Balance of groundwaterstreams below dumps with the application of environmental isotopes within hydrogeological examinations. Final report; Bilanzierung von Grundwasserstroemen unter Deponien mit Hilfe von umweltisotopen-hydrologischen Analysen im Rahmen hydrogeologischer Untersuchungen. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Geyh, M A; Ays, G

1995-08-15

Deponiesickerwaesser eine von der natuerlichen Isotopenzusammensetzung abweichende Markierung haben koennten, die vom Deponieinhalt und Isotopen-Fraktionierungen bei dessen Abbau gepraegt ist. Die Isotopenwerte des Grundwassers ober- oder unterstrom der Deponien wurden zu verschiedenen Jahreszeiten gemessen, um natuerliche und anthropogene Veraenderungen der Isotopenzusammensetzungen im Deponiebereich zu erfassen. Es wurde erwartet, dass die Mobilitaet der chemischen Kontaminanten durch physikalische, chemische und biologische Retardation gegenueber der der isotopisch markierten Wassermolekuele eingeschraenkt sei. Im Abstrom von Hausmuelldeponien koennen mit Hilfe der Sauerstoff- und Kohlenstoff-Isotopenzusammensetzung im Sickerwasser unterschiedlich stark von der Deponie beeinflusste Bereiche voneinander abgegrenzt werden. Die Kohlenstoff-Isotopenzusammensetzung kann zur Verfolgung der Phasen des chemischen Abbaus organischer Inhaltsstoffe eingesetzt werden. In Sonderabfalldeponien treten spezielle Isotopen-Effekte auf, die mit der andersartigen Zusammensetzung der Inhaltsstoffe zu erklaeren sind. (orig.)

Redoxspeziation von endlagerrelevanten Elementen mit Hilfe von Trennmethoden gekoppelt an ein Massenspektrometer mit induktiv gekoppeltem Plasma

OpenAIRE

Graser, Carl-Heinrich

2015-01-01

Im Rahmen dieser Arbeit wurden Redoxspeziationsanalysen von Eisen, Neptunium und Plutonium per CE-SF-ICP-MS durchgeführt. Durch Optimierung der Trennparameter konnten Trennungen der Pu Oxidationsstufen III bis VI und Trennungen der Np Oxidationsstufen IV bis VI binnen 15 Minuten mit einer Nachweisgrenze von 10-12 M durchgeführt werden. Die Trennung der Fe Oxidationsstufen II und III gelang in weniger als 5 Minuten mit einer Nachweisgrenze von 5-10-8 M.

Das polyzystische Ovarialsyndrom: Im Spannungsfeld von Hormonen und Stoffwechsel

Directory of Open Access Journals (Sweden)

Wehr E

2010-01-01

Full Text Available Das polyzystische Ovarialsyndrom (PCOS ist eine komplexe Erkrankung und betrifft mindestens 5–10 % aller Frauen. Es ist charakterisiert durch Hyperandrogenismus (klinisch und/oder biochemisch, Oligo- oder Anovulation und polyzystische Ovarien. In der Pathogenese spielt neben der Hyperandrogenämie und der abnormen Gonadotropinsekretion die Insulinresistenz eine zentrale Rolle. Ein genetischer Hintergrund des PCOS wird vermutet, neben verschiedenen Kandidatengenen werden auch genomweite Assoziationsstudien neue Kenntnisse bringen, um in Zukunft sowohl Diagnose als auch Therapie des PCOS zu vereinfachen. Das PCOS bringt ein hohes metabolisches Risiko mit sich, ca. die Hälfte aller betroffenen Frauen ist adipös, viele leiden an Insulinresistenz, Glukosetoleranzstörungen und Diabetes mellitus Typ 2. Weiters sind viele Frauen mit PCOS von unerfülltem Kinderwunsch, Hirsutismus, Akne und androgenetischer Alopezie betroffen. Vor allem Adipositas und Hirsutismus führen zu einer starken psychischen Belastung betroffener Frauen, das Suizidrisiko ist deutlich erhöht. Zur exakten Diagnose des PCOS bedarf es einer genauen Anamnese und körperlichen Untersuchung mit anthropometrischen Messungen und Hirsutismus-Score. Ein Hormonstatus mit Bestimmung von Androgenen ist unerlässlich, ein LHRH-Test kann weitere diagnostische Hinweise liefern. Weiters sollten zur metabolischen Abklärung ein oraler Glukosetoleranztest, eine Messung der Körperfettverteilung und die Bestimmung eines Lipidstatus erfolgen. Therapeutisch ist vor allem bei adipösen Frauen eine Lebensstilintervention am wichtigsten, zusätzlich kommen Insulinsensitizer und orale Kontrazeptiva zum Einsatz. Zusammenfassend ist das PCOS eine extrem häufige Erkrankung mit komplexen Folgen und bedarf einer konsequenten, interdisziplinären individuellen Therapie bei betroffenen Frauen.

Methods of measuring floor resistance; Messverfahren zur Bestimmung des Ableitwiderstandes von Fussboeden

Energy Technology Data Exchange (ETDEWEB)

Seemann, A. [BGFW Berufsgenossenschaft der Gas-, Fernwaerme- und Wasserwirtschaft, Duesseldorf (Germany); Tutschek, G.; Warszewski, P. [Ruhrgas AG, Essen (Germany). Abt. Anlagensicherheit

2001-04-01

In gas fitting plants where explosive gas/air mixtures can occur the flooring materials must be conductive. Persons who are insulated from earth can easily acquire and retain an electrostatic charge. If an electrostatically charged person touches a conducting object (e.g. pipe, gas fitting plant) a spark occur at the point of contact. Such sparks can cause ignition of an explosive gas/air mixture. To avoid the retention of static electricity the recommended level of the earth of a floor must be lower than 10{sup 8} {omega} and the persons have to wear dissipative footwear. In several standards methods for checking floor resistance are described. A useful test method is given in DIN EN 1081. (orig.) [German] Explosionsfaehige Erdgas-/Luftgemische koennen durch elektrostatische Entladungsfunken gezuendet werden. Um eine elektrostatische Aufladung von Personen zu vermeiden, darf der Ableitwiderstand des Fussbodens den Wert von 10{sup 8} {omega} nicht ueberschreiten, und es muss ableitfaehiges Schuhwerk getragen werden. In verschiedenen Normen sind Messerfahren fuer die Ueberpruefung des Ableitwiderstandes von verlegten Fussboeden angegeben. Eine fuer die Praxis brauchbare Messmethode wird in DIN EN 1081 angegeben. (orig.)

Interpretation of ozone vertical profiles and their variations in the Northern hemisphere on the basis of GOME satellite data. Final report; Interpretation von Ozon-Vertikalprofilen und deren Variationen in der noerdlichen Hemisphaere unter Benutzung von GOME Satellitendaten. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Eichmann, K.U.; Bramstedt, K.; Weber, M.; Rozanov, V.; Debeek, R.; Hoogen, R.; Burrows, J.P.

2000-07-04

Semiglobal ozone vertical profiles based on GOME measurements were established and evaluated systematically. GOME (Global Ozone Monitoring Experiment), carried by the ERS-2 satellite, is the first European passive optical sensor for long-term monitoring of ozone, other trace elements, and aerosols. Especially the vertical distribution of ozone in the Arctic region was measured and interpreted with a view to enhanced ozone degradation in the Arctic winter and spring seasons. Apart from the regional variations, also the time variations of the profiles are to provide further information on the dynamics and chemical processes in the polar vortex. The retrieval algorithm used for assessing the ozone vertical profiles, FURM (FUll Retrieval Method), is based on the GOMETRAN radiation transport model developed at Bremen university especially for evaluation of the GOME data. The GOME ozone profiles were validated with ozone probes and other satellite experiments. [German] Ziel des Projektes war eine systematische Bestimmung und Auswertung von semiglobalen Ozonvertikalprofilen aus den Messdaten von GOME. Das auf dem Satelliten ERS-2 fliegende Spektrometer GOME (Global Ozone Monitoring Experiment) ist der erste europaeische, passive, optische Sensor, der fuer Langzeitmessungen von Ozon, anderen Spurenstoffen und Aerosolen konzipiert wurde. Im Projekt wurde insbesondere die vertikale Verteilung von Ozon in der Arktis bestimmt und interpretiert hinsichtlich des verstaerkten Ozonabbaus im arktischen Winter und Fruehjahr. Neben der raeumlichen Variation sollen auch die zeitlichen Ablaeufe und Veraenderungen der Profile weitere Erkenntnise hinsichtlich der Dynamik und der chemischen Prozesse im Polarwirbel liefern. Der Retrievalalgorithmus zur Bestimmung des Ozonhoehenprofils, FURM (Full Retrieval Method) genannt, basiert auf dem Strahlungstransportmodell GOMETRAN, das an der Universitaet Bremen speziell fuer die Auswertung der Daten des GOME Instrumentes entwickelt wurde

Microbial rehabilitation of soils in the vicinity of former coking plants; Mikrobielle Sanierung von Kokereiboeden

Energy Technology Data Exchange (ETDEWEB)

Knackmuss, H J [Fraunhofer-Institut fuer Grenzflaechen- und Bioverfahrenstechnik, Stuttgart (Germany); Bryniok, D [Fraunhofer-Institut fuer Grenzflaechen- und Bioverfahrenstechnik, Stuttgart (Germany)

1997-12-31

Two airlift reactors with a nominal volume of 15 liters were provided with a closed aeration circuit. This mode of operation for the first time permitted to determine the carbon balance of PAH degradation. A mineralisation rate of approx. 35% was found by this method, whereas in experiments performed in shaking bottles mineralisation was always over 60% in the case of PAH mixtures. Use of PAH mixtures leads to competitive effects. These effects were studied by means of bacterial pure cultures. Further fundamental studies were performed to find suitable solvents for PAH degradation in a culture system with two liquid phases and examine liquid-liquid extraction of PAH from soil washing water. (orig./SR) [Deutsch] Zwei Airliftreaktoren mit einem Nennvolumen von 15 Litern wurden mit einem geschlossenen Belueftungskreislauf versehen. Diese Betriebsweise erlaubte erstmals die Bestimmung einer Kohlenstoffbilanz des PAK-Abbaus. Diese ergab eine Mineralisation von ca. 35%, waehrend die Mineralisationsrate bei Versuchen im Schuettelkolben selbst im Falle von PAK-Gemischen immer ueber 60% lag. Bei der Verwertung von PAK-Gemischen treten Kompetitionseffekte auf. Diese wurden mit bakteriellen Reinkulturen untersucht. Weitere grundlegende Arbeiten betrafen die Auswahl geeigneter Loesungsmittel fuer den PAK-Abbau in einem Kultursystem mit zwei Fluessigphasen und die Fluessig/Fluessig-Extraktion von PAK aus Bodenwaschwasser. (orig./SR)

Microbial rehabilitation of soils in the vicinity of former coking plants; Mikrobielle Sanierung von Kokereiboeden

Energy Technology Data Exchange (ETDEWEB)

Knackmuss, H.J. [Fraunhofer-Institut fuer Grenzflaechen- und Bioverfahrenstechnik, Stuttgart (Germany); Bryniok, D. [Fraunhofer-Institut fuer Grenzflaechen- und Bioverfahrenstechnik, Stuttgart (Germany)

1996-12-31

Two airlift reactors with a nominal volume of 15 liters were provided with a closed aeration circuit. This mode of operation for the first time permitted to determine the carbon balance of PAH degradation. A mineralisation rate of approx. 35% was found by this method, whereas in experiments performed in shaking bottles mineralisation was always over 60% in the case of PAH mixtures. Use of PAH mixtures leads to competitive effects. These effects were studied by means of bacterial pure cultures. Further fundamental studies were performed to find suitable solvents for PAH degradation in a culture system with two liquid phases and examine liquid-liquid extraction of PAH from soil washing water. (orig./SR) [Deutsch] Zwei Airliftreaktoren mit einem Nennvolumen von 15 Litern wurden mit einem geschlossenen Belueftungskreislauf versehen. Diese Betriebsweise erlaubte erstmals die Bestimmung einer Kohlenstoffbilanz des PAK-Abbaus. Diese ergab eine Mineralisation von ca. 35%, waehrend die Mineralisationsrate bei Versuchen im Schuettelkolben selbst im Falle von PAK-Gemischen immer ueber 60% lag. Bei der Verwertung von PAK-Gemischen treten Kompetitionseffekte auf. Diese wurden mit bakteriellen Reinkulturen untersucht. Weitere grundlegende Arbeiten betrafen die Auswahl geeigneter Loesungsmittel fuer den PAK-Abbau in einem Kultursystem mit zwei Fluessigphasen und die Fluessig/Fluessig-Extraktion von PAK aus Bodenwaschwasser. (orig./SR)

Fragen - Nachfragen - Echofragen. Formen und Funktionen von Interrogationen im gesprochenen Deutsch

Directory of Open Access Journals (Sweden)

