto granular activated carbon (GAC). In this study, profiling of AA contaminants in biological effluents and tertiary effluents was conducted using effect-directed analysis (EDA) including high performance liquid chromatography (HPLC) fractionation, a recombinant yeast screen containing androgen receptor (YAS), in combination with mass spectrometry analyses. Analysis of a wastewater secondary effluent from a membrane bioreactor revealed complex profiles of AA activity comprising 14 HPLC fractions and simpler profiles of GAC effluents with only 2 to 4 moderately polar HPLC fractions depending on GAC treatment conditions. Gas chromatography-mass spectrometry and ultra-high performance liquid chromatography-nanospray mass spectrometry analyses of AA fractions in the secondary effluent resulted in detection of over 10 chemical contaminants, which showed inhibition of YAS activity and were potential AAs. The putative AAs included biocides, food additives, flame retardants, pharmaceuticals and industrial contaminants. To our knowledge, it is the first time that the AA properties of N-ethyl-2-isopropyl-5-methylcyclohexanecarboxamide (WS3), cetirizine, and oxcarbazepine are reported. The EDA used in this study was proven to be a powerful tool to identify novel chemical structures with AA activity in the complex aquatic environment. The adsorption process to GAC of all the identified antiandrogens, except WS3 and triclosan, fit well with the pseudo-second order kinetics models. Adsorption to GAC could further remove most of the AAs identified in the biological effluents with high efficiencies. Copyright

  4. Separation of tritium from reprocessing effluents

    International Nuclear Information System (INIS)

    Bruggeman, A.; Doyen, W.; Harnie, R.; Leysen, R.; Meynendonckx, L.; Monsecour, M.; Goossens, W.R.A.; Baetsle, L.H.

    1980-01-01

    For several years tritium retention has been studied at the Belgian Nuclear Research Centre, SCK/CEN; initially attention was focused on the removal of tritium from gaseous reprocessing effluents. If tritium can be released from the spent fuel into the gaseous phase before any aqueous operation, adsorption on molecular sieves after some isotopic dilution with hydrogen and after complete conversion to (tritiated) water is the most practical collection method. A once-through 15 m 3 .h -1 oxidation-adsorption unit with a closed regeneration system and with a decontamination factor of 1000 at total (tritiated) hydrogen and water inlet concentrations down to 1000 vpm (parts per million by volume) has been constructed and tested at SCK/CEN and it is described in the text. If no special head-end treatment is used an appropriate liquid management inside the reprocessing plant restricts the volume of tritiated aqueous effluents to about 3 m 3 per tonne of LWR fuel processed. However, for further reduction an isotope separation process becomes necessary. SCK/CEN is developing the ELEX process, which is a combination of water ELectrolysis and tritium EXchange between hydrogen and water, the exchange being promoted by a hydrophobic catalyst. For electrolysis under normal conditions an elementary tritium separation factor of 11.6 with a standard deviation of 6% was obtained. As concerns the exchange step a hydrophobic catalyst has been developed which yields for the flow rates used at atmospheric pressure and at 20 0 C an overall exchange rate constant of 9 mol.s -1 .m -3 in a countercurrent trickle-bed reactor. At present an integrated bench scale de-tritiation unit is being built for further tests and for a dynamic demonstration of the ELEX process

  5. Evaluation 2000 and regulation and method. Release monitoring and environmental surveillance around Cea centers; Bilan 2000 et reglementation et methode. Controle des rejets et surveillance de l'environnement des centres CEA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-06-01

    This publication counts for the year 2000 for the evaluation of liquid and gaseous radioactive effluents releases and the radioactivity levels measured in the vicinity of Cea centers, through the air, water, vegetation and milk surveillance. An analysis of the results from 1996 to 2000 allows to follow their evolution. A second booklet develops the sampling and measurement methods made on effluents in environment. It present besides the regulation applied to effluents monitoring. (N.C.)

  6. Assessment of derived emission limits for radioactive effluents resulted from the decommissioning activities of the VVR-S nuclear research reactor

    International Nuclear Information System (INIS)

    Tuca, C.; Stochioiu, A.; Sahagia, M.; Gurau, D.; Dragusin, M.

    2015-01-01

    This paper presents complex studies on establishment of derived emission limits for potential radionuclides emitted as gaseous and liquid effluents, during the decommissioning activities (2nd and 3rd phases) of a nuclear research reactor, cooled and moderated with distilled water, type VVR-S, owned by the IFIN-HH. In the present paper there are described: the analysis methods and equipment used, the methodologies for calculating doses and the Derived Emission Limits (DEL), the experimentally measured activities of the representative radionuclides found in gaseous and liquid effluents resulted from decommissioning activities, as well as the effective derived limits of liquid and gaseous effluents, applying the calculation methodologies, specific to critical categories of exposed subjects. A constraint effective dose limit for a person from the critical group of 50 μSv/year was considered in calculations. From the comparison of the two series of values, measured released activities and DELs, there has been concluded that for the gaseous effluents they comply with the DELs, while in the case of liquid effluents they are higher and consequently they must be treated as liquid radioactive wastes. - Highlights: • The DELs for gaseous and liquid effluents in decommissioning were studied. • The impact on the environment and critical group was assessed. • Gamma-ray spectrometry was used to determine the radionuclide composition. • Based on the dosimetry models, the values of conservative DELs were calculated. • The DELs are compliant for gases, not for liquids; require the treatment as rad-waste

  7. Biogas Production Using Anaerobic Biodigester from Cassava Starch Effluent

    Directory of Open Access Journals (Sweden)

    S. Sunarso

    2010-12-01

    Full Text Available IKMs’ factory activity in Margoyoso produces liquid and solid wastes. The possible alternative was to use the liquid effluent as biogas raw material. This study focuses on the used of urea, ruminant, yeast, microalgae, the treatment of gelled and ungelled feed for biogas production, pH control during biogas production using buffer Na2CO3, and feeding management in the semi-continuous process of biogas production that perform at ambient temperature for 30 days. Ruminant bacteria, yeast, urea, and microalgae was added 10% (v/v, 0.08% (w/v, 0.04% (w/v, 50% (v/v of mixing solution volume, respectively. The pH of slurry was adjusted with range 6.8-7.2 and was measured daily and corrected when necessary with Na2CO3. The total biogas production was measured daily by the water displacement technique. Biogas production from the ungelling and gelling mixture of cassava starch effluent, yeast, ruminant bacteria, and urea were 726.43 ml/g total solid and 198 ml/g total solid. Biogas production from ungelling mixture without yeast was 58.6 ml/g total solid. Biogas production from ungelling mixture added by microalgae without yeast was 58.72 ml/g total solid and that with yeast was 189 ml/g total solid. Biogas production from ungelling mixture of cassava starch effluent, yeast, ruminant bacteria, and urea in semi-continuous process was 581.15 ml/g total solid. Adding of microalgae as nitrogen source did not give significant effect to biogas production. But adding of yeast as substrate activator was very helpful to accelerate biogas production. The biogas production increased after cassava starch effluent and yeast was added. Requirement of sodium carbonate (Na2CO3 to increase alkalinity or buffering capacity of fermenting solution depends on pH-value

  8. Measurements of gas and volatile element production rates from an irradiated molten lead and lead-bismuth spallation target with proton beams of 1 and 1.4 GeV; Mesures de taux de production d'elements gazeux et volatiles lors de reactions induites par des protons de 1 et 1,4 GeV sur des cibles epaisses de plomb et plomb-bismuth liquides

    Energy Technology Data Exchange (ETDEWEB)

    Tall, Y

    2008-03-15

    The integrated project EUROTRANS (European Research Programme for the Transmutation of High Level Nuclear Waste in an Accelerator Driven System) of the 6. EURATOM Framework Programme aims to demonstrate the transmutation of radioactive waste in ADS (Accelerator Driven Sub-critical system). It will carry out a first advanced design of an experimental facility to demonstrate the technical feasibility of transmutation, and will produce a conceptual design of an industrial facility dedicated to transmutation. An ADS consists of three fundamental elements: the accelerator of protons, the sub-critical core and the spallation target. SUBATECH (physique Sub-Atomique et des Technologies associees) laboratory is involved to the study of the chosen liquid lead-bismuth as a spallation ADS target. The irradiation of liquid lead-bismuth target with energetic proton beam generates in addition to neutrons, volatile and radioactive residues. In order to determine experimentally the production rates of gas and volatile elements following a spallation reaction in a lead-bismuth target, the experiment IS419 was performed at the ISOLDE facility at CERN (Centre Europeen de la Recherche Nucleaire). This experiment constitutes the frame of the thesis whose main objective is to assess and study the production and release rates of many gas and volatile element from the irradiated lead-bismuth target with an energetic proton beam. The obtained data are compared to Monte Carlo simulation code (MCNPX) results in order to test the intranuclear cascade model of Bertini and of Cugnon, and the evaporation options of Dresner and Schmidt. (author)

  9. Radioactive effluents from CANDU 6 reactors during normal operation

    International Nuclear Information System (INIS)

    Boss, C.R.; Allsop, P.J.

