Filters
Results 1 - 10 of 13
Results 1 - 10 of 13.
Search took: 0.025 seconds
| Sort by: date | relevance |
No abstract available
Source
CEA, 75 - Paris (France); Societe Francaise de Radioprotection, 92 - Fontenay-aux-Roses; 481 p; ISBN 2-7272-0084-6; 
; 1983; p. 367-369; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983; Published in summary form only.
; 1983; p. 367-369; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983; Published in summary form only.
No abstract available
Source
CEA, 75 - Paris (France); Societe Francaise de Radioprotection, 92 - Fontenay-aux-Roses; 481 p; ISBN 2-7272-0084-6; ; 1983; p. 371-373; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983; Published in summary form only.
; 1983; p. 371-373; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983; Published in summary form only.
[en] The three main following topics were developed: human health studies; general aspects of plutonium monitoring; problems related to plutonium contaminated wastes
[fr]
Les trois principaux themes suivants ont ete developpes: les problemes sanitaires; les problemes generaux de detection de plutonium; les problemes poses par les dechets contenant du plutoniumSource
1983; 481 p; Commissariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983; ISBN 2-7272-0084-6;
[en] The results presented, have been obtained from the synthesis of the tests of prototypes made by the two manufacturers SAST (Saphymo-STel), MGP (Merlin Gerin Provence) and by the CEA (DEIN and SPR Saclay), during homologation tests. The main results are essentially presented in a tabular form
[fr]
Les resultats presentes resultent de la synthese des essais de recette des prototypes tete de serie effectues en usine chez les deux constructeurs SAST (SAPHYMO-STEL), MGP (MERLIN GERIN PROVENCE) et au CEA (DEIN et SPR/SACLAY), au cours des essais d'homologation. Les principaux resultats sont presentes sous forme de tableaux essentiellementSource
CEA, 75 - Paris (France); Societe Francaise de Radioprotection, 92 - Fontenay-aux-Roses; 481 p; ISBN 2-7272-0084-6; ; 1983; p. 345-365; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983
; 1983; p. 345-365; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983
[en] The B.F.S.A. plutonium monitor (monitor with sequential filter to measure plutonium and other transuranium element aerosols) includes two units: the CFSA sampler with sequential filter for alpha aerosols, and the processing unit in conjunction with its signalling unit. The main parameters of the CFSA and its principle being presented, the description of the sampler is given
[fr]
La balise plutonium B.F.S.A. (Balise a Filtre Sequentiel pour les Aerosols alpha) destinee a mesurer les aerosols de plutonium et d'autres transuraniens, est composee du capteur CFSA a filtre sequentiel pour aerosols alpha et de l'unite de traitement associee a son coffret de signalisation. Apres avoir donne les principaux parametres et le principe du CFSA, on en fait la descriptionSource
CEA, 75 - Paris (France); Societe Francaise de Radioprotection, 92 - Fontenay-aux-Roses; 481 p; ISBN 2-7272-0084-6; ; 1983; p. 273-286; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983
; 1983; p. 273-286; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983
[en] The B.F.S.A. plutonium monitor (Monitor with Sequential Filter to measure alpha Aerosols) aims at measuring aerosols of plutonium and other transuranium elements. The needs of reprocessing plants and laboratories in the course of plutonium recycling, have shown the necessity to carry out a TCR monitor (Radiation protection Control Board), that is to say pluggable to a centralized board. In view of this situation, the D.E.I.N. (Electronics and Nuclear Instrumentation Department of the CEA) proposed in June 1980, an action for the study and the industrialization of a French equipment of which the main objectives are given. The development of the action technical and financial means, is recalled and the results are given
[fr]
La balise plutonium B.F.S.A., Balise a Filtre Sequentiel pour les Aerosols alpha, est destinee a la mesure des aerosols de plutonium et autres transuraniens. Les besoins des usines de retraitement et des laboratoires au cours du recyclage du plutonium, ont montre la necessite de developper une balise TCR (Tableaux de Controle de la Radioprotection), c'est-a-dire connectable a un tableau centralise. Devant cette situation, le D.E.I.N. (Departement d'Electronique et d'Instrumentation Nucleaire du CEA) a propose en juin 1980, une action pour l'etude et l'industrialisation d'un materiel francais dont on donne les principaux objectifs dans cet article. On retrace le deroulement de l'action, cadre technique et financier, et on en donne les resultatsSource