Rost-Roth, Martina

2003-01-01

Full Text Available Präsentiert werden Befunde aus einer empirischen Untersuchung zu Nachfragen und anderen Fragen in mündlichen Kommunikationen. Ausgangspunkt ist die Beobachtung, daß Beschreibungen von Nachfragen nur in geringer Zahl vorliegen, aus sehr unterschiedlichen Bereichen stammen (Konversationsanalyse, grammatische Beschreibungen von Fragen und Literatur zu Echofragen und sich Beschreibungen von Nachfrageformen sowie Nachfragefunktionen und die jeweils unterstellten Form-Funktions-Bezüge - auch in den einzelnen Bereichen - vielfach widersprechen. Vor diesem Hintergrund ist zentales Anliegen der Untersuchung, einen übergeordneten Analyserahmen für die Befassung mit Frageformen und Fragefunktionen zu entwickeln, der die Beschreibung von Nachfragen in einer allgemeineren Beschreibung von Interrogationen verortet. Das Besondere von Nachfragen wird darin gesehen, daß es sich um Interrogationen handelt, die auf andere sprachliche Äußerungen Bezug nehmen. Hier sind wiederum verschiedene Mittel zu unterscheiden, die für die Unterscheidung von Echofragen und anderen Nachfragen bestimmend sind. In diesem Zusammenhang wird gezeigt, daß auch der Art der Bezugnahme besondere Bedeutung für die Bestimmung von Nachfrageformen und Nachfragefunktionen zukommt. Anhand der Analysen von empirischen Fragevorkommen im gesprochenen Deutsch werden zunächst verschiedene 'Strukturtypen' differenziert. Die Vergleiche von Nachfragen und anderen Fragen zeigen vor allem Unterschiede in Hinblick auf die Frequenz verbloser und elliptischer Frageformulierungen. Daran anschließend werden Nachfragefunktionen im Bereich der Verständnissicherung sowie andere Nachfragefunktionen erörtert. Bei der Suche nach einem gemeinsamen Nenner für sehr unterschiedliche Nachfragefunktionen erweisen sich als zentrale Funktionsparameter :1. die Fokussierungsleistung (über die Bezugnahme auf vorausgehende Äußerungen der Gesprächspartner sowie 2. der Interrogativmodus (über die

Suitability of tracers; Eignung von Tracern

Energy Technology Data Exchange (ETDEWEB)

Klotz, D. [GSF - Forschungszentrum fuer Umwelt und Gesundheit GmbH, Neuherberg (Germany). Inst. fuer Hydrologie

1999-02-01

Hydrological tracer techniques are a means of making statements on the direction and speed of underground water. One of the simpler tasks is to find out whether there is hydrological communication between two given points. This requires a determination of the direction of flow, which places less exacting demands on the properties of the tracer than does the task of determining the flow velocity of underground water. Tracer methods can serve to infer from flow velocity the distance (flow) velocity, which is defined as the ratio between the distance between two points located in flow direction and the actual time it takes water to flow from one to the other. [Deutsch] Mit Hilfe der hydrologischen Markierungstechniken koennen Aussagen ueber die Richtung und die Geschwindigkeit von Bewegungen des unterirdischen Wassers gemacht werden. Der einfachere Fall liegt vor, wenn festgestellt werden soll, ob zwischen zwei Punkten eine hydrologische Verbindung besteht. Bei dieser Fliessrichtungsbestimmung sind die Forderungen an die Eigenschaften der einzusetzenden Tracer geringer als bei der Bestimmung der Geschwindigkeit des unterirdischen Wassers. Von den Geschwindigkeiten des unterirdischen Wassers ist die Abstands-(Fliess)geschwindigkeit, die definiert ist durch das Verhaeltnis aus dem Abstand und der wahren Fliesszeit zwischen zwei in Bewegungsrichtung gelegenen Punkten, durch Tracermethoden zu bestimmen. (orig.)

Automatized determination of U, Am and Pu; Automatisierte Bestimmung von U, Am und Pu

Energy Technology Data Exchange (ETDEWEB)

Schumacher, C. [Forschungszentrum Juelich (Germany). Geschaeftsbereich S; FH Aachen, Campus Juelich (Germany); Zoriy, M. [Forschungszentrum Juelich (Germany). Geschaeftsbereich S; Scherer, U.W. [FH Aachen, Campus Juelich (Germany)

2015-07-01

This work describes the implementation of automatized separation methods for the determination of uranium, and simultaneous determination of americium and plutonium, respectively, in water samples by alpha ray spectrometry. Either method should be a procedure suitable for low-level determinations in routine analysis. Starting from proven methods for determination of actinides in urine samples by using TRISKEM DGA resins ''normal'' (n) or ''branched'' (b) it was investigated whether they could be applied to water samples when using the self-constructed automated column system Multi TSM. Selected separation methods were applied to deionized water and tap water samples. Suitability of the methods even in the presence of larger amounts of solutes was tested by investigating water samples taken from several ponds. Finally, the method was qualified by determination of a water sample from an interlaboratory comparison to analyze americium and plutonium. Radiochemical yields were determined by addition of respective tracer radionuclides before sample preparation.

Zur medienpädagogischen Ausbildung von Lehrerinnen und Lehrern. Folgerungen aus der aktuellen lern- und professionstheoretischen Diskussion

Directory of Open Access Journals (Sweden)

Sigrid Blömeke

2001-08-01

Full Text Available Vor dem Hintergrund neuerer Ansätze in der Lerntheorie und in der Professionstheorie werden Folgerungen für die inhaltliche und die didaktisch- methodische Gestaltung der medienpädagogischen Lehrerausbildung gezogen. Dafür wird in einem ersten Schritt die Frage des Verhältnisses von Wissen und Handeln geklärt und der Wissenserwerb wird als aktiv-konstruierender Prozess beschrieben. Die in diesem Zusammenhang herausgearbeiteten grundsätzlichen Gestaltungsprinzipien werden dann in einem zweiten Schritt auf der Basis einer an den Aufgaben von Lehrerinnen und Lehrern orientierten näheren Bestimmung medienpädagogischer Kompetenz für den Erwerb dieser konkretisiert. In inhaltlich-systematischer Hinsicht steht die kognitive Strukturbildung im Vordergrund, in didaktisch-methodischer Hinsicht wird ein besonderer Akzent auf Fallarbeit gelegt, deren Möglichkeiten auch an-hand eines Beispiels verdeutlicht werden.

Separation of plutonium oxide nanoparticles and colloids

Energy Technology Data Exchange (ETDEWEB)

Wilson, Richard E.; Skanthakumar, S.; Soderholm, L. [Argonne National Laboratory, IL (United States). Chemical Sciences and Engineering Division

2011-11-18

Colloidal plutonium is an important component of Pu aqueous speciation. Pu colloids are problematic in nuclear separations and are a potential transport vector in the environment. Using a mixture of n-octanol and trichloroacetic acid a selective and reversible separation of these particles can be achieved by exploiting their surface reactivity. [German] Kolloidales Plutonium ist ein wichtiger Bestandteil in waessrigen Pu-Bereitungen. Pu-Kolloide sind problematisch bei der Wiederaufbereitung von Kernmaterial und bilden einen potenziellen Transportvektor in die Umwelt. Mit einem Loesungsmittelgemisch aus n-Octanol und Trichloressigsaeure gelingt die selektive und reversible Trennung dieser Partikel durch Ausnutzung ihrer Oberflaechenreaktivitaet.

Studies for reconstruction efficiency and background measurements of {tau} lepton identification in Z {yields} {tau}{tau} decays in data of the ATLAS experiment; Studien zur Messung von Rekonstruktionseffizienz und Untergrund der {tau}-Lepton-Identifikation im Zerfall Z {yields} {tau}{tau} beim ATLAS-Experiment aus Daten

Energy Technology Data Exchange (ETDEWEB)

Johnert, Sebastian

2008-11-15

In this diploma thesis two methods are presented, by which {tau} leptons shall be studied in the future data of the ATLAS experiment. The first part is formed by the determination of misidentification rates of jets from QCD 2-jet events as {tau} particles. The second part is the development of a method for the determination of the {tau} reconstruction and identification efficiency relatively to the {mu} efficiency. In this connection invariant masses from Z{yields}ll events are determined, the masses from Z{yields}{tau}{tau} events compared with those from Z{yields}ee and Z{yields}{mu}{mu}, {tau} efficiencies averaged over all ranges and in different {eta} ranges calculated as well as a mehtod for the determination of {tau} efficiencies in different transverse-momentum ranges presented. Furthermore an improved estimation of the QCD background is performed and the behaviour of the {tau} efficiency under regardment of the trigger studied. [German] In dieser Diplomarbeit werden zwei Methoden vorgestellt, mit denen {tau}-Leptonen in den zukuenftigen Daten des ATLAS-Experiments untersucht werden sollen. Den ersten Teil bildet die Bestimmung von Missidentifikationsraten von Jets aus QCD-2-Jet-Ereignissen als {tau}-Leptonen. Der zweite Teil ist die Entwicklung einer Methode zur Bestimmung der {tau}-Rekonstruktions und -Identifikationseffizienz relativ zur {mu}-Effizienz. In diesem Zusammenhang werden invariante Massen aus Z {yields} ll-Ereignissen bestimmt, die Massen aus Z {yields} {tau}{tau}-Ereignissen mit denen aus Z {yields} ee und Z {yields} {mu}{mu} verglichen, {tau}-Effizienzen gemittelt ueber alle Bereiche und in verschiedenen {eta}-Bereichen berechnet sowie eine Moeglichkeit zur Bestimmung von {tau}-Effizienzen in unterschiedlichen Transversalimpulsbereichen vorgestellt. Des Weiteren wird eine verbesserte Abschaetzung des QCD-Untergrunds vorgenommen und das Verhalten der {tau}-Effizienz unter Beruecksichtigung des Triggers untersucht. (orig.)

Japan's spent fuel and plutonium management challenge

International Nuclear Information System (INIS)

Katsuta, Tadahiro; Suzuki, Tatsujiro

2011-01-01

Japan's commitment to plutonium recycling has been explicitly stated in its long-term program since 1956. Despite the clear cost disadvantage compared with direct disposal or storage of spent fuel, the Rokkasho reprocessing plant started active testing in 2006. Japan's cumulative consumption of plutonium has been only 5 tons to date and its future consumption rate is still uncertain. But once the Rokkasho reprocessing plant starts its full operation, Japan will separate about 8 tons of plutonium annually. Our analysis shows that, with optimum use of available at-reactor and away-from-reactor storage capacity, there would be no need for reprocessing until the mid-2020s. With an additional 30,000 tons of away-from-reactor (AFR) spent-fuel storage capacity reprocessing could be avoided until 2050. Deferring operation of the Rokkasho plant, at least until the plutonium stockpile had been worked down to the minimum required level, would also minimize international concern about Japan's plutonium stockpile. The authors are happy to acknowledge Frank von Hippel, Harold Feiveson, Jungming Kang, Zia Mian, M.V. Ramana, and other IPFM members, as well as the generous grant from the MacArthur Foundation for helping make this research possible.

Experiences with the use of conservative tracers as an aid in transferring lysimeter results to the open field; Erfahrungen beim Einsatz von konservativen Tracern als Hilfsmittel zur Uebertragung von Lysimeterergebnissen auf Freilandflaechen

Energy Technology Data Exchange (ETDEWEB)

Seeger, J.; Meissner, R.; Rupp, H. [UFZ - Umweltforschungszentrum Leipzig-Halle GmbH, Falkenberg (Germany). Lysimeterstation; Mueller, L.; Eulenstein, F. [Zentrum fuer Agrarlandschafts- und Landnutzungsforschung e.V. (ZALF), Muencheberg (Germany)

1999-02-01

Four lysimeter trials performed on an IS-type soil yielded an almost constant range of displacement of a tracer front (NO{sub 3} front) of 4.0 to 4.5 mm / l of seepage water (referred to a surface area of 1 m-2 and a depth of 1 m). This was experimental confirmation of a tentatively formulated simplified relationship between seepage water volume, vertical tracer displacement, and field capacity. The results were also in very good agreement with those of a control study in the open field carried out under similar hydrological, pedological, and agrotechnical conditions using lysimeters and Cl tracers for determining quantities of seepage water formation. As the present lysimeter trials mirror soil hydrological processes in the open field with sufficient accuracy, they appear well suited to take the place of the so often lacking territorial data as a means of validating mathematical models describing seepage-water-bound material export. [Deutsch] Auf der Basis von 4 Lysimeterversuchen konnte fuer die Bodenart IS ein nahezu konstanter Wertebereich fuer die Verlagerung einer Tracerfront (NO{sub 3}-Front) in Hoehe von 4,0 bis 4,5 mm/l Sickerwasser (bezogen auf eine Oberflaeche von 1 m{sup 2} und eine Tiefe von 1 m) ermittelt werden. Damit konnte die vereinfachte Beziehung zwischen Sickerwassermenge, Tracerverlagerungstiefe und Feldkapazitaet experimentell bestaetigt werden. Ein Vergleich zur Bestimmung der Sickerwassermengenbildung mit Hilfe von Lysimetern und durch Einsatz von Cl-Tracern unter aehnlich hydrologischen, pedologischen und agrotechnischen Bedingungen im Freiland wies eine hohe Uebereinstimmung auf. Da die hier durchgefuehrten Lysimeteruntersuchungen bodenhydrologische Prozesse von Freilandflaechen mit ausreichender Genauigkeit widerspieglen, erscheinen sie anstelle oft fehlender Gebietskenndaten zur Validierung von mathematischen Modellen zur Beschreibung sickerwassergebundener Stoffaustraege gut geeignet. (orig.)