    1995-12-01

    During routine operation of a CANDU 6 reactor, various gaseous, liquid, and solid radioactive wastes are generated. The layout of the CANDU 6 reactor and the design of its systems ensure that these are minimized, but small quantities of gaseous and liquid wastes are continually discharged at very low concentrations. This report discusses the make-up of these chronically generated gaseous and liquid effluents. From a safety perspective, the doses to individual members of the public resulting from radioactive wastes chronically discharged from CANDU 6 reactors have been negligible. Similarly, doses to the regional and global populations have been negligible, generally less than 0.001% of background. While far below regulatory limits, releases of tritium, noble gases and gross β - -γ have been the most radiologically significant emissions, while radioiodine and particulates have had the greatest potential to deliver public dose. (author). 8 refs., 16 tabs., 3 figs

  10. Collective dose to the European Community from nuclear industry effluents discharge in 1978

    CERN Document Server

    Camplin, W C

    1983-01-01

    The results are presented of a study to evaluate the collective dose commitment to the population of the European Community from effluents released by the nuclear industry within the EC in 1978. Airborne and liquid effluent discharge data have been taken from published sources, and computer modelling techniques have been used to predict the transfer of radioactivity through the environment to man. The collective dose commitments due to discharges from each nuclear installation have been evaluated and the comparative significance of individual radionuclides and their pathways to man have been considered. Airborne releases resulted in an estimated collective effective dose equivalent commitment of 95 man Sv, the major part of which is due to carbon-14 from both power stations and reprocessing plants. The collective effective dose equivalent commitment from liquid effluents is estimated to be 408 man Sv, mostly due to caesium-137 and other radionuclides from the Sellafield (formerly Windscale) reprocessing plant...

  11. Chemical products toxicological tests performed on lake and river fish; Essai toxicologiques de produits chimiques sur des poissons d'eau douce

    Energy Technology Data Exchange (ETDEWEB)

    Teulon, F.; Simeon, C. [Commissariat a l' Energie Atomique, Centre de Pierrelatte (France). Centre d' Etudes Nucleaires

    1966-07-01

    The volume and toxical values of industrial and urban effluents are growing higher and therefore acute or chronic pollution hazard is proportionally increased. Hence it is necessary to determine the effluent components minimum lethal dose for fish (one hour or six hours according to applicable standards). The following tests are described in this report: toxicity of some chemical products, tested individually (sodium, sulphate, sodium chloride, sodium fluoride, etc...); toxicity of some metal ions (Al{sup 3+}, Fe{sup ++}, Fe{sup 3+}, Pb{sup ++}, etc...); toxicity of certain mixed compounds for various fish species (sun perch, tench, gold fish, roach, gudgeon, bleak). The test results obtained represent local values and may be used for reference and as a general basis for other investigation and calculation of the effluents data when released. (author) [French] Le volume et la toxicite des effluents industriels et urbains deviennent de plus en plus importants, les risques de pollution aigue ou chronique croissent en proportion. Il est donc necessaire de determiner les doses minima mortelles pour le poisson (1 h ou 6 h, d'apres les conventions) des composants eventuels des effluents consideres. Les essais qui font l'objet de ce rapport sont les suivants: toxicite de quelques produits chimiques, pris separement (sulfate, chlorure, fluorure de sodium, etc...); toxicite de quelques ions metalliques: Al{sup 3+}, Fe{sup ++} et Fe{sup 3+}, Pb{sup ++}, etc...); toxicite de quelques melanges sur des especes differentes de poissons ( perche-soleil, tanche, carassin, gardon, goujon, ablette). Les chiffres obtenus representent des valeurs locales et peuvent servir de references et de base de travail pour le calcul des caracteristiques des effluents a leur rejet. (auteur)

  12. Des Connaissances Aux Politiques

    International Development Research Centre (IDRC) Digital Library (Canada)

    Les synergies ont été mises en commun au fur et à mesure des progrès de la recherche. .... Recherche normative (sur le rôle et la performance des institutions .... Système national d'information sur la gestion environnementale connecté à 19 ...... Un fort contrôle centralisé sur l'élaboration des politiques nationales peut ...

  13. 79 Influences des rejets des eaux usées domestiques dans les ...

    African Journals Online (AJOL)

    PR BOKO

    Keywords : wastewater, watercress, soil, mobility, metal elements traces, adsorption. 1. Introduction. L'usage agricole d'effluents liquides peut être considéré comme une valorisation potentielle d'eau, de nutriments et de matières organiques [1-3]. Il préserve l'environnement en réduisant ou en éliminant les polluants ...

  14. Évaluation des pratiques agricoles des légumes feuilles : le cas des ...

    African Journals Online (AJOL)

    SARAH

    30 sept. 2017 ... ... de Biochimie et Immunologie Appliquée, Centre de Recherche en Sciences Biologiques, Alimentaires et .... l'intoxication des agriculteurs et des consommateurs, ... source d'alimentation en eau et au pouvoir d'achat des.

  15. UNC Nuclear Industries reactor and fuels production facilities 1985 effluent release report

    International Nuclear Information System (INIS)

    Rokkan, D.J.

    1986-01-01

    Analyses of routine samples from radioactive liquid and airborne streams were performed using UNC's Radioanalytical Laboratory and the analytical services of US Testing Company. All significant effluent discharges from UNC facilities to the environment during CY 1985 are reported in this document

  16. Recovery of ammonia and production of high-grade phosphates from digester effluents

    Science.gov (United States)

    Conservation and recovery of nitrogen and phosphorus from animal wastes and municipal effluents is important because of economic and environmental reasons. In this paper we present a novel technology for separation and recovery of ammonia and phosphorus from liquid swine manure. Phosphorus recovery ...

  17. Determination and removal of antibiotics in secondary effluent using a horizontal subsurface flow constructed wetland.

    Science.gov (United States)

    Zhang, Chunhui; Ning, Ke; Zhang, Wenwen; Guo, Yuanjie; Chen, Jun; Liang, Chen

    2013-04-01

    Increased attention is currently being directed towards the potential negative effects of antibiotics and other PPCPs discharged into the aquatic environment via municipal WWTP secondary effluents. A number of analytical methods, such as high performance liquid chromatography technologies, including a high performance liquid chromatography-fluorescence method (HPLC-FLD), high performance liquid chromatography-UV detection method (HPLC-UV) and high performance liquid chromatography-mass spectrometry method (HPLC-MS), have been suggested as determination technologies for antibiotic residues in water. In this study, we implement a HPLC-MS/MS combined method to detect and analyze antibiotics in WWTP secondary effluent and apply a horizontal subsurface flow constructed wetland (CW) as an advanced wastewater treatment for removing antibiotics in the WWTP secondary effluent. The results show that there were 2 macrolides, 2 quinolones and 5 sulfas in WWTP secondary effluent among all the 22 antibiotics considered. After the CW advanced treatment, the concentration removal efficiencies and removal loads of 9 antibiotics were 53-100% and 0.004-0.7307 μg m(-2) per day, respectively.

  18. Détermination des particularités phénotypiques érythrocytaires des donneurs de sang du groupe O de Tlemcen

    OpenAIRE

    BEGHDAD, Mohammed El Amine; ZAZOUA, KHAMES Farid

    2014-01-01

    La transfusion sanguine est une thérapeutique essentielle et incontournable de nos jours, En revanche elle présente des risques directement liés à sa nature même par le transfert de liquide biologique d'un individu à un autre à l'origine des risques infectieux et immunologiques. Ces derniers sont essentiellement dus au polymorphisme génétique des antigènes éiythrocytaires engendrant une alto-immunisation anti-érythrocytaire pouvant aboutir à des situations d'impasse transfusionnel...

  19. INDUSTRIE ET ENVIRONNEMENT Les préoccupations environnementales de l’industrie des corps gras

    Directory of Open Access Journals (Sweden)

    Pages Xavier

    2002-09-01

    Full Text Available Les préoccupations environnementales de l’industrie des corps gras sont principalement rythmées par le renforcement des contraintes réglementaires et concernent tous les aspects environnementaux : effluents gazeux et aqueux, déchets, management, énergie. Ces aspects sont inégalement présents dans les différents sous-secteurs de l’industrie des corps gras ; quelques exemples sont présentés. La réduction des émissions de COV (composés organiques volatils et les nuisances olfactives sont une problématique concernant principalement l’activité de trituration, la lipochimie et la fonte de corps gras animaux. Des valeurs limites de consommation de solvant sont maintenant imposées réglementairement en extraction; la prise en compte de problèmes de nuisance olfactive donnent lieu à l’amélioration des procédés de traitement d’air (corps gras animaux ou à leur mise en place progressive (trituration de colza. La gestion des déchets reste une préoccupation essentielle pour l’ensemble de la profession et tout particulièrement pour les secteurs des corps gras animaux et la lipochimie, en raison de la remise en cause des filières d’élimination due au renforcement des contraintes réglementaires, mais aussi en raison des coûts de traitement. Ce poste ne doit pas être négligé par les entreprises : réduction à la source, recherche de filières pérennes, valorisation énergétique ou matière sont des éléments permettant également une réduction significative des coûts. La maîtrise de la consommation d’énergie est un élément important, voir stratégique, notamment dans le secteur de la trituration des graines oléagineuses. Des actions de sensibilisation permettent de poursuivre également l’effort auprès des PME, actuellement moins impliquées. En matière de traitement d’eau, des avancées notables sont observées depuis une décennie ; néanmoins certaines difficultés persistent, notamment dans les

  20. The liquid hydrogen cell in the EL3 Saclay reactor; Cellule a hydrogene liquide dans la pile EL3 de Saclay

    Energy Technology Data Exchange (ETDEWEB)

    Jacrot, B; Lacaze, A; Weil, L [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; [Grenoble-1 Univ., 38 (France)

    1960-07-01

    Description and results in connection with the liquid hydrogen cell, for obtaining slow neutrons, in the EL3. (author) [French] Description et resultats concernant la cellule a hydrogene liquide de EL3 utilisee pour obtenir des neutrons lents. (auteur)

  1. Effluent from Wastewater Treatment Plants

    DEFF Research Database (Denmark)

    Kristensen, Jannie Munk; Nierychlo, Marta; Albertsen, Mads

    Incoming microorganisms to wastewater treatment plants (WWTPs) are usually considered to be removed in the treatment process. Analyses of the effluent generally show a very high degree of reduction of pathogens supporting this assumption. However, standard techniques for detecting bacteria......-independent 16SrRNA gene amplicon sequencing was applied for the identification and quantification of the microorganisms. In total 84 effluent samples from 14 full-scale Danish wastewater treatment plants were investigated over a period of 3 months. The microbial community composition was investigated by 16S r...... contain pathogenic species. One of these was Arcobacter (Campylobacteraceae) which was found in up to 16% relative abundance. This indicates that Arcobacter, and perhaps other pathogenic genera, are not being removed efficiently in full-scale plants and may pose a potential health safety problem. Further...