CEA, 75 - Paris (France); Societe Francaise de Radioprotection, 92 - Fontenay-aux-Roses; 481 p; ISBN 2-7272-0084-6; ; 1983; p. 265-272; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983
; 1983; p. 265-272; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983
[en] For the different categories of wastes, the evolution of the cumulated production until the year 2000 is described by curves and the general situation of production points is presented, all that in France. The storage conditions are specified according to the type of wastes, category A, B, or C; the threshold under which the waste is classified in A category being fixed by the safety authorities at 2.104 CMA (maximum permissible concentration), that is to say for plutonium 1Ci/m3. The knowledge of waste activity is another basic element of the management of such wastes, the fixing of the threshold, above which wastes contaminated by plutonium have to be stored underground, still keeping to be specified
[fr]
Pour les differentes categories de dechets on decrit sous forme de courbes l'evolution de production cumulee jusqu'a l'an 2000 et on presente l'implantation generale des points de production, tout cela en France. On precise ensuite les conditions de stockage pour chaque categorie de dechets A, B et C; la fixation du seuil en deca duquel le dechet peut etre classe en categorie A ayant ete fixee par les autorites de surete a 2.104 CMA (concentration maximale admissible), c'est-a-dire pour le plutonium 1Ci/m3. La connaissance de l'activite des dechets est un autre element fondamental de la gestion de ce type de dechet, la fixation du seuil au-dela duquel un dechet contamine par du plutonium doit etre stocke en profondeur restant encore a determinerSource
CEA, 75 - Paris (France); Societe Francaise de Radioprotection, 92 - Fontenay-aux-Roses; 481 p; ISBN 2-7272-0084-6; ; 1983; p. 379-386; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983
; 1983; p. 379-386; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983
[en] The quantity of plutonium contained in controlled or accidental releases and in wastes processed or not is evaluated to compare it to the one dispersed during aerial nuclear explosions. The characteristics of plutonium fallouts from aerial nuclear explosions are reviewed: fallout zones, mass and activity of dispersed plutonium, behaviour of deposited plutonium of dose commitments. Among accidental situations, some are quoted with their consequences. About plutonium involved in industrial activities, the paper deals with the following points: evaluation of plutonium production in fuel cycle; brief chronology of the AEN solid waste disposal into the sea; liquid and gaseous effluents of reprocessing plants; wastes waiting for processing in the reprocessing plants of Windscale and La Hague
[fr]
On tente d'evaluer la quantite de plutonium contenu dans les rejets controles ou accidentels et dans les dechets conditionnes ou non, resultant des activites industrielles, afin de la comparer a celle dispersee lors d'essais nucleaires aeriens. On passe en revue les caracteristiques des retombees de plutonium provenant d'essais nucleaires aeriens: zones des retombees, masse et activite du plutonium disperse, comportement du plutonium depose, equivalents de dose engagee. Parmi les situations accidentelles, on en cite quelques unes en donnant brievement les consequences. Pour ce qui est du plutonium engage dans les activites industriels, on s'interesse aux points suivants: evaluation du plutonium produit dans le cycle du combustible; rapide historique des immersions de dechets solides de l'AEN; rejets liquides et gazeux d'usines de retraitement; dechets en attente de conditionnement pour les usines de retraitement de Windscale et La HagueSource
CEA, 75 - Paris (France); Societe Francaise de Radioprotection, 92 - Fontenay-aux-Roses; 481 p; ISBN 2-7272-0084-6; ; 1983; p. 449-470; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983; 32 refs.
; 1983; p. 449-470; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983; 32 refs.