Bestimmung der optimalen Array-Apertur für die Ultraschallprüfung von faserverstärkten Kunststoffen

OpenAIRE

Kurras, Martin

2017-01-01

Für die zerstörungsfreie Prüfung von Kohlenstofffaserverbundwerkstoffen (CFK) wird häufig die Ultraschallprüfung verwendet. Neben dem klassischen Ultraschallverfahren findet dabei auch die Phased Array Technologie Anwendung. Hierbei wird zwischen zwei Verfahren unterschieden: dem handelsüblichen Phased Array oder Conventional Phased Array (CPA) und dem tomographischen Sampling Phased Array (SPA). Der Einsatz von Phased Arrays im Zusammenhang mit Linear-Scan-Technik und das sich daraus ergeben...

Airborne remote sensing of water constituents at Lake Constance; Flugzeuggestuetzte Fernerkundung von Wasserinhaltsstoffen im Bodensee

Energy Technology Data Exchange (ETDEWEB)

Heege, T.

2000-12-01

An inversion scheme for the retrieval of water constituents in case II waters from airborne multispectral scanner data is presented. This method includes modules for the calculation of aerosol types and contents, for the correction of sun glitter radiances and for the atmospheric correction of the image data. In 1996 extensive measurements were performed to determine the optical properties in Lake Constance. In combination with data collected through many years within a project of the German Research Foundation (SFB 248), for the first time a data set of inherent optical parameters being specific for typical substances in the Lake could be established. By means of the inversions scheme and the specific optical properties, geo-coded maps of suspended matter and chlorophyll were calculated from the multispectral airborne measurements above Lake Constance. (orig.) [German] Zur Berechnung von Wasserinhaltsstoffen aus Daten flugzeuggetragener Multispektralscanner wird ein Inversionsverfahren vorgestellt. Es beinhaltet die Bestimmung von Aerosoltypen und -konzentrationen, die bildpunktweise Korrektur von Oberflaechenreflexionen des Sonnenlichtes und die Atmosphaerenkorrektur von Fernerkundungsdaten. Zur Erfassung der optischen Groessen im Wasser wurden umfangreiche Messkampagnen am Bodensee durchgefuehrt. Zusammen mit vieljaehrigen Datensaetzen des DFG-Sonderforschungsbereichs 248 wird damit erstmalig ein vollstaendiger Satz der inhaerenten optischen stoffspezifischen Groessen fuer den Bodensee bestimmt. Zur Validation werden diese anhand von verschiedenen Modellen zur Verknuepfung der inhaerenten Streu- und Absorptionskoeffizienten mit den messbaren Groessen Extinktion und diffuse Reflexion auf Konsistenz geprueft. Aus Befliegungen mit dem Multispektralscanner Daedalus werden mit den vorgestellten Verfahren und optischen Groessen georeferenzierte Verteilungskarten von Schwebstoff und Phytoplankton-Pigmenten berechnet. (orig.)

1,2-Oxathiolane - A Photoelectron Spectroscopic Study

DEFF Research Database (Denmark)

Jørgensen, F. S.; Carlsen, Lars

1983-01-01

Der cyclische Sulfensureester 1,2-Oxathiolan (1) wurde durch milde Thermolyse von 3-(Phthalimidothio)-1-propanol (2) gewonnen und durch Photoelektronen-Spektroskopie identifiziert.- Die Möglichkeiten zur photoelektronenspektroskopischen Bestimmung der Konformation von Sulfensureestern werden...

Measurement of thyrotropin receptor antibodies (TRAK) with a second generation assay in patients with Graves' disease; Die Bestimmung von Thyreotropin-Rezeptor-Antikoerpern (TRAK) mit einem Assay der zweiten Generation bei Patienten mit Morbus Basedow

Energy Technology Data Exchange (ETDEWEB)

Zoephel, K.; Wunderlich, G.; Franke, W.G. [Klinik und Poliklinik fuer Nuklearmedizin, Technische Univ. Dresden (Germany); Koch, R. [Inst. fuer Medizinische Informatik und Biometrie, Technische Univ. Dresden (Germany)

2000-06-01

, porcinen Radiorezeptorassays (RRA), rekombinante, humane TSH-Rezeptoren verwendet werden ('coated tube'-Prinzip, CT RRA). Methoden: Insgesamt wurden 207 Patienten mit verschiedenen Schilddruesenerkrankungen sowie 205 schilddruesengesunde Personen als Kontrollkollektiv sowohl in einem etablierten RRA (Fa. Medipan Diagnostica GmbH, Selchow) als auch im neuen CT RRA (Fa. B.R.A.H.M.S. Diagnostica GmbH, Berlin) untersucht. 60 Patienten mit Morbus Basedow befanden sich nach erfolgter Thyreostase mit einem Hyperthyreoserezidiv vor einer Radiojodtherapie, 109 Patienten wiesen eine disseminierte Autonomie (DA) auf und bei den restlichen 38 bestand eine Hashimoto-Thyeroiditis. Mittels ROC-Analyse wurden Normbereiche fuer beide Assays festgelegt und auf ihre diagnostische Brauchbarkeit geprueft. Ergebnis: Waehrend der aeltere RRA 42/60 Basedown-Patienten positiv fand, detektierte der CT RRA 52/60 TRAK-positiv. Die Sensitivitaet stieg somit von 70% auf 86,7% (Spezifitaet: 99,5% bei beiden Assays). Im Hashimoto- und im Kontrollkollektiv fanden der neue CT RRA jeweils eine falsch positive Probe, der aeltere hingegen 3, respektive 2 Proben falsch positiv. Schlussfolgerung: der neue DYNOtest {sup trademark} TRAK human ist fuer Morbus-Basedow-Patienten mit rezidivierender Hyperthyreose deutlich sensitiver - bei gleichhoher Spezifitaet. Die Bestimmung der funktionellen Assaysensitivitaet und der Interassay-Variation fiel im CT RRA praeziser aus als im etablierten RRA. Auch die Handhabung des CT RRA is einfacher. (orig.)

Interactions between industrial organic pollutants and rhizosphere components and documentation of material streams in plant-based wastewater treatment plants - laboratory experiments; Wechselwirkungen industrieller organischer Schadstoffe mit Rhizosphaerenkomponenten und Bilanzierung von Stoffstroemen in Pflanzenklaeranlagen - Laborversuche

Energy Technology Data Exchange (ETDEWEB)

Plugge, J.

2001-07-01

The purpose of the present study was to examine the suitability of plant/soil systems for cleaning organically polluted effluents and to assess the influence of plant growth and dissolved humic substances on processes leading to the elimination of organic pollutants. This involved an examination of sorption interactions between selected pollutants on the one hand and sand and root material on the other, use of vertically irrigated plant-bearing sand columns for simulating real plant-based wastewater treatment plants, assessment of the cleaning efficiency of these systems with respect to the employed model pollutants and determination of the contamination of the filter material and plants with pollutants. Radiotracer techniques were used to determine pollution paths of phenanthrene and its microbial degradation in the model system. [German] In der vorliegenden Arbeit wurde die Eignung von Pflanze/Boden-Systemen zur Reinigung carbochemisch belasteter Abwaesser untersucht und der Einfluss eines Pflanzenbewuchses sowie geloester Huminstoffe auf die Prozesse, die zur Entfernung organischer Schadstoffe fuehren, bewertet. Die Bearbeitung dieses Themas umfasste Untersuchungen zu Sorptionswechselwirkungen ausgewaehlter Schadstoffe mit Sand- und Wurzelmaterial, die Anwendung vertikal durchstroemter, bepflanzter Sandsaeulen zur Nachbildung realer Pflanzenklaeranlagen, die Erfassung der Reinigungseffizienz dieser Systeme fuer die Modellschadstoffe sowie die Bestimmung der Schadstoffkontamination des Filtermaterials und der Pflanzen. Unter Anwendung der Radiotracertechnik erfolgte darueber hinaus die Bestimmung der Schadstoffpfade von Phenanthren einschliesslich des mikrobiellen Abbaus im Modellsystem. (orig.)

Environmental monitoring of mercury in waters. Reagent-free and rapid determination of mercury at trace levels.; Umweltmonitoring von Quecksilber in Gewaessern. Reagenzienfreie und schnelle Bestimmung von Hg im Spurenbereich

Energy Technology Data Exchange (ETDEWEB)

Huber, Jessica; Leopold, Kerstin [Ulm Univ. (Germany). Inst. fuer Analytische und Bioanalytische Chemie

2013-05-15

With the help of nano gold collectors for the enrichment of the total mercury content of water samples can be analyzed fully automatically using atomic fluorescence spectrometry without extensive sample preparation. [German] Mit Hilfe von Nanogoldkollektoren zur Anreicherung kann der Gesamtquecksilber-Gehalt von Gewaesserproben vollautomatisiert mittels Atomfluoreszenzspektrometrie ohne aufwendige Probenvorbereitung analysiert werden.

Statistical methods for the analysis of left-censored variables [Statistische Analysemethoden für linkszensierte Variablen und Beobachtungen mit Werten unterhalb einer Bestimmungs- oder Nachweisgrenze

Directory of Open Access Journals (Sweden)

Pesch, Beate

2013-03-01

Full Text Available [english] In some applications statisticians are confronted with values which are reported to be below a limit of detection or quantitation. These left-censored variables are a challenge in the statistical analysis. In a simulation study, we compare different methods to deal with this type of data in statistical applications. These include measures of location, dispersion, association, and statistical modeling. Our simulation study showed that the multiple imputation approach and the Tobit regression lead to unbiased estimates, whereas the naïve methods including simple substitution of non-detects lead to unreliable estimates. We illustrate the application of the multiple imputation approach and the Tobit regression with an example from occupational epidemiology. [german] In der statistischen Praxis treten immer wieder Variablen mit Werten unterhalb einer Bestimmungs- oder Nachweisgrenze auf. Diese sind linkszensiert und stellen daher eine Herausforderung für die statistische Analyse dar. Im Rahmen einer Simulationsstudie vergleichen wir Schätzmethoden zur Berechnung von Lage- und Streuungmaßen, Korrelationen und Regressionsparametern bei diesen Variablen. Unsere Ergebnisse zeigen, dass die multiple Imputationsmethode und die Tobit Regression zu unverzerrten Schätzungen führen. Naive Methoden, einschließlich der einfachen Substitution von zensierten Beobachtungen, ergeben hingegen unzuverlässige Schätzungen. Wir illustrieren die Anwendung der multiplen Imputationsmethode und der Tobit Regression anhand eines Beispiels aus der Epidemiologie der Arbeitswelt.

Characterization of adrenal masses: can image replace biopsy?; Charakterisierung von Nebennierenraumforderungen. Kann die Bildgebung die Biopsie ersetzen?