  2. Study of atmospheric emissions from liquid and solid fuels burning facilities and from raw phosphate chemical treatment in Sfax City (Tunisia); Etude des residus de combustion des fuels liquide et solide et de traitement chimique du phosphate brut dans la ville de Sfax (Tunisie)

    Energy Technology Data Exchange (ETDEWEB)

    Azri, Ch; Tili, A.; Serbaji, M.M. [Faculte des Sciences de Sfax, Dept. des Sciences de la Terre, Sfax (Tunisia); Medhioub, K. [Institut Preparatoire aux Etudes d' Ingenieurs de Sfax (IPEIS), Sfax (Tunisia)

    2002-07-01

    Study of atmospheric emissions from solid and liquid fuels burning facilities and from chemical treatment processes of raw phosphate in Sfax City (Tunisia) shows different forms of pollution concerning mainly sulfur oxides (SO{sub x}), sulfuric and phosphoric acid mists, fluorinated compounds and dust. Limited performances of amortized and/or over used de-pollution systems can explain high atmospheric emissions above emission limits. Gaseous pollution has been shown as coming mainly from phosphate treatment processes inside the chemical complex 'SIAPE' while particulate pollution is coming from all specific industries (SIAPE, charcoal facilities and weaving and soap factories). Calculated emission factors of these industries for some heavy metals (Pb, Cd, Ni, Cu, Zn) are very different. They are ranging from 0.3 to 9.5 g/t for phosphate treatment residues. Excepted Ni with 15.5 g/t, they are rather small for heavy fuels combustion residues. It, nevertheless, exceeds the emission factor of Ni for the phosphate treatment process. Volumes of emissions and calculated annual fluxes of metals are showing that 'SIAPE' could be a potential source of atmospheric pollution in the city. Its contribution to metal emissions is really exceeding emissions from well identified heavy fuels burning facilities in the city. Just to compare, Ni emissions from its processes are equal to emissions from 38 heavy fuels burning facilities of 4.8 t/day capacity (Ni 1 046 kg/year instead of 27 kg/year). Such a fact is clearly pointing out the high level of anthropogenic pollution from chemical processes adopted for primary matter transformation. They hence should be fitted with suitable de-pollution systems. (authors)

  3. Continuous monitoring of gaseous effluents

    International Nuclear Information System (INIS)

    Velasco, A.; Giraut, H.; Prado, M.; Bonino, A.D.

    1990-01-01

    The system allows to continuously determine the radioactive materials discharge (iodine, noble gases and aerosols) to the environment. It consists in compelling, by a pump, a known and fixed fraction of the total flow and preserving the aerosols by a filter. The gas -now free from aerosols- traverses an activated carbon filter which keeps the iodine; after being free from aerosols and iodine, the effluent traverses a measurement chambers for noble gases which has a scintillator. (Author) [es

  4. Waste monitoring system for effluents

    International Nuclear Information System (INIS)

    Macdonald, J.M.; Gomez, B.; Trujillo, L.; Malcom, J.E.; Nekimken, H.; Pope, N.; Bibeau, R.

    1995-07-01

    The waste monitoring system in use at Los Alamos National Laboratory's Plutonium Facility, TA-55, is a computer-based system that proves real-time information on industrial effluents. Remote computers monitor discharge events and data moves from one system to another via a local area network. This report describes the history, system design, summary, instrumentation list, displays, trending screens, and layout of the waste monitoring system

  5. Optimum input leads for cryogenic apparatus; Optimisation des descentes de courant dans des enceintes cryogeniques

    Energy Technology Data Exchange (ETDEWEB)

    Der Nigohossian, G [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1967-02-15

    The electrical leads used to introduce a current into a cryostat cause a heat influx due to thermal conduction and to Joule heating. It is very important to be able to minimize this flux. Theoretical calculation of optimized leads takes into account the varying heat and electrical conductivities of the leads as well as the heat exchange coefficient with the effluent gas. Practical results have been summarized in different tables which permit for a specific material i.e. copper, aluminium, brass, stainless steel with the intensity and end temperatures being known (i.e. 4,2 or 18,5 deg. K at the cold end; 77,295 or 320 deg. K at the warm end) to deduce the minimum heat flow and the length-cross section ratio of the optimized leads. A general method is indicated, which would allow to solve the same problem for other materials. (author) [French] Les conducteurs electriques assurant la liaison d'appareillages situes dans des cryostats apportent tant par effet Joule que par conductibilite thermique une certaine quantite de chaleur qu'il est tres important de pouvoir minimiser. L'etude theorique de l'optimisation des descentes de courant tient compte des variations des conductibilites thermique et electrique ainsi que de l'influence des echanges avec le gaz. Pratiquement les resultats ont ete resumes dans differents tableaux ce qui permet, pour un materiau donne tel que cuivre, aluminium, laiton, acier inoxydable, connaissant l'intensite et les temperatures d'extremites 4,2 et 18,5 deg. K d'une part, et 77,295 et 330 deg. K d'autre part, de deduire la consommation minimale et le rapport longueur-section d'un conducteur optimise. Une methode generale est indiquee, qui permet de resoudre le probleme pour d'autres materiaux. (auteur)

  6. Radioactive Waste Facilities at the Australian Atomic Energy Commission Research Establishment; Installations pour le Traitement des Dechets Radioactifs au Centre de Recherche de la Commission Australienne a l'Energie Atomique; 0423 0421 0422 0414 ; Dispositivos para Evacuacion de Desechos Radiactivos en el Centro de Investigaciones de la Australian Atomic Energy Commission

    Energy Technology Data Exchange (ETDEWEB)

    Berglin, C. L.W.; Keher, L. H.; Miles, G. L.; Wilson, A. R.W. [Australian Atomic Energy Commission Research Establishment, Lucas Heights, Sydney, NSW (Australia)

    1960-07-01

    This paper describes the facilities,which are being provided for the collection, treatment and disposal of radioactive wastes at Lucas Heights in relation to the estimated arisings. Low-activity effluent is divided into three types: (a) Sewage; (b) Trades waste, arising from reactor cooling tower blow-down and engineering workshops and other inactive areas; and (c) Effluent arising from laboratories and other active areas. The effluent treatment plant for the latter type of effluent consists essentially of mixing and alkali dosing tanks, a sludge-blanket clarifier (using a calcium- iron-phosphate process) and holding tanks. Methods of concentrating the sludge and of secondary treatment are at present being investigated and are discussed. The discharge formula and the expected dilution obtained in the Woronora river are discussed, together with a dilution experiment carried out in the tidal waters. It is proposed to bury all low-activity solid waste after baling where appropriate and the choice and location of the disposal area is discussed. A facility for the storage and disposal of highly active solid waste is discussed. It is proposed to evaporate and store the medium- and high-activity liquid waste. Details are given of the capital and operating costs of the Effluent Treatment Plant and other waste handling facilities. (author) [French] Le memoire decrit les installations que le Centre de Lucas Heights cree a l'heure actuelle, eu egard au developpement envisage'en matiere de rassemblement, de traitement et d'elimination des dechets radioactifs. Les' effluents de faible activite se divisent en trois categories: a) Eaux d'egout; b) Dechets industriels provenant de la tour de refroidissement du reacteur, des ateliers et d'autres zones non-actives; c) Effluents provenant des laboratoires et d'autres zones actives. L'usine affectee au traitement du dernier type d'effluents se compose essentiellement de malaxeurs, de bacs de dosage d'alcalis, d'un clarificateur d

  7. Liquids and liquid mixtures

    CERN Document Server

    Rowlinson, J S; Baldwin, J E; Buckingham, A D; Danishefsky, S

    2013-01-01

    Liquids and Liquid Mixtures, Third Edition explores the equilibrium properties of liquids and liquid mixtures and relates them to the properties of the constituent molecules using the methods of statistical thermodynamics. Topics covered include the critical state, fluid mixtures at high pressures, and the statistical thermodynamics of fluids and mixtures. This book consists of eight chapters and begins with an overview of the liquid state and the thermodynamic properties of liquids and liquid mixtures, including vapor pressure and heat capacities. The discussion then turns to the thermodynami

  8. Gestion des risques

    CERN Document Server

    Louisot, Jean-Paul

    2009-01-01

    Depuis le début du lie siècle, la gestion des risques connaît une véritable révolution culturelle. Jusqu'alors fonction technique, centrée autour de l'achat de couverture d'assurances, elle est devenue une discipline managériale et transversale : une valise d'instruments que chaque manager doit connaître et appliquer quels que soient son domaine de compétence et ses missions au sein de l'organisation. En effet, la gestion des risques est une culture qui doit être assimilée par chacun des acteurs. C'est précisément l'ambition des 101 questions rassemblées dans cet ouvrage : apporter à chaque manager d'entreprise, de collectivité, d'établissement de santé..., des réponses claires au " pourquoi " et au " comment " : Comment identifier les risques ? Comment analyser les risques ? Quels sont les objectifs de la gestion des risques ? Une carte des risques pour quoi faire ? Pourquoi faut-il financer les risques ? Les entreprises ont-elles des responsabilités pénales ? En quoi consiste la gestion...