[en] The present paper limits itself to the evaluation of quantities of plutonium in spent fuel reprocessing wastes and to their control. Plutonium is mainly represented by fives of its isotopes: Pu238, Pu239, Pu240, Pu241 and Pu242 of which some characteristics are recalled. The isotopic composition of plutonium varies according to the mass burning ratio and the initial enrichment in uranium 235. The PUREX reprocessing method is recalled, pointing out the different types of wastes produced along the treatment. Voluminal and mass quantities of plutonium are specified for the following wastes: hulls, high-level vitrified wastes, bituminized wastes of co-precipitation sludges. Some measuring methods of the quantities of plutonium in wastes are briefly quoted
[fr]
Le present article se limite a l'evaluation des quantites de plutonium presentes dans les dechets de retraitement des combustibles irradies et a leur controle. Le plutonium y est represente essentiellement par cinq de ses isotopes: Pu238, Pu239, Pu240, Pu241 et Pu242 dont on rappelle brievement les principales caracteristiques. La composition isotopique du plutonium varie avec le taux de combustion massique subi en reacteur et avec l'enrichissement initital en uranium 235 utilise. On rappelle le principe du procede de retraitement PUREX en notant les differentes sortes de dechets qui en decoulent. On precise les teneurs volumiques et massiques en plutonium dans les dechets ''coques'', dans les dechets vitrifies de haute activite, dans les dechets bitumes de boues de co-precipitation, ainsi que dans les dechets technologiques. On cite quelques methodes de mesure de la quantite de plutonium dans les dechetsSource
CEA, 75 - Paris (France); Societe Francaise de Radioprotection, 92 - Fontenay-aux-Roses; 481 p; ISBN 2-7272-0084-6; ; 1983; p. 433-445; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983; 9 refs.
; 1983; p. 433-445; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983; 9 refs.
[en] The most precise method to qualify an aerosol sampling system consists in measuring the deposition of particles on the filter or on the surfaces of which the system consists. It involves to be able to extract by washing the mass of particles deposited and to measure it. For this method, fluorescein salts (sodium or ammonium salts) are used; the concentration of the washing solution is measured with a photometer. According to the desired aerosol particles, an uranine generator for fine aerosols or a mono-dispersed aerosol generator is used. After the description of the design of the sampling head (intake, transfer and collection of aerosols on the filter), the tests realized to optimize the shape and the geometric dimensions are presented. The results obtained for 200 and 300 l.mn-1 flow rates are given. To reduce the flow rate variations, a measuring and regulating system has been studied and tested. Finally, the reasons for which the sampling head depression has not been kept in spite of the improvement it brought are given
[fr]
La methode la plus precise pour qualifier un systeme de prelevement d'aerosols consiste a mesurer le depot des particules sur le filtre de collection ou sur les parois composant le systeme. Cela implique de pouvoir extraire par lavage la masse de particules deposees et la mesurer. On utilise, pour cette methode, des sels de fluoresceine (sels de sodium ou d'ammonium); on mesure au photometre la concentration de la solution de lavage. Suivant la granulometrie des aerosols desires, on utilise soit le generateur d'uranine pour les aerosols fins, soit le generateur d'aerosols monodisperse concu par Berglund et Liu pour les gros aerosols. Apres avoir decrit la conception de la tete de prelevement (entree, transfert et collection des aerosols sur le filtre), on presente les essais realises afin d'en optimiser la forme et les dimensions geometriques. On donne ensuite les resultats obtenus pour des debits de 200 et 300 l.min-1. Afin de reduire les variations du debit, un systeme de mesure et de regulation a ete etudie et teste. On explique pourquoi la mise en depression de la tete de prelevement n'a pas ete retenue malgre l'amelioration qu'elle apportaitSource
CEA, 75 - Paris (France); Societe Francaise de Radioprotection, 92 - Fontenay-aux-Roses; 481 p; ISBN 2-7272-0084-6; ; 1983; p. 287-313; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983; 5 refs.
; 1983; p. 287-313; Commisariat a l'Energie Atomique; Saclay (France); Congress on plutonium and radioprotection; Saclay (France); 14-16 Jun 1983; 5 refs.
| 1 | 2 | Next |