Energy Technology Data Exchange (ETDEWEB)

Heinz-Peer, G.; Hoenigschnabel, S.; Lechner, G. [Universtaetsklinik fuer Radiodiagnostik, Abt. Chirurgische Faecher, Wien (Austria)]|[Ludwig Boltzmann-Inst. fuer Radiologische Tumorforschung, Wien (Austria); Niederle, B. [Universitaetsklinik fuer Chirurgie, Univ. Wien (Austria)

1999-07-01

This paper describes the diagnostic value of new imaging techniques in characterization of adrenal masses and evaluates the role of adrenal biopsy. For differentiation of benign and malignant adrenal lesions, sensitivities and specificities of 85-100% can be reached by unenhanced computed tomography (CT) methods, chemical shift techniques in magnetic resonance imaging (MRI), delayed enhanced CT techniques, and by evaluation of wash-out curves in contrast-enhanced CT. The diagnostic value of all CT techniques depends on threshold values. The value of dynamic contrast-enhanced MRI is under discussion and should be reevaluated by using delayed enhance series. Biochemical and scintigraphic methods (NP 59 iodine iodomethyl-norcholesterol and MIBG meta-iodobenzylguanidine scintigrams) are valuable for the diagnosis of functional adrenal masses; however, they do not allow differentiation of benign and malignant tumors. According to excellent results of new imaging techniques in characterization of adrenal masses, the indications for fine-needle aspiration biopsy have already regressed, as have complications associated with this invasive technique. (orig.) [Deutsch] Diese Arbeit beschreibt die Moeglichkeiten der Charakterisierung von Nebennierenlaesionen durch die Bildgebung von neuen Untersuchungstechniken und evaluiert den geaenderten Stellenwert der Nebennierenbiopsie. Mittels der nativen Computertomographie (CT), der Chemical-Shift-Technik der Magnetresonanztomographie (MRT) oder Dichtemessungen in CT-Kontrastmittelspaetserien bzw. der Bestimmung des prozentuellen Dichteverlustes in CT-Kontrastmittelserien koennen in der Differenzierung von benignen und malignen Nebennierenlaesionen Sensitivitaeten und Spezifitaeten von 85%-100% erreicht werden. Die diagnostische Wertigkeit der CT-Techniken ist abhaengig von der Definition eines Schwellenwertes. Die Wertigkeit der dynamischen KM-verstaerkten MRT wird derzeit unterschiedlich beurteilt und sollte anhand verbesserter

Water winning in aquifers in the catchment area of the Elbe river. Task report no. 5: Radon applied for characterisation of geohydraulic processes; Wassergewinnung in Talgrundwasserleitern im Einzugsgebiet der Elbe. Teilbericht zum Thema Nr. 5: Radon zur Charakterisierung geohydraulischer Prozesse

Energy Technology Data Exchange (ETDEWEB)

Dehnert, J.; Nestler, W. [Hochschule fuer Technik und Wirtschaft, Dresden (Germany). Lab. fuer Geotechnik und Wasserwesen; Freyer, K.; Treutler, H.C. [UFZ - Umweltforschungszentrum Leipzig-Halle GmbH, Leipzig (Germany). Sektion Analytik

1998-06-09

The work performed has two objectives. The first is to test a new method for determination of optimal volumes of pumped groundwater samples at official sampling and measuring sites, in order to significantly enhance the level of representativity of groundwater samples. The second is to establish information about the required framework conditions which enable natural radon activity concentrations in river bank filtrates to be used for determination of residence times or infiltration velocities, respectively, of infiltration from surface waters to aquifers. Aspects of required equipment and instrumentation for both objectives are explained in the report. (orig./CB) [Deutsch] Mit dieser Arbeit werden zwei Ziele verfolgt. Mit dem neuen Verfahren zur Bestimmung optimaler Abpumpvolumen von Grundwassermessstellen soll die Repraesentativitaet von Grundwasserproben bei der Probennahme deutlich verbessert werden. Das zweite Ziel besteht in der Untersuchung der Voraussetzungen, unter denen die natuerliche Radonaktivitaetskonzentration des Uferfiltrats zur Bestimmung von Aufenthaltszeiten bzw. Infiltrationsgeschwindigkeiten von infiltriertem Oberflaechenwasser in Talgrundwasserleitern genutzt werden kann. Fuer beide Zielstellungen werden Moeglichkeiten fuer eine geraetetechnische Umsetzung aufgezeigt. (orig.)

Abdominal fat-evaluation by use of single scan computed tomography; Computertomographische Bestimmung des intraabdominellen Fettvolumens mittels Einschicht-Messung

Energy Technology Data Exchange (ETDEWEB)

Jacobi, V. [Klinikum der Johann-Wolfgang-Goethe-Univ., Frankfurt am Main (Germany). Inst. fuer Allgemeine Roentgendiagnostik; Steinkamp, M. [Klinikum der Johann-Wolfgang-Goethe-Univ., Frankfurt am Main (Germany). Inst. fuer Allgemeine Roentgendiagnostik; Kirchner, J. [Klinikum der Johann-Wolfgang-Goethe-Univ., Frankfurt am Main (Germany). Inst. fuer Allgemeine Roentgendiagnostik; Fischer, H. [Klinikum der Johann-Wolfgang-Goethe-Univ., Frankfurt am Main (Germany). 2. Medizinische Klinik; Diedrich, C.F. [Klinikum der Johann-Wolfgang-Goethe-Univ., Frankfurt am Main (Germany). 2. Medizinische Klinik; Kollath, J. [Klinikum der Johann-Wolfgang-Goethe-Univ., Frankfurt am Main (Germany). 2. Medizinische Klinik

1997-02-01

Purpose: Several studies emphasised the importance of the relationship between intraabdominal and total body adipose tissue as a risk factor for the development of metabolic or cardiovascular diseases. Therefore, the aim of the present study was to examine whether a single scan computed tomography is able to determine the whole intraabdominal fat volume with high accuracy and reproducibility. Materials and methods: Regions of interests (ROIs) were drawn manually for measuring intraabdominal fat in 51 unsuspicious abdominal CT. Results: The sexual differentiation of adipose tissue already described in a lot of studies could be confirmed in this study. Fat still predominates in females in lower half of the body (gynoid obesity). In men it predominates in the upper half (android obesity). Significant correlation concerning measuring the whole intraabdominal fat volume could be found in L1-level in women (r=0.992) and in L2-level in men (r=0.992). Measurement of a single scan enables us to assess whole intraabdominal fat volume due to a special formula. Conclusion: The determination of intraabdominal fat measured by a single scan computed tomography is a procedure associated with high accuracy and reproducibility. (orig.) [Deutsch] Ziel: Da in zahlreichen Studien hervorgehobene Bedeutung des intraabdominellen Fettgewebes gegenueber dem Gesamtkoerperfett als Risikofaktor fuer die Entwicklung metabolischer und kardiovaskulaerer Erkrankungen fordert ein Verfahren zur annaehernd exakten Bestimmung des intraabdominellen Fettgewebes. Ziel der vorliegenden Studie war zu pruefen, ob mit genuegender Genauigkeit die Verwendung einer Einschicht-Methode einen gezielten Einsatz der Computertomographie ermoeglicht und welche Lokalisation der zu waehlenden Schicht die aussagekraeftigste Messung ermoeglicht. Material und Methode: Anhand von 51 Computertomographien des Abdomens anderer Indikation (Normalbefunde) wurde das gesamte intraabdominelle Fettvolumen semiautomatisch mittels ROI

Plutonium fires; Incendies de plutonium

Energy Technology Data Exchange (ETDEWEB)

Mestre, E.

1959-06-23

The author reports an information survey on accidents which occurred when handling plutonium. He first addresses accidents reported in documents. He indicates the circumstances and consequences of these accidents (explosion in glove boxes, fires of plutonium chips, plutonium fire followed by filter destruction, explosion during plutonium chip dissolution followed by chip fire). He describes hazards associated with plutonium fires: atmosphere and surface contamination, criticality. The author gives some advices to avoid plutonium fires. These advices concern electric installations, the use of flammable solvents, general cautions associated with plutonium handling, venting and filtration. He finally describes how to fight plutonium fires, and measures to be taken after the fire (staff contamination control, atmosphere control)

Verfahren zur genbasierten Diagnose eines Legasthenierisikos

OpenAIRE

Wilcke, Arndt; Ahnert, Peter; Kirsten, Holger; Ligges, Carolin; Boltze, Johannes

2016-01-01

Die vorliegende Erfindung betrifft ein Verfahren zur Diagnose eines Legasthenierisikos, umfassend die Schritte: a) Bereitstellung einer Nukleinsäure beinhaltenden Probe von einem zu diagnostizierenden Menschen, b) Bestimmung des Genotyps der Nukleinsäure der Probe für mindestens eine chromosomale Region, ausgewählt aus der Gruppe bestehend aus der Region von Nukleotid 12091000 bis 12200000 des Chromosoms 1, der Region von Nukleotid 89066000 bis 89088000 des Chromosoms 15, der Region von Nukle...

Stop plutonium; Stop plutonium

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-02-01

This press document aims to inform the public on the hazards bound to the plutonium exploitation in France and especially the plutonium transport. The first part is a technical presentation of the plutonium and the MOX (Mixed Oxide Fuel). The second part presents the installation of the plutonium industry in France. The third part is devoted to the plutonium convoys safety. The highlight is done on the problem of the leak of ''secret'' of such transports. (A.L.B.)

Interpretation of ultrasonic images; Interpretation von Ultraschall-Abbildungen

Energy Technology Data Exchange (ETDEWEB)

Mueller, W; Schmitz, V; Kroening, M [Fraunhofer-Institut fuer Zerstoerungsfreie Pruefverfahren, Saarbruecken (Germany)

1998-11-01

-Signale, welche den rekonstruierten Bildpunkt verursacht haben. Hierbei handelt es sich um den Vergleich des rekonstruierten Bildes mit den zugehoerigen HF-Daten. Vergleich von zwei rekonstruierten Abbildungen durch Verknuepfung mittels logischer Operatoren. Hier wird z.B. die Rekonstruktion eines unbekannten Reflektors mit der eines Modellreflektors verglichen. Vergleich von Original-HF-Daten durch simultanes Scannen durch zwei Datensaetze. In diesem Fall werden die Echos eines unbekannten mit denen eines bekannten Reflektors verglichen. Die benoetigten Datensaetze bekannter Reflektoren koennen dabei durch Messungen an Modellreflektoren oder durch Modellierung erzeugt werden. Das Ziel ist die Identifikation des Reflektortypes, z.B. rissartig oder nicht, die Bestimmung von Position, Groesse und Orientierung sowie die Identifikation von begleitenden Satellitenechos. Die Interpretation des SAFT-rekonstruierten B-Bildes wird dabei durch eine komplette Beschreibung des Reflektors erreicht. Zusaetzlich zum angestrebten Ziel der Interpretation ist die beschriebene Software zum Ausbilden und Trainieren von Ultraschallpruefern geeignet. (orig.)

In-situ remediation strategy for enhanced microbial de-acidification of geogenic sulphuric acid mining lakes - mesocosmic studies; In situ-Sanierungsstrategie zur Foerderung der mikrobiellen Entsaeuerung von geogen schwefelsauren Bergbaurestseen - Mesokosmosstudien

Energy Technology Data Exchange (ETDEWEB)

Froemmichen, R.

2001-07-01

The author investigated whether neutralisation of acid mining lakes can be enhanced by adding low-cost, complex organic carbon sources. Subjects: Selection of a complex carbon source suited for stimulation of dissimilatory iron and sulfate reduction; design and observation of a near-natural landscape compartment (mesocosmos) at different scales as a preparation for the field study; Description of reactions in the mesocosmic lake water and sediment; Assessment of neutralisation equivalents and neutralisation rates on the basis of an identification of reduced iron and sulphur compounds. [German] Die Hypothese, dass durch Zugabe kostenguenstiger komplexer organischer Kohlenstoffquellen in die sedimentnahe Wasserzone eines sauren Tagebaurestsees seeinterne Neutralisierungsprozesse gefoerdert werden, liegt dieser Arbeit zu Grunde. Seeinterne Neutralisationsprozesse, wie die dissimilatorische Eisen- und Sulfatreduktion, fuehren ueber die Akkumulierung von reduzierten Eisen- und Schwefelverbindungen im Sediment zur Alkalinitaetsbildung im Gewaessersystem und im Seewasser zu hoeheren pH-Werten. Daher leiten sich folgende Ziele fuer diese Arbeit ab: - Auswahl einer geeigneten komplexen Kohlenstoffquelle zur Stimulierung der dissimilatorischen Eisen- und Sulfatreduktion - Design und Beobachtung eines naturnahen Landschaftsausschnittes (Mesokosmos) unterschiedlicher Massstabsebenen in Vorbereitung fuer die Fallstudie im Freiland - Beschreibung von Stoffumsetzungen im Seewasser und -sediment der Mesokosmen - Abschaetzung von Neutralisationsaequivalenten und Bestimmung von Neutralisationsraten anhand der Identifizierung reduzierter Eisen- und Schwefelverbindungen. (orig.)