  9. Mechanical pumps for liquid metals; Pompes mecaniques pour metaux liquides

    Energy Technology Data Exchange (ETDEWEB)

    Baumier, J; Gollion, H J [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-07-01

    The pumping of liquid metals by centrifugal pumps poses two principal problems. These are hermetic sealing of the rotating shaft and, its guidance where immersed in liquid metal. The solutions to the problems used on 13 experimental pumps are given here. The resolution of the guidance problem consists in the majority of cases in the utilisation of hydrostatic bearings. Accordingly, a theoretical study was instituted for the first time to calculate the bearings of the earlier pumps. After this, an experimental study was carried out, to check the theory by water tests. A relation for bearing calculation of pumps with diffusers is proposed. Finally the influence of the bearing elasticity on the shafts critical speed is studied. (authors) [French] Le pompage des metaux liquides, par des pompes centrifuges, pose 2 principaux problemes, qui sont: d'une part, la realisation d'une excellente etancheite au passage de l'arbre, d'autre part, son guidage sur la partie immergee dans le metal liquide. Les solutions retenues pour resoudre ces problemes sur 13 pompes experimentees sont presentees. Le probleme du guidage de l'arbre, a dans la majorite des cas ete resolu en utilisant un palier hydrostatique, aussi l'etude en a d'abord ete approfondie de facon theorique pour calculer les paliers des premieres pompes, puis experimentale pour controler la theorie, en effectuant des essais a l'eau. On propose une relation pour calculer les paliers des pompes a diffuseurs. On a en outre effectue une etude de l'influence de l'elasticite du palier hydrostatique sur la vitesse critique de l'arbre. (auteurs)

  10. La gouvernance des risques naturels et la problematique des ...

    African Journals Online (AJOL)

    Depuis quelques années, la gouvernance des risques naturels dus aux inondations remet en cause les processus de mise en oeuvre des politiques urbaines et la qualité de la structure des aménagements dans les grandes villes du Golfe de Guinée. La perception de la gouvernance et l'application des politiques de ...

  11. Effluent Mixing Modeling for Liquefied Natural Gas Outfalls in a Coastal Ecosystem

    Directory of Open Access Journals (Sweden)

    Mustafa Samad

    2014-06-01

    Full Text Available Liquid Natural Gas (LNG processing facilities typically are located on ocean shores for easy transport of LNG by marine vessels. These plants use large quantities of water for various process streams. The combined wastewater effluents from the LNG plants are discharged to the coastal and marine environments typically through submarine outfalls. Proper disposal of effluents from an LNG plant is essential to retain local and regional environmental values and to ensure regulatory and permit compliance for industrial effluents. Typical outfall designs involve multi-port diffuser systems where the design forms a part of the overall environmental impact assessment for the plant. The design approach needs to ensure that both near-field plume dispersion and far-field effluent circulation meets the specified mixing zone criteria. This paper describes typical wastewater process streams from an LNG plant and presents a diffuser system design case study (for an undisclosed project location in a meso-tidal coast to meet the effluent mixing zone criteria. The outfall is located in a coastal and marine ecosystem where the large tidal range and persistent surface wind govern conditions for the diffuser design. Physical environmental attributes and permit compliance criteria are discussed in a generic format. The paper describes the design approach, conceptualization of numerical model schemes for near- and far-field effluent mixing zones, and the selected diffuser design.

  12. Characterization of secondary treated effluents for tertiary membrane filtration and water recycling

    KAUST Repository

    Ayache, C.; Pidou, Marc; Gernjak, Wolfgang; Poussade, Yvan; Croue, Jean-Philippe; Tazi-Pain, Annie; Keller, Jurg R.

    2012-01-01

    This study evaluates the impacts of water quality from three different secondary effluents on low pressure membrane fouling. Effluent organic matter (EfOM) has been reported by previous studies as responsible for membrane fouling. However, the contribution of the different components of EfOM to membrane fouling is still not well understood. In order to improve and optimize treatment processes, characterization and quantification of the organic matter are important. The characterization methods used in this study are liquid chromatography coupled with an organic detector (LC-OCD) and excitation emission matrix fluorescence spectroscopy (EEM). A bench-scale hollow fibre membrane system was used to identify the type of fouling depending on the feed water quality. Results showed no measurable dissolved organic carbon removal by the membranes for the three secondary effluents. Biopolymers and humic-like substances found in different proportions in the three effluents were partially retained by the membranes and were identified to contribute significantly to the flux decline of the low pressure membranes. The observed fouling was determined to be reversible by hydraulic backwashing for two effluents and only by chemical cleaning for the third effluent. © IWA Publishing 2012.

  13. Physico-chemical treatment of coke plant effluents for control of water pollution in India

    Energy Technology Data Exchange (ETDEWEB)

    Ghose, M.K. [Indian School of Mines, Dhanbad (India). Center of Mining Environmental

    2002-01-01

    Coal carbonizing industries in India are important and are growing every year. Large quantities of liquid effluents produced in this industry contain a large amount of suspended solids, high biochemical oxygen demand (BOD), chemical oxygen demand (COD), phenols, ammonia and other toxic substances, which are causing serious surface water pollution in the area. There is a large number of coke plants in the vicinity of Jharia Coal Field (JCF). The working principle of a coke plant and the effluents produced is described. One large coke plant was chosen to evaluate characteristics of the effluent and to suggest a proper treatment method. Present effluent treatment system was found to be inadequate and a large quantity of a very good quality coke breeze is being lost, which is also causing siltation on the riverbed in addition to surface water pollution. Physico-chemical treatment has been considered as a suitable option for the treatment of coke plant effluents. A scheme has been proposed for the treatment, which can be suitably adopted for the recycling, reuse or safe disposal of the treated effluent. Various unit process and unit operations are discussed. The process may be useful on industrial scale for various sites so as to maintain a clean environment.

  14. Characterization of secondary treated effluents for tertiary membrane filtration and water recycling

    KAUST Repository

    Ayache, C.

    2012-06-01

    This study evaluates the impacts of water quality from three different secondary effluents on low pressure membrane fouling. Effluent organic matter (EfOM) has been reported by previous studies as responsible for membrane fouling. However, the contribution of the different components of EfOM to membrane fouling is still not well understood. In order to improve and optimize treatment processes, characterization and quantification of the organic matter are important. The characterization methods used in this study are liquid chromatography coupled with an organic detector (LC-OCD) and excitation emission matrix fluorescence spectroscopy (EEM). A bench-scale hollow fibre membrane system was used to identify the type of fouling depending on the feed water quality. Results showed no measurable dissolved organic carbon removal by the membranes for the three secondary effluents. Biopolymers and humic-like substances found in different proportions in the three effluents were partially retained by the membranes and were identified to contribute significantly to the flux decline of the low pressure membranes. The observed fouling was determined to be reversible by hydraulic backwashing for two effluents and only by chemical cleaning for the third effluent. © IWA Publishing 2012.

  15. Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

    International Nuclear Information System (INIS)

    Shields, K.D.; Ballinger, M.Y.

    1999-03-01

    This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities

  16. Facility Effluent Monitoring Plan for the 325 Radiochemical Processing Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Shields, K.D.; Ballinger, M.Y.

    1999-04-02

    This Facility Effluent Monitoring Plan (FEMP) has been prepared for the 325 Building Radiochemical Processing Laboratory (RPL) at the Pacific Northwest National Laboratory (PNNL) to meet the requirements in DOE Order 5400.1, ''General Environmental Protection Programs.'' This FEMP has been prepared for the RPL primarily because it has a ''major'' (potential to emit >0.1 mrem/yr) emission point for radionuclide air emissions according to the annual National Emission Standards for Hazardous Air Pollutants (NESHAP) assessment performed. This section summarizes the airborne and liquid effluents and the inventory based NESHAP assessment for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements. The RPL at PNNL houses radiochemistry research, radioanalytical service, radiochemical process development, and hazardous and radioactive mixed waste treatment activities. The laboratories and specialized facilities enable work ranging from that with nonradioactive materials to work with picogram to kilogram quantities of fissionable materials and up to megacurie quantities of other radionuclides. The special facilities within the building include two shielded hot-cell areas that provide for process development or analytical chemistry work with highly radioactive materials and a waste treatment facility for processing hazardous, mixed radioactive, low-level radioactive, and transuranic wastes generated by PNNL activities.

  17. Solidification of Radioactive Waste Solutions; Solidification des Effluents Radioactifs; 041e 0422 0412 0415 0420 0416 0414 0415 041d 0418 0415 0420 0410 0414 0418 041e 0410 041a 0422 0418 0412 041d 042b 0425 0421 0411 0420 041e 0421 041d 042b 0425 0420 0410 0421 0422 0412 041e 0420 041e 0412 ; Solidificacion de Efluentes Radiactivos

    Energy Technology Data Exchange (ETDEWEB)

    Brezhneva, N. E.; Golovanov, Ju. N.; Oziraner, S. N.; Eremin, A. A.; Rozanova, V. N.

    1963-02-15

    This paper sets out the results of experimental development of a method for the solidifaction of radioactive waste solutions, based on the drying and vitrification of precipitates of iron-hydroxide obtained by settling from radioactive solutions. The solidification system is based on the principle of maximum reduction of the waste off-gases after removal of the aerosols and volatile radioactive components. The authors established optimum conditions to obtain a chemically stable glass and succeeded in lowering the temperature for the melting of the glass by modifying the fluxes added. An appreciable drop in the chemical stability of the glass was noted when it was stored for a long time at temperatures above 300 Degree-Sign - 350 Degree-Sign C. The authors studied the leachability of radiocaesium from the glass. They also investigated the volatility of radiocaesium and radio ruthenium in the course of drying and melting and showed that in an atmosphere of carbonic acid gas the volatility of ruthenium completely disappears. Hie volatility of radiocaesium in appreciable quantities becomes noticeable at temperatures above 700 Degree-Sign C and increases as the temperature rises. It is shown that radiocaesium condenses in the drainage tubes at temperatures below 400 Degree-Sign C and is easily washed off by weak solutions of nitric acid and water. Calculations of the heat release from radioactive glass show that the radius of globular glass castings from high-activity materials (10 c/g) must not exceed 25 cm. The paper includes the flowsheet for a process for the drying and vitrification of radioactive sludge by means of a gas- and heat-remover, together with details of the apparatus required. (author) [French] Les auteurs exposent les resultats des recherches qu'ils ont faites, dans leur laboratoire, pour mettre au point une methode de solidification des effluents radioactifs, fondee sur la dessiccation et la vitrification de l'hydroxyde de fer, obtenu par

  18. Effluent treatment for nuclear thermal propulsion ground testing

    Science.gov (United States)

    Shipers, Larry R.