Investigation of environmental samples from Fukushima with respect to uranium and plutonium by AMS; Untersuchung von Umweltproben aus Fukushima in Bezug auf Plutonium und Uran mittels AMS

Energy Technology Data Exchange (ETDEWEB)

Schneider, Stephanie

2017-02-01

In March 2011, the nuclear power plant Fukushima Dai-ichi was seriously damaged by a tsunami caused by an earthquake. During the accident large quantities of radionuclides, mainly of the volatile elements cesium and iodine, were released to the environment. In small amounts refractory elements such as plutonium and uranium have also been released. Plutonium and the uraniumisotope {sup 236}U have primarily been delivered by human activities in the environment. Large amounts were released during the atmospheric nuclear weapons tests. Additional sources are accidents in nuclear facilities, like Chernobyl. Every source has its own characteristic isotopic composition. It is therefore possible to determine the origin of the contamination by measuring the isotopic ratios of {sup 240}Pu/{sup 239}Pu and {sup 236}U/{sup 238}U. These ratios can be determined by using accelerator mass spectrometry. Due to its high sensitivity, it is possible to measure even small amounts of plutonium and especially of {sup 236}U. These measurements were performed using the compact 500 kV facility ''TANDY'' of ETH Zurich. In 2013 and 2015 vegetation, litter and soil drill core samples were taken in the contaminated area in Fukushima prefecture. In 2015 samples were taken as close to the sampling locations of the 2013 campaign as possible. After isolation of plutonium and uranium by chemical extraction, separate targets were prepared for the measurement. The {sup 240}Pu/{sup 239}Pu ratios indicate global fallout as the plutonium source for most samples. The plutonium of the reactors of Fukushima Dai-ichi is located in the upper layers like in vegetation or litter. From the uranium ratios alone the reactors could not unambigously be identified as the source of {sup 236}U. However, this is plausible in the cases were reactor plutonium was detected. None of the samples contained higher plutonium activity concentrations than in the rest of Japan, caused by global fallout. This

Measurements with high spectral resolution of backscattered radiation over clouds in the spectral range {Delta}{lambda} = 0.2 - 4.5 {mu}m. Final report; Spektral hochaufloesende Messungen rueckgestreuter Strahlung ueb Wolken im Spektralbereich {Delta}{lambda} = 0.2 - 4.5 {mu}m. Endbericht

Energy Technology Data Exchange (ETDEWEB)

Grassl, H [World Meteorological Organization (WMO), Geneva (Switzerland); Fischer, J [Freie Univ. Berlin (Germany). Inst. fuer Weltraumwissenschaften; Bakan, S [Max-Planck-Institut fuer Meteorologie, Hamburg (Germany); Armbruster, W [Freie Univ. Berlin (Germany). Inst. fuer Weltraumwissenschaften; Bartsch, B [Max-Planck-Institut fuer Meteorologie, Hamburg (Germany); Betancor, M [Hamburg Univ. (Germany). Meteorologisches Inst.; Kollewe, M [Hamburg Univ. (Germany). Meteorologisches Inst.; Schueller, L [Freie Univ. Berlin (Germany). Inst. fuer Weltraumwissenschaften

1996-12-31

The following five problems were to be investigated: 1. Explanation of the discrepancies between measured and calculated data for the absorption of solar radiation by clouds. 2. Verification and application of remote measuring methods for determining cloud height and optical density, droplet size distribution and liquid water concentrations within clouds, and cloud phases. 3. Derivation and verification of a remote measuring method for determining the total atmospheric vapour concentration. 4. Remote measuring of aerosol type and optical density. 5. Remote measurement of the total concentration of atmospheric trace gases (O{sub 3}, CO, SO{sub 2}, NO{sub 2}). (orig./KW) [Deutsch] Es sollten fuenf Teilziele untersucht werden: 1. Erklaerung der Diskrepanzen bei der Absorption der Sonnenstrahlung in Wolken, die im Vergleich von Messung und Strahlungstransportrechnung auftreten. 2. Verifizierung und Anwendung von Fernerkundungsverfahren zur Bestimmung von: - Wolkenhoehe und optischer Dicke der Wolken - Troepfchengroessenverteilung und Fluessigwassergehalt von Wolken - Wolkenphase. 3. Herleitung und Verifizierung eines Fernerkundungsverfahrens zur Bestimmung des Gesamtwasserdampfgehalts der Atmosphaere. 4. Fernerkundung von Aerosoltyp und optischer Dicke der Aerosole. 5. Fernerkundung des Gesamtgehalts atmosphaerischer Spurengase (O{sub 3}, CO, SO{sub 2} und NO{sub 2}). (orig./KW)

Mediastinal Hodgkin lymphomas in computertomography: exact CT-based volume assessment and approximations with simple geometric models; Mediastinale Hodgkin-Lymphone in der Computertomographie. Vergleich von exakter CT-gestuetzter Volumetrie und Volumenabschaetzung mit Hilfe einfacher geometrischer Modelle

Energy Technology Data Exchange (ETDEWEB)

Battmann, A. [Marburg Univ. (Germany). Abt. fuer Strahlendiagnostik; Dieckmann, K.; Resch, A.; Poetter, R. [Allgemeines Krankenhaus, Wien (Austria). Universitaetsklinik Strahlentherapie und Strahlenbiologie; Battmann, A. [Giessen Univ. (Germany). Zentrum fuer Pathologie

2001-03-01

; results in the closest approximation compared to the true volume. In the course of clinical studies it might be helpful to apply this formula to determine the prognostic relevance of the tumor size and its development under therapy. (orig.) [German] Hintergrund: Ziel dieser Arbeit waren die Bestimmung eines moeglichst exakten Modells zur Abschaetzung der Volumina von Lymphommanifestationen im Vergleich zu computertomographisch bestimmten Tumorvolumina und eine Abschaetzung der zu erwartenden Fehlerbreite. Material und Methoden: Es wurden 30 CT-Untersuchungen mediastinaler Tumoren von an Morbus Hodgkin erkrankten Kindern fuer die Untersuchung herangezogen. Die CT-Aufnahmen wurden mittels einer an einen Framegrabber angeschlossenen CCD-Videokamera digitalisiert. Mit Hilfe der GLOBAL-LAB-Image-Software wurde die Tumormasse unter Ausschluss nicht tumorzugehoeriger Binnenstrukturen ermittelt. Im Anschluss wurden die Volumina einfacher geometrischer Figuren (Quader, Ellipsoid, Oktaeder) aus den Maximalausmessungen der Tumoren errechnet. Abschliessend erfolgte die Berechnung der Abweichung der Volumina der geometrischen Modelle von dem durch das Computerprogramm ermittelten echten Tumorvolumen. Ergebnisse: Das Volumenmodell 'Quader' ueberschaetzte das Tumorvolumen um 89 bis 268%. Das Volumenmodell 'Ellipsoid' ueberschaetzte die Tumorgroesse im Mittel um 29%. Das Modell 'Oktaeder' unterschaetzte die Tumorgroesse im Mittel um 18%. Eine Division des Quadervolumens durch 2,3 approximierte das geometrische am naechsten an das Realvolumen: Im Mittel wurde das Tumorvolumen bei Tumoren, deren Volumen 20 ml ueberschritt, um 2% ueberschaetzt. Eine suffiziente Abschaetzung von Tumoren, deren Volumen weniger als 20 ml betrug, war weder mittels dieser noch mit den uebrigen Approximationen moeglich. Schlussfolgerungen: Fuer die Bestimmung von Tumorvolumina bei mediastinalen Hodgkin-Lymphomen ab 20 ml Volumen bietet die Formel Quader /2,3 die bestmoegliche

Abfallverbrennung in Deutschland - Entwicklungen und Kapazitäten (KIT Scientific Reports ; 7560)

OpenAIRE

Richers, Ulf

2010-01-01

Die Verbrennung von Abfällen bildet in Deutschland seit vielen Jahrzehnten einen wichtigen Beitrag zur Abfallentsorgung. In der Arbeit werden im ersten Teil ausgewählte Standorte von Abfallverbrennungsanlagen ausführlich beschrieben, um die Vielfalt der technischen Realisierungsmöglichkeiten und die Veränderungen im Lauf der Zeit zu dokumentieren. Der zweite Teil umfasst die Bestimmung der Verbrennungskapazität von deutschen Abfallverbrennungsanlagen, die überwiegend Siedlungsabfälle einsetze...

CONVERSION OF PLUTONIUM TRIFLUORIDE TO PLUTONIUM TETRAFLUORIDE

Science.gov (United States)

Fried, S.; Davidson, N.R.

1957-09-10

A large proportion of the trifluoride of plutonium can be converted, in the absence of hydrogen fluoride, to the tetrafiuoride of plutonium. This is done by heating plutonium trifluoride with oxygen at temperatures between 250 and 900 deg C. The trifiuoride of plutonium reacts with oxygen to form plutonium tetrafluoride and plutonium oxide, in a ratio of about 3 to 1. In the presence of moisture, plutonium tetrafluoride tends to hydrolyze at elevated temperatures and therefore it is desirable to have the process take place under anhydrous conditions.

Polycyclic aromatic hydrocarbons (PAHs), their transfer into and dislocation within soil; Eintraege von polyzyklischen aromatischen Kohlenwasserstoffen (PAH) und ihre Verlagerung im Boden

Energy Technology Data Exchange (ETDEWEB)

Duerbeck, H W; Niehaus, R; Mueller, U; Bueker, I [Forschungszentrum Juelich GmbH (Germany). Inst. fuer Angewandte Physikalische Chemie

1998-12-31

In order to assess the terrestrial hazard potential of polycyclic aromatic hydrocarbons (PAHs), it is vital to investigate their nuisance concentrations and deposition to soil and plants as well as their dislocation in soil. This was the object of the first part of the research programme ``Locational evaluation of chemical soil pollution``, conducted by the national research institutions. It was headed ``Analysis of exposure`` and comprised the following individual contributions: 1. Integrated long-term measurements of polycyclic aromatic hydrocarbons in soil air at ground level (FZJ), 2. Determination of PAH nuisance concentrations at the Scheyern experimental station as well as at the motorway by-passing Munich to the east (A 99), near Kirchheim (GSF), 3. Investigations regarding PAH exposure via the air pathway and inclusion of acquired data in substance flows made up for the east-German dry zone (Bad Lauchstaedt), (UFZ), 4. Simulation of PAH concentration and deposition in south-western Germany (FZK). (orig./SR) [Deutsch] Zur Abschaetzung des Gefaehrdungspotentials von Polycyclischen Aromatischen Kohlenwasserstoffen (PAK) im terrestrischen Bereich sind daher Untersuchungen ueber die Immissionskonzentrationen und die Deposition auf Boeden und Pflanzen sowie ueber ihre Verlagerung im Boden von essentieller Bedeutung. Die Bearbeitung dieser Thematik erfolgte im Teilbereich I `Eintragsanalyse` des AGF-Programms `Standortgerechte Bewertung chemischer Bodenbelastungen` mit folgenden Einzelbeitraegen: 1. Integrierende Langzeitmessung von Polycyclischen Aromatischen Kohlenwasserstoffen in bodennaher Luft, (FZJ) 2. Bestimmung der PAH-Immissionskonzentrationen am Versuchsgut Scheyern sowie an der oestlichen Autobahnumgehung von Muenchen (A 99) bei Kirchheim, (GSF) 3. Untersuchungen zum Eintrag von PAH ueber den Luftpfad und Einbeziehung der Daten in Stoffkreislaeufe im Mitteldeutschen Trockengebiet (Bad Lauchstaedt), (UFZ) 4. Simulation der PAH-Konzentration und

Polycyclic aromatic hydrocarbons (PAHs), their transfer into and dislocation within soil; Eintraege von polyzyklischen aromatischen Kohlenwasserstoffen (PAH) und ihre Verlagerung im Boden

Energy Technology Data Exchange (ETDEWEB)

Duerbeck, H.W.; Niehaus, R.; Mueller, U.; Bueker, I. [Forschungszentrum Juelich GmbH (Germany). Inst. fuer Angewandte Physikalische Chemie

1997-12-31

In order to assess the terrestrial hazard potential of polycyclic aromatic hydrocarbons (PAHs), it is vital to investigate their nuisance concentrations and deposition to soil and plants as well as their dislocation in soil. This was the object of the first part of the research programme ``Locational evaluation of chemical soil pollution``, conducted by the national research institutions. It was headed ``Analysis of exposure`` and comprised the following individual contributions: 1. Integrated long-term measurements of polycyclic aromatic hydrocarbons in soil air at ground level (FZJ), 2. Determination of PAH nuisance concentrations at the Scheyern experimental station as well as at the motorway by-passing Munich to the east (A 99), near Kirchheim (GSF), 3. Investigations regarding PAH exposure via the air pathway and inclusion of acquired data in substance flows made up for the east-German dry zone (Bad Lauchstaedt), (UFZ), 4. Simulation of PAH concentration and deposition in south-western Germany (FZK). (orig./SR) [Deutsch] Zur Abschaetzung des Gefaehrdungspotentials von Polycyclischen Aromatischen Kohlenwasserstoffen (PAK) im terrestrischen Bereich sind daher Untersuchungen ueber die Immissionskonzentrationen und die Deposition auf Boeden und Pflanzen sowie ueber ihre Verlagerung im Boden von essentieller Bedeutung. Die Bearbeitung dieser Thematik erfolgte im Teilbereich I `Eintragsanalyse` des AGF-Programms `Standortgerechte Bewertung chemischer Bodenbelastungen` mit folgenden Einzelbeitraegen: 1. Integrierende Langzeitmessung von Polycyclischen Aromatischen Kohlenwasserstoffen in bodennaher Luft, (FZJ) 2. Bestimmung der PAH-Immissionskonzentrationen am Versuchsgut Scheyern sowie an der oestlichen Autobahnumgehung von Muenchen (A 99) bei Kirchheim, (GSF) 3. Untersuchungen zum Eintrag von PAH ueber den Luftpfad und Einbeziehung der Daten in Stoffkreislaeufe im Mitteldeutschen Trockengebiet (Bad Lauchstaedt), (UFZ) 4. Simulation der PAH-Konzentration und

Further development of landfill sealing systems. Subproject 20: long-term behaviour of earthen layers in landfill liners, moisture conditions under the action of temperature; Weiterentwicklung von Deponieabdichtungssystemen. Teilvorhaben 20: Langzeitverhalten von Erdstoffschichten in Deponiebasisabdichtungen, Feuchtehaushalt unter Temperatureinwirkung

Energy Technology Data Exchange (ETDEWEB)

Holzloehner, U.; Schossig, W.; Wuttke, W.; Ziegler, F.

1996-12-31

The sealing properties of the earthen layers in landfill liners depend on water content, which is not constant but changes according to the moisture conditions of the landfill and the adjacent soil. Earthen layers in landfill liners tend to lose water over the course of time and this may result in desiccation cracking. To study the behaviour of soils undergoing desiccation, test devices and methods were developed to evaluate the water transport characteristics of soil samples. Measurement of the temporal and spatial changes in moisture distribution within the cylindrical soil sample was accompanied by a calculation in which diffusion coefficients were iteratively varied so as to reach optimum agreement with the observed moisture distribution. Overburden pressure can to some extent prevent desiccation. Therefore test devices were developed which made it possible to load soil samples simultaneously by vertical stress and by suction. (orig./SR) [Deutsch] Die Dichtigkeit von Erdstoffschichten in Deponieabdichtungen haengt vom Wassergehalt ab, der nicht konstant ist, sondern sich entsprechend dem Feuchtehaushalt von Deponie und umgebendem Boden aendert. Die Erdstoffabdichtungssschichten tendieren langfristig zum Trocknerwerden, wodurch es zu Rissen kommen kann. Um das Austrocknungsverhalten zu untersuchen, wurden Versuchsgeraete und -verfahren zur Bestimmung von Wassertransportkennwerten an Bodenproben entwickelt. Die Messung der zeitlichen und oertlichen Aenderung der Feuchteverteilung in der zylindrischen Bodenprobe wurde durch eine Rechnung begleitet, in der die eingegebenen Diffusionskoeffizienten iterativ variiert wurden, bis optimale Uebereinstimmung mit der gemessenen Feuchteverteilung erreicht war. Auflast kann Austrocknung bis zu einem gewissen Grad verhindern. Deshalb wurden Geraete entwickelt, in denen Bodenproben gleichzeitig einer Wasserspannung und einer vertikalen Spannung ausgesetzt werden koennen. (orig./SR)

Development of units for change measurement of batteries at photovoltaic plant. Final report; Entwicklung von Einheiten zur Ladezustandserfassung von Batterien in PV-Anlagen. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Rothert, M.; Knorr, R.; Willer, B.

1996-12-31

The aim of the project was to contribute to enhanced service life and reliability of batteries in photovoltaic systems by developing further processes and components for charge measurement. The essential basic information in charge determination is the direct measurement of acid concentration in the electrolyte compartment of lead batteries and the evaluation and processing of this signal. Within the framework of this project, operative acidity sensors were developed and tested. They are accurate within an error margin of 0.5 per cent for short periods and of 2 per cent for long periods. A charge measurement unit based on the acid concentration reading was built and special algorithms for measuring charge were developed and tested. This unit stands out particularly because of the following: determination of dynamic charge, long-term stability, and automatic and regular adaptation to the type, size and age of the battery. Using this unit in combination with the acid concentration sensor in photovoltaic plant will permit more efficient plant operation and reliable protection of the battery. (orig./MM) [Deutsch] Ziel des Vorhabens war es, Massnahmen zur Verbesserung der Lebensdauer und Zuverlaessigkeit von Batterien in PV-Anlagen durch die konkrete Weiterentwicklung von Verfahren und Komponenten zur Ladezustandserfassung aufzuzeigen, durchzufuehren und zu demonstrieren. Die direkte Messung der Saeuredichte im Elektrolytraum von Bleibatterien sowie die Auswertung und Weiterverarbeitung dieses Signals bildet dabei die wesentliche Basisinformation. Im Rahmen des Vorhabens wurden funktionstuechtige Saeuredichtesensoren entwickelt und erprobt. Die dabei erreichte Genauigkeit betraegt im Kurzzeitbereich 0,5% und im Langzeitbereich ca. 2%. Eine Ladezustandseinheit basierend auf dem Saeuredichtesignal wurde aufgebaut und spezielle Algorithmen zur Ladezustandserfassung entwickelt und getestet. Besonders die Bestimmung des dynamischen Ladezustands, die Langzeitstabilitaet sowie

Measurements of emission rates of hydrocarbons from sunflower as a function of temperature, light intensity and stress (ozone levels); Bestimmung von Emissionsraten pflanzlicher Kohlenwasserstoffe bei Sonnenblumen in Abhaengigkeit von Temperatur, Lichtintensitaet und Stress, insbesondere von der Belastung mit Ozon

Energy Technology Data Exchange (ETDEWEB)

Schuh, G.; Wildt, J.; Kley, D.

1996-08-01

The emission rates of isoprene, mono- and sesquiterpenes from sunflower (Helianthus annuus L. cv. giganteus) were determined in an environmental chamber, a continuously stirred tank reactor. {alpha}-pinene, {beta}-caryophyllene and two oxygenated compounds were emitted. The emission rates of all terpenes increased exponentially with temperature. Substance specific differences of the rate of increase of the emission rates were observed. For all substances the dependence of their emission rates on temperature increased with increasing light intensity. Increasing lightflux resulted in an increase of the emission rates for all substances. The raise of emission rates with lightflux was dependent on temperature and increased with increasing temperature. During periods without plant stress the emission rates exhibited a good correlation with the rate of transpiration as well as with the rate of net photosynthesis. Sunflowers emitted higher amounts of terpenes when they were stressed by mechanical, wounding and ozone treatment as well as nutrient- or water deficiency. The emission rates increased by a factor of 5-300. Exposure with ozone had an effect on hydrocarbon emission rates with a delay-time. 3-4 h after exposure with 25-120 ppb ozone the emission rates increased by factor of 5-100. This increase was only observed on the first day of exposure. Nutrient deficiency resulted in an increase of emission rates by a factor of 10-300. In situations of mechanical, wounding and ozone stress, substance specific changes in the emission spectrum were observed. A model was developed to explain the observed phenomena. The main pathway of ozone loss in the chamber is caused by the uptake through the stomata of the plants. However, up to 50% of the ozone loss must be explained by other processes indirectly caused by the plants. (orig./MG) [Deutsch] In Laborversuchen wurden Emissionsraten biogener Kohlenwasserstoffe von Sonnenblumen gemessen. Die groessten Emissionsraten wiesen die

Konkomitantes Auftreten von Lichen sclerosus und Hashimoto-Thyreoiditis

Directory of Open Access Journals (Sweden)

Eberz B

2009-01-01

Full Text Available Der Lichen sclerosus (LS zählt zu den chronisch entzündlichen Hauterkrankungen, der auf dem Boden einer Immundysregulierung entsteht. Per 01.06.2009 war die Prävalenz des klinisch und stanzbioptisch diagnostizierten anogenitalen Lichen sclerosus in einer allgemein gynäkologischen Praxis in Mürzzuschlag 9,1 % (278/3040 Patientinnen. Die frühzeitige Abklärung chronischer Vulvabeschwerden unter standardmäßiger Einbeziehung einer Vulvabiopsie erlaubte es, auch Frühformen des LS zu erfassen. Nach klinischer und stanzbioptischer Diagnose eines LS wird in Anlehnung an die "Guidelines for the Management of Lichen Sclerosus" [1] ein serologisches Screening auf Autoantikörper (TPO-AK, TG-AK, Parietalzell- und antinukleäre Antikörper durchgeführt. Bei 263 unserer 278 LS-Patientinnen wurde ein serologisches Screening auf Autoimmunerkrankungen durchgeführt. Insgesamt hatten 58/263 LS-Patientinnen pathologisch erhöhte Thyroidperoxidase-(TPO- und/oder Thyreoglobulin- (TG- Antikörpertiter (23 %, davon 50/263 (19 % auch eine sonographisch bestätigte Hashimoto-Thyreoiditis. Bei 50 % dieser Hashimoto-Patientinnen war bereits im Vorfeld eine Hypothyreose bekannt, bei den restlichen 25 Patientinnen handelte es sich allerdings um eine Erstdiagnose im Rahmen des Screenings für LS. Aufgrund der hohen Prävalenz von Hashimoto-Thyreoiditis in LS-Patientinnen empfehlen wir bei allen Frauen mit LS ein Screening auf TPO- und TG-Antikörper. Bei erhöhten Titern sollte eine Abklärung mittels Schilddrüsensonogramm sowie eine Bestimmung von basalem "thyroid-stimulating hormone" (TSH, freiem T3 und freiem T4 erfolgen. In der Schilddrüsensprechstunde sollten Frauen mit Hashimoto-Thyreoiditis gezielt nach chronischen bzw. rezidivierenden anogenitalen Beschwerden, insbesondere Pruritus, Brennen oder Dyspareunie befragt werden. Bei positiver Anamnese ist eine Zuweisung an einen auf Vulvaerkrankungen spezialisierten Facharzt für Gynäkologie sinnvoll.

Plutonium in nature; Le plutonium dans la nature

Energy Technology Data Exchange (ETDEWEB)

Madic, C.

1994-12-31

Plutonium in nature comes from natural sources and anthropogenic ones. Plutonium at the earth surface comes principally from anthropogenic sources. It is easily detectable in environment. The plutonium behaviour in environment is complex. It seems necessary for the future to reduce releases in environment, to improve predictive models of plutonium behaviour in geosphere, to precise biological impact of anthropogenic plutonium releases.

Belastung des Bodensees mit organischen Spurenstoffen : Bestimmung von polychlorierten Biphenylen und polybromierten Diphenylethern in Sedimenten, Muscheln und Fischen

OpenAIRE

Pfeiffer, Jörg Alexander

2011-01-01

Persistente organische Mikroverunreinigungen können über die Zuflüsse in den Bodensee eingetragen werden, insbesondere wenn diese einen höheren Abwasseranteil haben. Besonders für lipophilere Verbindungen besteht die Gefahr, dass sie sich dort in Sedimenten ablagern und in Fischen und Muscheln anreichern. Typische Vertreter von problematischen Verunreinigungen sind polychlorierten Biphenyle (PCB), die aufgrund ihrer toxischen Eigenschaften bereits vor über 20 Jahren verboten wurden. Eine m...

Experimental studies to validate model calculations and maximum solubility limits for Plutonium and Americium; Experimentelle Arbeiten zur Absicherung von Modellrechnungen und Maximalkonzentrationen fuer Plutonium und Americium

Energy Technology Data Exchange (ETDEWEB)

NONE

2017-02-16

This report focuses on studies of KIT-INE to derive a significantly improved description of the chemical behaviour of Americium and Plutonium in saline NaCl, MgCl{sub 2} and CaCl{sub 2} brine systems. The studies are based on new experimental data and aim at deriving reliable Am and Pu solubility limits for the investigated systems as well as deriving comprehensive thermodynamic model descriptions. Both aspects are of high relevance in the context of potential source term estimations for Americium and Plutonium in aqueous brine systems and related scenarios. Americium and Plutonium are long-lived alpha emitting radionuclides which due to their high radiotoxicity need to be accounted for in a reliable and traceable way. The hydrolysis of trivalent actinides and the effect of highly alkaline pH conditions on the solubility of trivalent actinides in calcium chloride rich brine solutions were investigated and a thermodynamic model derived. The solubility of Plutonium in saline brine systems was studied under reducing and non-reducing conditions and is described within a new thermodynamic model. The influence of dissolved carbonate on Americium and Plutonium solubility in MgCl{sub 2} solutions was investigated and quantitative information on Am and Pu solubility limits in these systems derived. Thermodynamic constants and model parameter derived in this work are implemented in the Thermodynamic Reference Database THEREDA owned by BfS. According to the quality assurance approach in THEREDA, is was necessary to publish parts of this work in peer-reviewed scientific journals. The publications are focused on solubility experiments, spectroscopy of aquatic and solid species and thermodynamic data. (Neck et al., Pure Appl. Chem., Vol. 81, (2009), pp. 1555-1568., Altmaier et al., Radiochimica Acta, 97, (2009), pp. 187-192., Altmaier et al., Actinide Research Quarterly, No 2., (2011), pp. 29-32.).

Multitracer studies for determining seepage water and anion movement in four types of soil using lysimeters with different functions and designs; Multitracer-Untersuchungen zur Bestimmung der Sickerwasser- und Anionenbewegung in vier Bodenformen bei Lysimetern unterschiedlicher Nutzung und Bauart

Energy Technology Data Exchange (ETDEWEB)

Knappe, S.; Russow, R. [UFZ - Umweltforschungszentrum Leipzig-Halle GmbH, Bad Lauchstaedt (Germany). Sektion Bodenforschung; Seeger, J. [Lysimeterstation Falkenberg (Germany)

1999-02-01

Lysimeter experiments based on the stable isotope tracer technique are a suitable means of examining the complex relationships governing water and material transport processes in the soil. The present paper reports on experiments in which water and nitrate movement was traced directly by means of lysimeters placed at different depths and using deuterium water and [{sup 15}N]N-nitrate for pulse marking. Extensive investigations carried out during the dissection of soil monoliths that had been used for many years in lysimeters offered an opportunity for stable isotope tracer studies aimed at determining seepage water and anion movement in undisturbed soils and, after dismantling the lysimeters, conducting soil analyses to find out more about the fate of nonpercolated tracers at various soil depths. Following other authors, bromide anions were additionally used as conservative tracers. [Deutsch] Zur Untersuchung der komplexen Zusammenhaenge des Wasser- und Stofftransportes im Boden bieten sich Lysimeterversuche unter Nutzung der stabilisotopen Tracertechnik an. In der vorliegenden Arbeit wird zunaechst ueber die direkte Verfolgung der Wasser- und Nitrat-Bewegung in tiefengestaffelten Lysimetern durch Pulsmarkierung mit Deuteriumwasser und [{sup 15}N]Nitrat berichtet. Im Rahmen von umfangreichen Untersuchungen bei der Zerlegung von langjaehrig in Lysimetern genutzten Bodenmonolithen bestand des weiteren die Moeglichkeit, stabilisotope Traceruntersuchungen zur Bestimmung der Sickerwasser- und Anionenbewegung an ungestoerten Boeden durchzufuehren und nach der Zerlegung der Lysimeter ueber entsprechende Analysen des Bodens Aussagen zum Verbleib der nicht perkolierten Tracer in verschiedenen Bodentiefen zu treffen. Zusaetzlich wurde dabei das von anderen Autoren bereits genutzte Bromid-Anion als sogenannter konservativer Tracer eingesetzt. (orig.)