    1993-01-01

    The objectives are to define treatment functions, review concept options, discuss PIPET effluent treatment system (ETS), and outline future activities. The topics covered include the following: reactor exhaust; effluent treatment functions; effluent treatment categories; effluent treatment options; concept evaluation; PIPETS ETS envelope; PIPET effluent treatment concept; and future activities.

  19. Detritiation of Tritiated Effluent Gas and Water

    International Nuclear Information System (INIS)

    Ahn, Do Hee; Kim, Kwang Rag; Paek, Seung Woo; Lee, Min Soo; Yim, Sung Paal; Chung Hong Suk

    2007-06-01

    In a demonstration scale equipment for treatment of tritium in off-gas, Pt/SDBC as oxidation catalyst and Zeolite 13X as adsorbent was charged in the beds, respectively. It was confirmed from the performance test that decontamination factor of the equipment showed more than 100 under the flow rate of off-gas of 90 l/hr and at the temperature of 65 ∼ 80 .deg. C. A small scale CECE process has been developed combining LPCE catalytic column with SPE (solid polymer electrolyte) electrolysis. The catalytic column was a trickle-bed type packed with the mixture of 1 wt% Pt/SDBC catalyst and 4 mm Dixon wire-mesh ring. The experimental results of the CECE process proved that the decontamination factor of 13 ∼ 20 under the operating conditions of the water of the 4 l/day and the effluent hydrogen gas of 16.2 mol/h. A design code of CECE process also developed which will be applied the tritium industry. An experimental method for the reduction of tritiated organic waste by using catalytic oxidation was tested in a heated catalytic reactor of 0.5 wt% Pd/Al 2 O 3 . The simulated organic liquid was converted to water over 99%. A gas chromatographic column material was developed for the separation of mixed hydrogen isotopes. 17 wt% Pd-Pt on alumina showed 90% separation efficiency at 77 % yield for the separation of 29.2 % D 2 -H 2 gas mixture

  20. Facility Effluent Monitoring Plan for the 284-E and 284-W power plants

    International Nuclear Information System (INIS)

    Herman, D.R.

    1991-11-01

    A facility effluent monitoring plan is required by the US Department of Energy in DOE Order 5400.1 for any operations that involve hazardous materials and radioactive substances that could impact employee or public safety or the environment. This document is prepared using the specific guidelines identified in A Guide for Preparing Hanford Site Facility Effluent Monitoring Plans, WHC-EP- 0438. This facility effluent monitoring plan assesses effluent monitoring systems and evaluates whether they are adequate to ensure the public health and safety as specified in applicable federal, state, and local requirements. This facility effluent monitoring plan is the first annual report. It shall ensure long-range integrity of the effluent monitoring systems by requiring an update whenever a new process or operation introduces new hazardous materials or significant radioactive materials. This document must be reviewed annually even if there are no operational changes, and it must be updated as a minimum every three years. The 284-E and 284-W Power Plants are coal-fired plants used to generate steam. Electricity is not generated at these facilities. The maximum production of steam is approximately 159 t (175 tons)/h at 101 kg (225 lb)/in 2 . Steam generated at these facilities is used in other process facilities (i. e., the B Plant, Plutonium-Uranium Extraction Plant, 242-A Evaporator) for heating and process operations. The functions or processes associated with these facilities do not have the potential to generate radioactive airborne effluents or radioactive liquid effluents, therefore, radiation monitoring equipment is not used on the discharge of these streams. The functions or processes associated with the production of steam result in the use, storage, management and disposal of hazardous materials

  1. Radiation treatment of sewage effluent, (2)

    International Nuclear Information System (INIS)

    Sawai, Teruko; Sekiguchi, Masayuki; Sawai, Takeshi; Shimokawa, Toshinari; Tanabe, Hiroko

    1991-01-01

    The water demand of the past several years has increased rapidly. Recycling of municipal waste water is an effective mean of coping with the water shortage in Tokyo. We studied the radiation treatment method of further purification of the effluent from sewage treatment plants. By gamma irradiation the refractory organic substances in the effluent were decomposed and the COD values decreased with increasing dose. The high molecular weight components in the effluent were degraded to lower molecular weight substances and were decomposed finally to carbon dioxide. In this paper we studied on the fading color and the reducing of order of sewage effluent. (author)

  2. Removal of radium-226 from uranium mining effluents

    International Nuclear Information System (INIS)

    Averill, D.W.; Moffett, D.; Webber, R.T.; Whittle, L.; Wood, J.A.

    1984-12-01

    Uranium mining and milling operations usually generate large quantities of solid and liquid waste materials. A slurry, consisting of waste rock and chemical solutions from the milling operation, is discharged to impoundment areas (tailings basins). Most of the radioactive material dissolved in tailings slurries is precipitated by the addition of lime and limestone prior to discharge from the mill. However, the activity of one radioisotope, radium-226, remains relatively high in the tailings basin effluents. In Canada, radium-226 is removed from uranium mining and milling effluents by the addition of barium chloride to precipitate barium-radium sulphate [(Ba,Ra)SO 4 ]. Although dissolved radium-226 activities are generally reduced effectively, the process is considered to have two undesirable characteristics: the first related to suspended radium-226 in the effluents and the second to ultimate disposal of the (Ba,Ra)SO 4 sludge. A government-industry mining task force established a radioactivity sub-group in 1974 to assist in the development of effluent guidelines and regulations for the uranium mining industry (Radioactivity Sub-group, 1974). The investigation of more effective removal methods was recommended, including the development of mechanical treatment systems as alternatives to settling ponds. Environment Canada's Wastewater Technology Centre (WTC) initiated a bench scale study in March, 1976 which was designed to assess the feasibility of using precipitation, coagulation, flocculation and sedimentation for the removal of radium-226. In 1977, the study was accelerated with financial assistance from the Atomic Energy Control Board. The results were favourable, with improved radium removals obtained in bench scale batch tests using barium chloride as the precipitant and either alum or ferric chloride as the coagulant. A more comprehensive bench scale and pilot scale process development and demonstration program was formulated. The results of the joint study

  3. Selective catalytic reduction of nitrogen oxides from industrial gases by hydrogen or methane; Reduction catalytique selective des oxydes d'azote (NO{sub x}) provenant d'effluents gazeux industriels par l'hydrogene ou le methane

    Energy Technology Data Exchange (ETDEWEB)

    Engelmann Pirez, M

    2004-12-15

    This work deals with the selective catalytic reduction of nitrogen oxides (NO{sub x}), contained in the effluents of industrial plants, by hydrogen or methane. The aim is to replace ammonia, used as reducing agent, in the conventional process. The use of others reducing agents such as hydrogen or methane is interesting for different reasons: practical, economical and ecological. The catalyst has to convert selectively NO into N{sub 2}, in presence of an excess of oxygen, steam and sulfur dioxide. The developed catalyst is constituted by a support such as perovskites, particularly LaCoO{sub 3}, on which are dispersed noble metals (palladium, platinum). The interaction between the noble metal and the support, generated during the activation of the catalyst, allows to minimize the water and sulfur dioxide inhibitor phenomena on the catalytic performances, particularly in the reduction of NO by hydrogen. (O.M.)

  4. Particulate COD balance of particulate cod in eletrocuagulation/flotation reactor treating tannery effluent

    Directory of Open Access Journals (Sweden)

    Rodrigo Babora Borri

    2012-04-01

    Full Text Available Mass balance or particulate organic matter was studied in terms of COD, by means of electrocoagulation/flotation (ECF reactor treating tannery effluent. Reactor was operated in fill and draw (batch mode. Operating in hydraulic residence time of 65 minutes, ECF reactor reached 55 % COD removal. Although volatile solids were also removed from liquid phase (removal of 40%, fixed solids concentration, and hence total solids concentration, showed to be higher in withdrawn effluent than in ECF’s influent. This was assigned to NaCl added in order to enhance conductivity in wastewater.

  5. The exposure of the EC (European Community) population from nuclear industry effluents

    International Nuclear Information System (INIS)

    Broomfield, M.

    1983-01-01

    The collective dose commitment to the EC population from routine effluents released from nuclear power stations and reprocessing plants within the Community in 1978 amounted to approximately 500 man Sv. The collective dose commitments associated with discharges from the nuclear power stations was approximately 50 man Sv, being almost entirely due to airborne carbon-14. The total collective dose commitment from the reprocessing plants was approximately 450 man Sv, about two-thirds of which was due to radiocaesium in the liquid effluent from Sellafield. (UK)

  6. Closure report for CAU 93: Area 6 steam cleaning effluent ponds, Nevada Test Site. Volume 1

    International Nuclear Information System (INIS)

    1997-12-01

    The Steam Cleaning Effluent Ponds (SCEP) waste unit is located in Area 6 at the Nevada Test Site. The SCEPs are evaporation basins formerly used for the disposal of untreated liquid effluent discharged from steam cleaning activities associated with Buildings 6-623 and 6-800. This closure report documents the strategy and analytical results that support the clean closure or closure in place of each of the components within CAU 93. In addition, the report documents all deviations from the approved closure plan and provides rationale for all deviations

  7. Photonique des Morphos

    CERN Document Server

    Berthier, Serge

    2010-01-01

    La photonique est déjà présente dans notre vie quotidienne, et on attend maintenant que la manipulation des photons permette aussi le traitement logique des informations. Cependant, l’élément de base qui permet cette manipulation de la lumière, le cristal photonique, est d’une réalisation complexe et mal contrôlée. Dans la course à la maîtrise de la lumière, les structures photoniques naturelles ont beaucoup à nous apprendre. C’est ce que nous montre Serge Berthier qui étudie dans ce livre la structure des écailles des Morphos. Tenant compte de l’essor récent des approches biomimétiques, il présente de manière détaillée plus de dix-huit techniques expérimentales utilisées pour ses analyses, ainsi que les diverses approches théoriques développées pour la modélisation de structures multi-échelles complexes. Première étude quasi-exhaustive des structures fines d’un genre et des propriétés optiques ainsi que colorimétriques générées, ce livre fournit aux entomologiste...

  8. Droit des organisations internationales

    CERN Document Server

    Sorel, Jean-Marc; Ndior, Valère

    2013-01-01

    Cet ouvrage collectif offre aux enseignants et chercheurs en droit international, aux praticiens et aux étudiants, une analyse actualisée du droit des organisations internationales. Il dresse en cinq parties un tableau, illustré par des exemples variés, des problématiques que soulève le phénomène polymorphe d institutionnalisation de la société internationale. La première partie est consacrée au phénomène des « organisations internationales », sous l angle à la fois de l institutionnalisation progressive des relations internationales et de la difficulté à cerner une catégorie unifiée. La deuxième partie rend compte de la création, de la disparition et des mutations des organisations internationales, ici envisagées comme systèmes institutionnels et ordres juridiques dérivés. La troisième partie analyse l autonomie que l acquisition de la personnalité juridique et de privilèges et immunités, un organe administratif intégré, un personnel ou un budget propres confèrent aux organi...

  9. [Influence of diethyl sulfate (DES) mutagenesis on growth properties and pigment secondary metabolites of Phellinus igniarius].

    Science.gov (United States)

    Wang, Jing; Wu, Xin-yuan; Ma, Wei; Chen, Jing; Liu, Cheng; Wu, Xiu-li

    2015-06-01

    The diethyl sulfate (DES) mutagenesis was chosen for the mutagenic treatment to Phellinus igniarius, and the relationship of mutagenesis time and death rate was investigated with 0.5% DES. The differences of mycelial growth speed, liquid fermentation mycelia biomass, morphology and pigment classes of secondary metabolites production speed and antioxidant activities of metabolite products were discussed. The study displayed that DES mutagenesis could change mycelial morphology without obvious effect on mycelium growth, and the DES mutagenesis improved antioxidant activities of the active ingredients of P. igniarius and had more antioxidant activity of hypoxia/sugar PC12 nerve cells than that of P. igniarius.

  10. Revision of by-laws about effluents of EdF's nuclear power plants

    International Nuclear Information System (INIS)

    2002-01-01

    In France, in application of the clean water law from January 3, 1992 and since the decree 95-540 from May 4, 1995, each basic nuclear facility receives a single permission which covers both its water takes and its radioactive and non-radioactive effluents. This decree, initially dedicated to new facilities has been enlarged to all existing installations for which the prefectorial by-laws have reached their date-line. Thus, up to now, five inter-ministerial by-laws have renewed the permissions of water takes and effluents evacuation of the power plants of Saint-Laurent-des-Eaux (Loir-et-Cher), Flamanville (Manche), Paluel (Seine-Maritime), Belleville (Cher) and Saint-Alban (Isere). These by-laws foresee an important abatement of the effluents and concern more particularly the tritium, 14 C, the iodine isotopes and also some other non-radioactive chemical compounds. This document is a compilation of all revised by-laws about effluents and concerning the nuclear power plants listed above. (J.S.)

  11. The Comparative Accuracy of the 4 {pi} Liquid Scintillation Counting Method of Radioisotope Standardization; L'exactitude comparee de la methode de comptage 4 {pi} a scintillateurs liquides pour l'etalonnage des radioisotopes; Sravnitel'naya tochnost' 4 {pi} zhidkogo stsintillatsionnogo metoda podscheta standartiziruemykh radioizotopov; Exactitud del metodo de recuento con centelleador liquido 4 {pi} para normalizar radioisotopos, comparada con la de otros metodos

    Energy Technology Data Exchange (ETDEWEB)

    Steyn, J [National Physical Research Laboratory, Pretoria (South Africa)

    1960-06-15

    The accuracy of the 4 {pi} liquid scintillation counting method of standardizing {beta} emitters was compared to 4 l{pi} {beta}-{gamma} coincidence counting for the nuclides Co{sup 60}, I{sup 131} and Au{sup 198}. For P{sup 32} the liquid counting results were compared to 4 {pi} proportional counting. The efficiency of the liquid scintillation counting method was found to be energy dependent, dropping to about 97.5% for Co{sup 60} which was the lowest energy {beta} emitter investigated. (author) [French] La precision de la methode de comptage 4 {pi} a scintillateurs liquides pour l'etalonnage des emetteurs {beta} a ete comparee au comptage par coincidences 4 {pi} {beta}-{gamma} pour le So{sup 60}, le I{sup 131} et le Au{sup 198}. Dans le cas du P{sup 32}, les resultats du comptage au liquide ont ete compares a ceux du comptage 4 {pi} proportionnel. On a constate que le rendement de la methode de comptage a scintillateurs liquides variait en fonction de l'energie emise et qu'il descendait a environ 97.5% pour le Co{sup 60} qui, de tous les emetteurs {beta} etudies, emet l'energie la plus faible. (author) [Spanish] El autor compara la precision del metodo de recuento con centelleador iquido 4 {pi} para normalizar emisores {beta} con la del metodo de coincidencias {beta}-{gamma} 4 {pi}, para los siguientes nuclidos: So{sup 60}, I{sup 131} y Au{sup 198}. En el caso del P{sup 32}, confronta los resultados del primer metodo con los obtenidos mediante el recuento proporcional 4 {pi}. Comprueba que la eficacia del metodo de recuento con centelleador liquido depende de la energia y desciende al 97.5%, aproximadamente, para el Co{sup 60}, que fue el emisor {beta} mas debil que se investigo. (author) [Russian] Tochnost' 4 {pi} zhidkogo stsintillyatsionnog o metoda podscheta standartiziruemogo {beta}-izluchatelya sravnivalas' s 4 {pi} {beta}-{gamma} metodom podscheta na sovpadeniyakh dlya izotopov So{sup 60}, I{sup 131} i Au{sup 198}. Dlya R{sup 32} rezultaty zhidkogo

  12. Cytogenotoxicity evaluation of two industrial effluents using Allium ...

    African Journals Online (AJOL)

    ISHIOMA

    textile effluent was 4.5 times more toxic than the paint effluent. ... Key words: Genotoxicity, paint, textile, industrial effluents, Allium cepa, mutation, pollution, chromosomal .... concentration of a chemical producing 50% of the total effect).

  13. An automation model of Effluent Treatment Plant

    Directory of Open Access Journals (Sweden)

    Luiz Alberto Oliveira Lima Roque

    2012-07-01

    Full Text Available Population growth and intensification of industrial activities have increased the deterioration of natural resources. Industrial, hospital and residential wastes are dumped directly into landfills without processing, polluting soils. This action will have consequences later, because the liquid substance resulting from the putrefaction of organic material plows into the soil to reach water bodies. Cities arise without planning, industrial and household wastes are discharged into rivers, lakes and oceans without proper treatment, affecting water resources. It is well known that in the next century there will be fierce competition for fresh water on the planet, probably due to the scarcity of it. Demographic expansion has occurred without proper health planning, degrading oceans, lakes and rivers. Thus, a large percentage of world population suffers from diseases related to water pollution. Accordingly, it can be concluded that sewage treatment is essential to human survival, to preserve rivers, lakes and oceans. An Effluent Treatment Plant (ETP treats wastewater to reduce its pollution to acceptable levels before sending them to the oceans or rivers. To automate the operation of an ETP, motors, sensors and logic blocks, timers and counters are needed. These functions are achieved with programmable logic controllers (PLC and Supervisory Systems. The Ladder language is used to program controllers and is a pillar of the Automation and Control Engineering. The supervisory systems allow process information to be monitored, while the PLC are responsible for control and data acquisition. In the age we live in, process automation is used in an increasing scale in order to provide higher quality, raise productivity and improve the proposed activities. Therefore, an automatic ETP will improve performance and efficiency to handle large volumes of sewage. Considering the growing importance of environmental awareness with special emphasis

  14. Environmental and effluent monitoring at ANSTO sites, 2004-2005

    International Nuclear Information System (INIS)

    Hoffmann, Emmy L.; Loosz, Tom; Ferris, John M.; Harrison, Jennifer J.