Does an individual estimation of halflife improve the results of radioiodine therapy of Graves' disease?; Verbessert die individuelle Bestimmung der effektiven Halbwertszeit die Ergebnisse der Radioiodtherapie des Morbus Basedow?

Energy Technology Data Exchange (ETDEWEB)

Schneider, P.; Koerber, C.; Koerber-Hafner, N.; Haenscheid, H.; Reiners, Chr. [Klinik und Poliklinik fuer Nuklearmedizin der Univ. Wuerzburg (Germany)

2002-12-01

significantly improve. In addition, no influence of antithyroid medication on therapy success was found. (orig.) [German] Ziel: Der Einfluss unseres Dosimetriekonzepts auf den Erfolg der radioiodtherapie (RIT) bei Morbus Basedow wurde bezueglich dreier Fragen untersucht: Verbessert die individuelle praetherapeutische Bestimmung der Halbwertszeit (HWZ) im Radioiodtest den Therapieerfolg? Erlaubt die intratherapeutische Dosimetrie eine akkurate Dosiskalkulation? Zeigt eine thyreostatische Medikation einen messbaren Einfluss auf den Therapieerfolg? Methode: 126 Patienten erhielten wegen eines Morbus Basedow eine praetherapeutische Dosimetrie (Zieldosis: 200 Gy) mit zwei Methoden, die eine Bestimmung der HWZ oder eine Naeherungsloesung einschliesst. Die Behandlung wurde nach 6-9 Monaten als erfolgreich betrachtet, wenn der Zustand eu- oder hypothyreot war. Bei Hyperthyreose oder supprimiertem basalen TSH-Wert nach Absetzen der Thyreostatika wurde die RIT als Misserfolg gewertet. Thyreostatika, applizierte Aktivitaet, Dosis, spezifische Dosis pro Gewebe und HWZ wurden mittels der multiplen Regressionsanalyse bezueglich ihres Effekts auf den Therapieerfolg untersucht. Mit Logit-Transformation wurden relevante Parameter auf die Chancenverteilung einer erfolgreichen oder erfolglosen RIT untersucht. Ergebnisse: Von 126 Patienten wurden 42 (33,3%) ohne Erfolg und 84 (66,6%) erfolgreich therapiert. Bei Patienten mit geschaetzter intratherapeutischer HWZ entsprach die Erfolgsquote der bei individuell bestimmter HWZ. Die Wahrscheinlichkeit eines Therapieerfolgs war bei der intratherapeutisch geschaetzten HWZ hoeher (Odds: 10,0) als bei der individuell gemessenen. Die erzielte Dosis zeigte eine stark von der Organmasse abhaengige Streuung, die zu sehr unterschiedlichen spezifischen Dosen fuehrte. Die thyreostatische Medikation hatte keinen Einfluss. Schlussfolgerung: Durch individuelle praetherapeutische Dosimetrie mit kompletter Radioiodkinetik gegenueber einer einfachen individuellen

Plutonium

International Nuclear Information System (INIS)

Watson, G.M.

1976-01-01

Discovery of the neutron made it easy to create elements which do not exist in nature. One of these is plutonium, and its isotope with mass number 239 has nuclear properties which make it both a good fuel for nuclear power reactors and a good explosive for nuclear weapons. Since it was discovered during a war the latter characteristic was put to use, but it is now evident that use of plutonium in a particular kind of nuclear reactor, the fast breeder reactor, will allow the world's resources of uranium to last for millennia as a major source of energy. Plutonium is very radiotoxic, resembling radium in this respect. Therefore the widespread introduction of fast breeder reactors to meet energy demands can be contemplated only after assurances on two points; that adequate control of the radiological hazard resulting from the handling of very large amounts of plutonium can be guaranteed, and that diversion of plutonium to illicit use can be prevented. The problems exist to a lesser degree already, since all types of nuclear reactor produce some plutonium. Some plutonium has already been dispersed in the environment, the bulk of it from atmospheric tests of nuclear weapons. (author)

Non-destructive testing of concrete structures with the impact-echo method; Zerstoerungsfreie Pruefung von Betonbauteilen mit dem Impact-Echo-Verfahren

Energy Technology Data Exchange (ETDEWEB)

Algernon, Daniel; Feistkorn, Sascha; Scherrer, Michael [SVTI Schweizerischer Verein fuer technische Inspektionen, Wallisellen (Switzerland). Nuklearinspektorat

2016-05-01

The impact-echo method is based on the use of elastic waves. It was developed in the 1980 for the testing of concrete structures and is currently widespread. Main application areas are the component and coating thickness measurement and detection of delaminations, voids and other defects. Specifically, the method is also used to check the injection faults of clamping channels. Another application is the determination of mechanical material parameters such as the modulus of elasticity. Since the original development of the method has undergone several enhancements. The conversion of a single-point measurement method towards a area component testing, the use by the optimized measurement data acquisition and evaluation enlarged and delivered an important prerequisite for increasing the efficiency. The use of air-coupled sensors not only increases the measurement speed but also provides advantages in rough component surfaces. The imaging analysis in conjunction with signal processing algorithms simplifies the interpretation and allows statistical evaluation. [German] Das Impact-Echo-Verfahren beruht auf der Nutzung elastischer Wellen. Es wurde in den 1980er Jahren fuer die Pruefung von Stahlbetonbauteilen entwickelt und ist derzeit weit verbreitet. Haupteinsatzgebiete sind die Bauteil- und Schichtdickenmessung sowie die Detektion von Delaminationen, Hohl- und anderen Fehlstellen. Insbesondere wird das Verfahren auch zur Pruefung des Verpresszustandes von Spannkanaelen herangezogen. Eine weitere Anwendung ist die Bestimmung mechanischer Materialparameter wie dem Elastizitaetsmodul. Seit der urspruenglichen Entwicklung hat das Verfahren verschiedene Weiterentwicklungen erfahren. Die Ueberfuehrung von einem Einzelpunktmessverfahren hin zu einer flaechigen Bauteilpruefung hat die Einsatzmoeglichkeiten durch die optimierte Messdatenaufnahme und -auswertung vergroessert und eine wichtige Voraussetzung zur Erhoehung der Leistungsfaehigkeit geliefert. Der Einsatz

Plutonium Finishing Plant. Interim plutonium stabilization engineering study

Energy Technology Data Exchange (ETDEWEB)

Sevigny, G.J.; Gallucci, R.H.; Garrett, S.M.K.; Geeting, J.G.H.; Goheen, R.S.; Molton, P.M.; Templeton, K.J.; Villegas, A.J. [Pacific Northwest Lab., Richland, WA (United States); Nass, R. [Nuclear Fuel Services, Inc. (United States)

1995-08-01

This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage.

Plutonium Finishing Plant. Interim plutonium stabilization engineering study

International Nuclear Information System (INIS)

Sevigny, G.J.; Gallucci, R.H.; Garrett, S.M.K.; Geeting, J.G.H.; Goheen, R.S.; Molton, P.M.; Templeton, K.J.; Villegas, A.J.; Nass, R.

1995-08-01

This report provides the results of an engineering study that evaluated the available technologies for stabilizing the plutonium stored at the Plutonium Finishing Plant located at the hanford Site in southeastern Washington. Further processing of the plutonium may be required to prepare the plutonium for interim (<50 years) storage. Specifically this document provides the current plutonium inventory and characterization, the initial screening process, and the process descriptions and flowsheets of the technologies that passed the initial screening. The conclusions and recommendations also are provided. The information contained in this report will be used to assist in the preparation of the environmental impact statement and to help decision makers determine which is the preferred technology to process the plutonium for interim storage

Stop plutonium

International Nuclear Information System (INIS)

2003-02-01

This press document aims to inform the public on the hazards bound to the plutonium exploitation in France and especially the plutonium transport. The first part is a technical presentation of the plutonium and the MOX (Mixed Oxide Fuel). The second part presents the installation of the plutonium industry in France. The third part is devoted to the plutonium convoys safety. The highlight is done on the problem of the leak of ''secret'' of such transports. (A.L.B.)

Determination of plutonium in pure plutonium nitrate solutions - Gravimetric method

International Nuclear Information System (INIS)

1987-01-01

This International Standard specifies a precise and accurate gravimetric method for determining the concentration of plutonium in pure plutonium nitrate solutions and reference solutions, containing between 100 and 300 g of plutonium per litre, in a nitric acid medium. The weighed portion of the plutonium nitrate is treated with sulfuric acid and evaporated to dryness. The plutonium sulfate is decomposed and formed to oxide by heating in air. The oxide is ignited in air at 1200 to 1250 deg. C and weighed as stoichiometric plutonium dioxide, which is stable and non-hygroscopic

Precipitation of plutonium (III) oxalate and calcination to plutonium oxide

International Nuclear Information System (INIS)

Esteban, A.; Orosco, E.H.; Cassaniti, P.; Greco, L.; Adelfang, P.

1989-01-01

The plutonium based fuel fabrication requires the conversion of the plutonium nitrate solution from nuclear fuel reprocessing into pure PuO2. The conversion method based on the precipitation of plutonium (III) oxalate and subsequent calcination has been studied in detail. In this procedure, plutonium (III) oxalate is precipitated, at room temperature, by the slow addition of 1M oxalic acid to the feed solution, containing from 5-100 g/l of plutonium in 1M nitric acid. Before precipitation, the plutonium is adjusted to trivalent state by addition of 1M ascorbic acid in the presence of an oxidation inhibitor such as hydrazine. Finally, the precipitate is calcinated at 700 deg C to obtain PuO2. A flowsheet is proposed in this paper including: a) A study about the conditions to adjust the plutonium valence. b) Solubility data of plutonium (III) oxalate and measurements of plutonium losses to the filtrate and wash solution. c) Characterization of the obtained products. Plutonium (III) oxalate has several potential advantages over similar conversion processes. These include: 1) Formation of small particle sizes powder with good pellets fabrication characteristics. 2) The process is rather insensitive to most process variables, except nitric acid concentration. 3) Ambient temperature operations. 4) The losses of plutonium to the filtrate are less than in other conversion processes. (Author) [es

Plutonium-236 traces determination in plutonium-238 by α spectrometry

International Nuclear Information System (INIS)

Acena, M.L.; Pottier, R.; Berger, R.

1969-01-01

Two methods are described in this report for the determination of plutonium-236 traces in plutonium-238 by a spectrometry using semi-conductor detectors. The first method involves a direct comparison of the areas under the peaks of the α spectra of plutonium-236 and plutonium-238. The electrolytic preparation of the sources is carried out after preliminary purification of the plutonium. The second method makes it possible to determine the 236 Pu/ 238 Pu ratio by comparing the areas of the α peaks of uranium-232 and uranium-234, which are the decay products of the two plutonium isotopes respectively. The uranium in the source, also deposited by electrolysis, is separated from a 1 mg amount of plutonium either by a T.L.A. extraction, or by the use of ion-exchange resins. The report ends with a discussion of the results obtained with plutonium of two different origins. (authors) [fr

Plutonium controversy

International Nuclear Information System (INIS)

Gofman, J.W.