    2005-01-01

    This report presents the results of ANSTO's environmental and effluent monitoring at the Lucas Heights Science and Technology Centre (LHSTC) and the National Medical Cyclotron (NMC) sites, from July 2004 to June 2005. Effective doses to the critical group of members of the public potentially affected by routine airborne emissions from the LHSTC were less than 0.005 mSv/year. This estimated maximum potential dose is less than 24% of the ANSTO ALARA objective of 0.02 mSv/year, and much lower than the public dose limit of 1 mSv/year that is recommended by the Australian Radiation Protection and Nuclear Safety Agency (ARPANSA). The effective doses to the critical group of members of the public potentially exposed to routine liquid effluent releases from the LHSTC have been realistically estimated as a quarter (or less) of the estimated doses to the critical group for airborne releases. The levels of tritium detected in groundwater and stormwater at the LHSTC were less than those set out in the Australian Drinking Water Guidelines. The airborne and liquid effluent emissions from the NMC were below both the ARPANSA-approved notification levels and Sydney Water limits for acceptance of trade wastewater to sewer. Results of environmental monitoring at both ANSTO sites confirm that the facilities continue to be operated well within regulatory limits. ANSTO's routine operations at the LHSTC and NMC make only a very small addition to the natural background radiation dose of ∼1.5 mSv/year experienced by members of the Australian public

  15. Dresses problems arising from hot-plant operation and their solution (1961); Les problemes vestimentaires poses par l'exploitation des installations actives et leurs solutions (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J; Bouzigues, H; Boutot, P [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1961-07-01

    acceleree en periode d'incidents doivent etre traites comme le linge des centres hospitaliers. Le lavage du linge par le procede allemand du contre-courant (systeme Sulzman) se revele un procede precieux par les cadences rapides qu'il permet et, surtout, par sa faible production d'effluents liquides. Le nettoyage a sec est une technique d'avenir qui s'avere encore plus economique. Dans une laverie active, le controle des vetements traites du point de vue de la contamination residuaire peut constituer un serieux goulet d'etranglement a la production du linge propre s'il n'est pas solutionne par l'utilisation de machines automatiques a cadence rapide. Le risque encouru par le personnel d'exploitation est uniquement la contamination de l'atmosphere et des surfaces. A ce titre, l'installation doit etre traitee comme une zone active dans laquelle sont manipules journellement quelques dizaines de millicuries d'emetteurs dangereux et quelques microcuries de plutonium. (auteurs)

  16. Dresses problems arising from hot-plant operation and their solution (1961); Les problemes vestimentaires poses par l'exploitation des installations actives et leurs solutions (1961)

    Energy Technology Data Exchange (ETDEWEB)

    Rodier, J.; Bouzigues, H.; Boutot, P. [Commissariat a l' Energie Atomique, Centre de Production de Plutonium, Marcoule (France). Centre d' Etudes Nucleaires

    1961-07-01

    renouveles a cadence acceleree en periode d'incidents doivent etre traites comme le linge des centres hospitaliers. Le lavage du linge par le procede allemand du contre-courant (systeme Sulzman) se revele un procede precieux par les cadences rapides qu'il permet et, surtout, par sa faible production d'effluents liquides. Le nettoyage a sec est une technique d'avenir qui s'avere encore plus economique. Dans une laverie active, le controle des vetements traites du point de vue de la contamination residuaire peut constituer un serieux goulet d'etranglement a la production du linge propre s'il n'est pas solutionne par l'utilisation de machines automatiques a cadence rapide. Le risque encouru par le personnel d'exploitation est uniquement la contamination de l'atmosphere et des surfaces. A ce titre, l'installation doit etre traitee comme une zone active dans laquelle sont manipules journellement quelques dizaines de millicuries d'emetteurs dangereux et quelques microcuries de plutonium. (auteurs)

  17. Towards zero discharge by integrated effluent treatment approach

    International Nuclear Information System (INIS)

    Rath, Ashish Kumar; Pattnaik, Sambhu Prasad; Pati, Ganeswar; Saha, Sushant; Viswanath, Kowtha

    2014-01-01

    Heavy Water Plant, Talcher houses two Organo-phosphorus Solvent Production Plants namely, 60 MTPY TBP Plant engaged in the production of Tri-n-Butyl Phosphate and Versatile Solvent Production Plant (VSPP) capable of producing various Organo Phosphorus Solvents namely, 100 MTPY D2EHPA (Di-2-Ethyl Hexyl Phosphoric Acid), or 40 MTPY TAPO (Tri-Alkyl Phosphine Oxide) or TOPO (Tri-n-Octyl Phosphine Oxide) or DNPPA (Di-Nonyl Phenyl Phosphoric Acid). These solvents have important application for separation duties in front and back end of nuclear fuel cycle and also in conventional hydrometallurgy for separation metals like Ni, Cu, Zn, Co etc., both of these plants are first of their kind in India designed by the Heavy Water Board, Mumbai with R and D inputs from BARC. The two plants employ esterification (1) process between PCl 3 / and a suitable oxo-alcohol followed by hydrolysis, neutralization and product purification. The second and third steps find large usage of Water, which eventually surface as liquid effluent. All the gaseous emissions from plants, mostly HCl gas are traded off for Saline Water as liquid effluent by scrubbing the same with Sodium Hydroxide Solution

  18. Santé des adolescents et des jeunes au Burkina Faso : état des ...

    African Journals Online (AJOL)

    Il s'est agi d'une étude évaluative ayant utilisé une revue documentaire associée à une interview des acteurs clés et un atelier de validation et d'identification des interventions pertinentes pour un plan stratégique national. La situation de la santé des adolescents et des jeunes est caractérisée par des grossesses précoces ...

  19. Elimination of liquid discharge to the environment from the TA-50 Radioactive Liquid Waste Treatment Facility

    International Nuclear Information System (INIS)

    Moss, D.; Williams, N.; Hall, D.; Hargis, K.; Saladen, M.; Sanders, M.; Voit, S.; Worland, P.; Yarbro, S.

    1998-06-01

    Alternatives were evaluated for management of treated radioactive liquid waste from the radioactive liquid waste treatment facility (RLWTF) at Los Alamos National Laboratory. The alternatives included continued discharge into Mortandad Canyon, diversion to the sanitary wastewater treatment facility and discharge of its effluent to Sandia Canyon or Canada del Buey, and zero liquid discharge. Implementation of a zero liquid discharge system is recommended in addition to two phases of upgrades currently under way. Three additional phases of upgrades to the present radioactive liquid waste system are proposed to accomplish zero liquid discharge. The first phase involves minimization of liquid waste generation, along with improved characterization and monitoring of the remaining liquid waste. The second phase removes dissolved salts from the reverse osmosis concentrate stream to yield a higher effluent quality. In the final phase, the high-quality effluent is reused for industrial purposes within the Laboratory or evaporated. Completion of these three phases will result in zero discharge of treated radioactive liquid wastewater from the RLWTF

  20. Elimination of liquid discharge to the environment from the TA-50 Radioactive Liquid Waste Treatment Facility

    Energy Technology Data Exchange (ETDEWEB)

    Moss, D.; Williams, N.; Hall, D.; Hargis, K.; Saladen, M.; Sanders, M.; Voit, S.; Worland, P.; Yarbro, S.

    1998-06-01

    Alternatives were evaluated for management of treated radioactive liquid waste from the radioactive liquid waste treatment facility (RLWTF) at Los Alamos National Laboratory. The alternatives included continued discharge into Mortandad Canyon, diversion to the sanitary wastewater treatment facility and discharge of its effluent to Sandia Canyon or Canada del Buey, and zero liquid discharge. Implementation of a zero liquid discharge system is recommended in addition to two phases of upgrades currently under way. Three additional phases of upgrades to the present radioactive liquid waste system are proposed to accomplish zero liquid discharge. The first phase involves minimization of liquid waste generation, along with improved characterization and monitoring of the remaining liquid waste. The second phase removes dissolved salts from the reverse osmosis concentrate stream to yield a higher effluent quality. In the final phase, the high-quality effluent is reused for industrial purposes within the Laboratory or evaporated. Completion of these three phases will result in zero discharge of treated radioactive liquid wastewater from the RLWTF.

  1. Water feed and effluent treatment for hydrogen sulfide-water system

    International Nuclear Information System (INIS)

    Spevack, J.S.

    1981-01-01

    This invention provides a feed and effluent treatment system for improving the recovery of a gas (e.g. H 2 S) from solution in a liquid (e.g. water) when the liquid also contains dissolved nonvolatile components (e.g. the salts of sea water) at low temperatures. In a gas/liquid contact process in which the gas is at least partially soluble in the liquid, a portion of the liquid is extracted after it passes through a hot zone, the pressure of the liquid is reduced by flashing it through pressure reduction means to remove a portion of the dissolved gas, and the gas thus recovered is returned to the process

  2. Effluent management and pollution control

    International Nuclear Information System (INIS)

    Ananda Narayanan, R.; Vedamoorthy, S.

    2006-01-01

    Generation of waste/effluent has a direct impact on environment, the higher the generation of waste higher the environmental impact. Though complete prevention of radioactive waste generation is a difficult task, keeping the waste generation to the minimum practicable is essential objective of Radioactive Waste Management. In doing so, it is essential to minimize waste generation at all the stages of a Nuclear Plant Cycle. Waste minimization refers to both a) Waste generation by operational and maintenance activities of plant and b) Secondary waste resulting from predisposal management of Radioactive Waste. The management of the effluent can be done in efficient manner by better designs, improved procedure, periodic reviews and above all inculcate the awareness amongst the waste generators since minimisation of waste, at source is the most efficient way to safe guard the environment. Commissioning and rich operating experience of waste management plant gather novel ideas which result in beneficial improvements in the system and operating procedure. Some of the steps initiated by designers and site agencies towards this are worth mentioning. (author)

  3. Bioremediation of petroleum refinery effluent by Planococcus ...

    African Journals Online (AJOL)

    In the present investigation, Planococcus halophilus was screened for hydrocarbon degradation and bioremediation of refinery effluent. The test organism, P. halophilus, showed the capability to utilize kerosene as carbon source in minimal medium. Biological treatment of the refinery effluent with P. halophilus reduced the ...

  4. 324 and 327 Facilities Environmental Effluent Specifications

    International Nuclear Information System (INIS)

    JOHNSON, D.L.

    1999-01-01

    These effluent specifications address requirements for the 324/321 Facilities, which are undergoing stabilization activities. Effluent specifications are imposed to protect personnel, the environment and the public, by ensuring adequate implementation and compliance with federal and state regulatory requirements and Hanford programs

  5. Animal alternatives for whole effluent toxicity testing ...

    Science.gov (United States)

    Since the 1940s, effluent toxicity testing has been utilized to varying degrees in many countries to assess potential ecological impacts and assist in determining necessary treatment options for environmental protection. However, it was only in the early 1980’s that toxicity based effluent assessments and subsequent discharge controls became globally important, when it was recognized that physical and chemical measurements alone did not protect the environment from potential impacts. Consequently, various strategies using different toxicity tests, whole effluent assessment techniques (incorporating bioaccumulation potential and persistence) plus supporting analytical tools have been developed over 30 years of practice. Numerous workshops and meetings have focused on effluent risk assessment through ASTM, SETAC, OSPAR, UK competent authorities, and EU specific country rules. Concurrent with this drive to improve effluent quality using toxicity tests, interest in reducing animal use has risen. The Health and Environmental Sciences Institute (HESI) organized and facilitated an international workshop in March 2016 to evaluate strategies for concepts, tools, and effluent assessments and update the toolbox of for effluent testing methods. The workshop objectives were to identify opportunities to use a suite of strategies for effluents, and to identify opportunities to reduce the reliance on animal tests and to determine barriers to implementation of new methodologie

  6. Dental Encounter System (DES)

    Data.gov (United States)

    Department of Veterans Affairs — Dental Encounter System (DES) is an automated health care application designed to capture critical data about the operations of VA Dental Services. Information on...

  7. Diethylstilbestrol (DES) and Cancer

    Science.gov (United States)

    ... DES-exposed grandchildren have? Researchers are also studying possible health effects among women and men who are the children ... for unexposed men. In addition, researchers are studying possible health effects on the grandchildren of mothers who were exposed ...

  8. Table des illustrations

    OpenAIRE

    2016-01-01

    Tableaux Dates d’inauguration des grands hôtels japonais entre 1860 et 1945… 19 Histoire, tourisme et hôtellerie en Corée depuis les années 1870… 59-60 Dates d’inauguration des grands hôtels chinois depuis 1863… 84 Les hôtels de luxe et leurs capacités d’hébergement en Corée en 2000… 103 Les flux de personnes suscités par les hôtels « super luxe » de Séoul en 2000… 105 L’activité des grands hôtels à Séoul en 1999 (en wons)… 106 Propriété et gestion des grands hôtels à Séoul en 1999…. 110 La c...

  9. Direction des Publications

    African Journals Online (AJOL)

    Synthese

    potential and surface properties of their mixtures were investigated, in an ... suppose that the electrostatic repulsive interactions between the two anion ... concentration, et de la conformation des ..... proteins and polysaccharides in solutions,.

  10. Angra-1 NPP thermal influence on liquid effluent discharge zone

    International Nuclear Information System (INIS)

    Costa, Daniel de Araujo

    1996-01-01

    The Angra I Nuclear Power Plant makes use of sea-water to condense the steam generated in its secondary circuit. This water, collected from Itaorna bay, is then chlorinated and discharged, with higher temperature, in the Piraquara de Fora bay. Aiming the study of the marine ecosystem, submitted to the effects of the Nuclear Power Plant discharge water, the temperature, residual chlorine, flora and fauna are periodically monitored. Being sensitive to temperature variations and to chemical products, macroscopic algae are also bio-accumulators and primary producers, because of this, they are considered the main link in the food chain and therefore important bio-indicator. This paper shows the variation of species from the brown algae near the discharge of Angra I Nuclear Power Plant. (author)

  11. EPA Enforcement and Compliance History Online: Water Effluent Charts Details

    Data.gov (United States)

    U.S. Environmental Protection Agency — Detailed Discharge Monitoring Report (DMR) data supporting effluent charts for one Clean Water Act discharge permit. Includes effluent parameters, amounts discharged...

  12. Etude theorique et experimentale des evaporateurs de dioxyde de carbone operant dans des conditions de givrage

    Science.gov (United States)

    Bendaoud, Adlane Larbi

    . Dans la partie theorique, un modele traitant les aspects thermique, hydrodynamique et massique a ete elabore. Sur la base de ce modele a ete ecrit un programme informatique en langage FORTRAN 6.6. Il est base sur la discretisation du serpentin en volumes de controle, est entierement automatise et peut traiter des echangeurs de chaleur avec des circuits de refrigerant complexes pouvant avoir des entrees et sorties multiples ainsi que des bifurcations. La presence simultanee des trois phases thermodynamiques du refrigerant (liquide sous refroidi, fluide sature, vapeur surchauffee) dans le serpentin est aussi prise en charge. Le modele a ete valide pour un fonctionnement avec et sans formation de givre en utilisant des donnees experimentales disponibles dans la litterature et celles obtenues sur le banc d'essai de CanmetENERGIE. Celui-ci a ete mis a jour pour les besoins de la presente recherche et pour cela, un systeme de surchauffe et d'injection de la vapeur d'eau dans une enceinte a tres basse temperature a ete dimensionne, fabrique et installe. Un dispositif de visualisation de la formation de givre, ainsi qu'un equipement de mesure de la temperature, de la pression et de l'humidite relative de l'air ont aussi ete ajoutes. Une fois le modele valide, des simulations numeriques sur le serpentin avec et sans formation de givre ont ete effectuees. Un premier cas de base a servi comme reference pour d'autres cas pour lesquels une etude parametrique sur la geometrie et le fonctionnement a ete menee. Il a ete montre par rapport au cas de base que : 1. la diminution de la densite des ailettes sur des rangees specifiques du serpentin donne une surface minimale (Amin) plus grande, retardant ainsi l'obstruction totale du serpentin par le givre et permet donc un temps de fonctionnement plus grand et une frequence de degivrage plus faible. 2. une bonne configuration de circuit de refrigerant augmente le temps de fonctionnement du serpentin de 200 % et delivre une puissance

  13. La revolution des savants

    CERN Document Server

    Chavanne, A

    1989-01-01

    Premiere cassette : - 1666 : impact de la creation de l'Academie des Sciences par Colbert, trente ans apres le proces de Galile, et au moment des disparitions de Pascal, Descartes et Fermat. Elle dirigee par le hollandais Huyggens jusqu'a sa fuite de France au moment de la revocation de l'Edit de Nantes. - 1750 : l'Encyclopedie (ou "Dictionnaire raisonne des Sciences, des Arts et des Metiers") de Diderot et d'Alembert, soutenus par Malherbes, Buffon, Condorcet et Rousseau. - 1789 : Revolution francaise. - 8 aout 1793 : l'Assemblee, par une declaration de Marat, dissout l'Academie des Sciences. Celle-ci continue cependant ses travaux pour les poids et mesures jusqu'en 1795. - la Terreur : la condamnation a mort, pas au nom d'une "Revolution qui n'a pas besoin de savants" mais pour d'autres raisons, de trois grands hommes de science : Lavoisier, Bailly et Condorcet. - 1793-1794 : Au printemps 93, le Comite de Salut Publique s'inquiete du demi-million de soldats etrangers de toutes les pays frontaliers qui essai...

  14. Application of advanced oxidation process by electron beam irradiation in the organic compounds degradation present in industrial effluents

    International Nuclear Information System (INIS)

    Duarte, Celina Lopes

    1999-01-01

    The inefficacy of conventional methods to destroy toxic organic compounds present in industrial effluent has taken the search for new technologies of treatment. he water irradiation is the most efficient process to generate radicals that mineralise these compounds. A study to evaluate the Advanced Oxidation Process by electron beam irradiation to treat industrial effluent with high toxic organic compounds concentration was carried out. Experiments were conducted using a Radiation Dynamics Electron Beam Accelerator with 1,5 MeV energy and 37 power. The effluent samples from a big industrial complex were irradiated using the IPEN's Liquid Effluent Irradiation Pilot Plant and the effluent samples from five steps of a Governmental Wastewater Treatment Plant from SABESP - ETE Suzano (industrial Receiver Unit, Coarse Bar Screens, Medium Bar Screens, Primary Sedimentation and Final Effluent), were irradiated in a batch system. The electron beam irradiation showed be efficient on destroying the organic compounds delivered in these effluents mainly chloroform, dichloroethane, methyl isobutyl ketone, benzene, toluene, xylene, phenol and in the decoloring of dyes present in some samples. To remove 90% of the most organic compounds was necessary a 20 kGy dose for industry's ETE, 20 kGy for IRU, CBS and MBS and 10 kGy to 20 kGy for PS and FE. (author)

  15. 40 CFR 407.67 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS CANNED AND PRESERVED FRUITS AND VEGETABLES PROCESSING POINT SOURCE CATEGORY Canned and Preserved Fruits Subcategory § 407.67 Effluent limitations guidelines...

  16. 40 CFR 407.77 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS CANNED AND PRESERVED FRUITS AND VEGETABLES PROCESSING POINT SOURCE CATEGORY Canned and Preserved Vegetables Subcategory § 407.77 Effluent limitations guidelines...

  17. 40 CFR 415.342 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... SOURCE CATEGORY Chrome Pigments Production Subcategory § 415.342 Effluent limitations guidelines... available (BPT): Subpart AH—Chrome Pigments Pollutant or pollutant property BPT effluent limitations Maximum...

  18. 40 CFR 415.647 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... CATEGORY Cadmium Pigments and Salts Production Subcategory § 415.647 Effluent limitations guidelines... subject to this subpart and producing cadmium pigments must achieve the following effluent limitations...

  19. 40 CFR 415.643 - Effluent limitations guidelines representing the degree of effluent reduction attainable by the...

    Science.gov (United States)

    2010-07-01

    ... CATEGORY Cadmium Pigments and Salts Production Subcategory § 415.643 Effluent limitations guidelines... subject to this subpart and producing cadmium pigments must achieve the following effluent limitations...

  20. 40 CFR 440.23 - Effluent limitations representing the degree of effluent reduction attainable by the application...

    Science.gov (United States)

    2010-07-01

    ...) EFFLUENT GUIDELINES AND STANDARDS ORE MINING AND DRESSING POINT SOURCE CATEGORY Aluminum Ore Subcategory... discharged in mine drainage from mines producing bauxite ores shall not exceed: Effluent characteristic...