1976-01-01

If the world chooses to seek a solution to the energy dilemma through nuclear energy, the element plutonium will become an article of commerce to be handled in quantities of thousands of tonnes annually. Plutonium is a uniquely potent inhalation carcinogen, the potential induction of lung cancer dwarfing other possible toxic effects. For reasons to be presented here, it is the author's opinion that plutonium's carcinogenicity has been very seriously underestimated. If one couples the corrected carcinogenicity with the probable degree of industrial containment of the plutonium, it appears that the commercialization of a plutonium-based energy economy is not an acceptable option for society. Sagan's statement that ''the experience of 30 years supports the contention that plutonium can be used safely'' is manifestly indefensible. No meaningful epidemiological study of plutonium-exposed workers for that 30-year period has ever been done. Since thousands of those possibly exposed have left the industry and are not even available to follow-up, it is doubtful that any meaningful study of ''the experience of 30 years'' will ever be accomplished

Preparation of hexavalent plutonium and its determination in the presence of tetravalent plutonium; Preparation de plutonium hexavalent et dosage en presence de plutonium tetravalent

Energy Technology Data Exchange (ETDEWEB)

Corpel, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires; Corpel, J [Institut du Radium, 75 - Paris (France)

1958-07-01

In order to study the eventual reduction of plutonium from the VI-valent state to the IV-valent state, in sulphuric medium, under the influence of its own {alpha} radiation or of the {gamma}-rays from a cobalt-60 source, we have developed a method for preparing pure hexavalent plutonium and two methods for determining solutions containing tetravalent and hexavalent plutonium simultaneously. Hexavalent plutonium was prepared by anodic oxidation at a platinum electrode. Study of the oxidation yield as a function of various factors has made it possible to define experimental conditions giving complete oxidation. For concentrations in total plutonium greater than 1.5 x 10{sup -3} M, determination of the two valencies IV and VI was carried out by spectrophotometry at two wavelengths. For lower concentrations, the determination was done by counting, after separation of the tetravalent plutonium in the form of fluoride in the presence of a carrier. (author) [French] Afin d'etudier l'eventuelle reduction du plutonium de l'etat de valence VI a l'etat de valence IV, en milieu sulfurique sous l'influence de son propre rayonnement {alpha} ou des rayons {gamma} d'une source de cobalt-60, nous avons mis au point une methode de preparation de plutonium hexavalent pur et deux methodes de dosage des solutions contenant simultanement du plutonium tetravalent et du plutonium hexavalent. Nous avons prepare le plutonium hexavalent par oxydation anodique au contact d'une electrode de platine. L'etude de rendement de l'oxydation en fonction des divers facteurs nous a permis de definir des conditions experimentales donnant une oxydation complete. Pour des concentrations en plutonium total superieures a 1,5.10{sup -3} M, le dosage des deux valences IV et VI a ete realise par spectrophotometrie a deux longueurs d'onde. Pour des concentrations inferieures, le dosage a ete effectue par comptage apres separation du plutonium tetravalent sous la forme du fluorure en presence d'un entraineur

Plutonium in nature

International Nuclear Information System (INIS)

Madic, C.

1994-01-01

Plutonium in nature comes from natural sources and anthropogenic ones. Plutonium at the earth surface comes principally from anthropogenic sources. It is easily detectable in environment. The plutonium behaviour in environment is complex. It seems necessary for the future to reduce releases in environment, to improve predictive models of plutonium behaviour in geosphere, to precise biological impact of anthropogenic plutonium releases

SEPARATION OF PLUTONIUM

Science.gov (United States)

Maddock, A.G.; Smith, F.

1959-08-25

A method is described for separating plutonium from uranium and fission products by treating a nitrate solution of fission products, uranium, and hexavalent plutonium with a relatively water-insoluble fluoride to adsorb fission products on the fluoride, treating the residual solution with a reducing agent for plutonium to reduce its valence to four and less, treating the reduced plutonium solution with a relatively insoluble fluoride to adsorb the plutonium on the fluoride, removing the solution, and subsequently treating the fluoride with its adsorbed plutonium with a concentrated aqueous solution of at least one of a group consisting of aluminum nitrate, ferric nitrate, and manganous nitrate to remove the plutonium from the fluoride.

Macromolecular contrast media. A new approach for characterising breast tumors with MR-mammography; Makromolekulare Kontrastmittel fuer die MR-Mammographie. Ein neuer Ansatz fuer die Charakterisierung von Mammatumoren

Energy Technology Data Exchange (ETDEWEB)

Daldrup, H.E. [Contrast Media Lab., Dept. of Radiology, California Univ., San Francisco, CA (United States)]|[Muenster Univ. (Germany). Inst. fuer Klinische Radiologie; Roberts, T.P.L.; Roberts, H.C. [Contrast Media Lab., Dept. of Radiology, California Univ., San Francisco, CA (United States)]|[Mainz Univ. (Germany). Klinik und Poliklinik fuer Radiologie; Muehler, A. [Contrast Media Lab., Dept. of Radiology, California Univ., San Francisco, CA (United States)]|[Berlex Laboratories, Wayne, NJ (United States); Gossmann, A. [Contrast Media Lab., Dept. of Radiology, California Univ., San Francisco, CA (United States)]|[Koeln Univ. (Germany). Inst. und Poliklinik fuer Radiologische Diagnostik; Wendland, M.; Brasch, R.C. [Muenster Univ. (Germany). Inst. fuer Klinische Radiologie; Rosenau, W. [California Univ., San Francisco, CA (United States). Dept. of Pathology

1997-09-01

The value of macromolecular contrast agents (MMCM) for the characterization of benign and malignant breast tumors will be demonstrated in this review. Animal studies suggest a high potential of MMCM to increase the specificity of MR-mammography. The concept of tumor differentiation is based on the pathological hyperpermeability of microvessels in malignant tumors. MMCM show a leak into the interstitium of carcinomas, whereas they are confined to the intravascular space in benign tumors. Capabilities and limitations of the MMCM-prototype. Albumin-Gd-DTPA, for breast tumor characterization will be summarized and compared to the standard low molecular weight contrast agent Gd-DTPA. Initial experience with new MMCM, such as Dendrimers, Gd-DTPA-Polylysine and MS-325 will be outlined. The potential of `blood-pool`-iron oxides, such as AMI-227 for the evaluation of tumor microvascular permeabilities will be discussed. (orig.) [Deutsch] Diese Uebersicht stellt den Stellenwert makromolekularer Kontrastmittel (MMKM) fuer die MR-tomographische Charakterisierung von benignen und malignen Mammatumoren dar. Aufgrund experimenteller Studien lassen MMKM eine signifikante Verbesserung der Spezifitaet der dynamischen kontrastmittelunterstuetzten MR-Mammographie erwarten. Das differentialdiagnostische Konzept beruht auf der pathologischen Hyperpermeabilitaet von Kapillaren in Karzinomen, die einen MMKM-Austritt in das Tumorinterstitium bedingt, waehrend die intakten Kapillaren benigner Tumoren nicht permeabel fuer MMKM sind. Diagnostische Moeglichkeiten und Grenzen des MMKM-Prototyps, Albumin-Gd-DTPA (92 kD), werden dargestellt und mit dem niedermolekularen Standard-Kontrastmittel Gd-DTPA (500 D) verglichen. Erste Erfahrungen mit neuen, fuer die klinische Anwendung optimierten MMKM-Praeparaten, wie das Kaskadenpolymer, Gd-DTPA-Polylysine und das MS-325 werden vorgestellt. Das Potential von Blood-pool-Eisenoxidpraeparaten, z.B. AMI-227, fuer die Bestimmung von

Determination of calcitonin; Bestimmung von Kalzitonin

Energy Technology Data Exchange (ETDEWEB)

Goerges, R. [Klinik fuer Nuklearmedizin, Klinikum Essen, Univ. Duisburg/Essen (Germany); Gemeinschaftspraxis fuer Nuklearmedizin, Duisburg (Germany)

2005-03-01

Calcitonin in serum is a comparatively highly sensitive, specific and reliable tumor marker of central relevance for the diagnosis and follow-up of medullary thyroidal C-cell carcinoma (MTC) and neoplastic C-cell hyperplasia (CCH). It is seen considerably less often in other tumor entities. For determination we recommend immunometric two-site assays of approximately 1-2 pg/ml sensitivity. Higher MTC specificity is achieved by assays focussing on a largely selective determination of monomeric calcitonin. If this is realized, basal calcitonin levels are already greatly relevant for MTC or CCH diagnosis. The diagnostic sensitivity and specificity of calcitonin determination may be further enhanced by means of pentagastrin test, but even then false positive results are clinically relevant especially in benign CCH and renal insufficiency. In family screening in case of MTC patients, moleculargenetic techniques have become the procedure of choice and have now largely replaced the pentagastrin test. Calcitonin screening in adenomatous goitre (struma nodosa) is making headway. Although this accounts for only 10% of thyroidal malignomas (which are in fact rare), and the recommended levels of intervention will result in many unnecessary surgical operations, early tumor staging definitely increases the chances for curative intervention. (orig.)

Electricity transmission. Transmission providers' duties to permit and possibilities to deny TPA to the network; Durchleitung von Strom. Pflichten und Verweigerungsmoeglichkeiten von Elektrizitaetsversorgungsunternehmen

Energy Technology Data Exchange (ETDEWEB)

Kasper, O.

2001-07-01

The author gives a full account of the new legal situation in the German electricity market and explains the recent changes induced by implementation of the legal framework of the European Union for building the internal electricity market, and by recent national legislation amending laws and regulations. The juridical changes and the new legal provisions and their effects in practice are explained in ten chapters. Some important keywords: the concept of third-party access (TPA) to electricity transmission networks - the IEM Directive of the EU - the reform of the German energy industry law - objectives and consequences of the reform - market deregulation - transmission pricing - competences of the national supervisory energy authority - national cartel law, market dominating position and abuse of a dominant market position - European cartel law. (orig./CB) [German] Der Autor gibt eine umfassende Darstellung der neuen Rechtslage im Strommarkt in Deutschland und erlaeutert die Veraenderungen, die sich aus den Vorgaben der Europaeischen Union zur Herstellung des Strom-Binnenmarkts und durch neue deutsche Gesetzgebung und Novellierung bestehender Regelungen ergaben. In zehn Kapiteln werden die neuen rechtlichen Bestimmungen und ihre Auswirkungen in der Praxis angesprochen. Einige wichtige Stichworte: Durchleitungsbegriff und Durchleitungsbedingungen - Binnenmarkt-Richtlinie Elektrizitaet - Neuregelung des deutschen Energiewirtschaftsrechts - Ziele und Folgen der Energierechtsreform - Deregulierung des Marktes - Bestimmung von Durchleitungsentgelten - Zustaendigkeit der nationalen Energieaufsichtsbehoerde - nationales Kartellrecht und kartellrechtlicher Missbrauchstatbestand - Europaeisches Kartellrecht. (orig./CB)

The plutonium fuel cycles

International Nuclear Information System (INIS)

Pigford, T.H.; Ang, K.P.

1975-01-01

The quantities of plutonium and other fuel actinides have been calculated for equilibrium fuel cycles for 1000-MW water reactors fueled with slightly enriched uranium, water reactors fueled with plutonium and natural uranium, fast-breder reactors, gas-cooled reactors fueled with thorium and highly enriched uranium, and gas-cooled reactors fueled with thorium, plutonium and recycled uranium. The radioactivity quantities of plutonium, americium and curium processed yearly in these fuel cycles are greatest for the water reactors fueled with natural uranium and recycled plutonium. The total amount of actinides processed is calculated for the predicted future growth of the U.S. nuclear power industry. For the same total installed nuclear power capacity, the introduction of the plutonium breeder has little effect upon the total amount of plutonium in this century. The estimated amount of plutonium in the low-level process wastes in the plutonium fuel cycles is comparable to the amount of plutonium in the high-level fission product wastes. The amount of plutonium processed in the nuclear fuel cycles can be considerably reduced by using gas-cooled reactors to consume plutonium produced in uranium-fueled water reactors. These, and other reactors dedicated for plutonium utilization, could be co-located with facilities for fuel reprocessing ad fuel fabrication to eliminate the off-site transport of separated plutonium. (author)

Neue biosensorische Prinzipien für die Hämoglobin-A1c Bestimmung

Science.gov (United States)

Stöllner, Daniela

2002-06-01

Hämoglobin-A1c (HbA1c) ist ein Hämoglobin (Hb)-Subtypus, der durch nicht-enzymatische Glykierung des N-terminalen Valinrestes der Hämoglobin-beta-Kette entsteht. Das gemessene Verhältnis von HbA1c zum Gesamt-Hämoglobin (5-20 % bei Diabetikern) repräsentiert den Mittelwert der Blutglucosekonzentration über einen zweimonatigen Zeitraum und stellt zur Beurteilung der diabetischen Stoffwechsellage eine Ergänzung zur Akutkontrolle der Glukosekonzentration dar. Ziel der vorliegenden Arbeit war es, einen amperometrischen Biosensor für die Bestimmung des medizinisch relevanten Parameters HbA1c zu entwickeln. Durch Selektion geeigneter Bioerkennungselemente und deren Immobilisierung unter Erhalt der Bindungsfunktion für die Zielmoleküle Hämoglobin bzw. HbA1c wurden spezifische, hochaffine und regenerationsstabile Sensoroberflächen geschaffen. Für die Entwicklung des HbA1c-Biosensors wurden zwei Konzepte - Enzymsensor und Immunosensor - miteinander verglichen. Die enzymatische Umsetzung von HbA1c erfolgte mit der Fructosylamin Oxidase (FAO) aus Pichia pastoris N 1-1 unter Freisetzung von H2O2, welches sowohl optisch über eine Indikatorreaktion als auch elektrochemisch nach Einschluss der FAO in PVA-SbQ und Fixierung des Immobilisats vor einer H2O2-Elektrode nachgewiesen wurde. Die Kalibration des Enzymsensors mit der HbA1c-Modellsubstanz Fructosyl-Valin ergab Nachweisgrenzen, die ausserhalb des physiologisch relevanten HbA1c-Konzentrationsbereich lagen. Aus der Umsetzung von glykierten Peptiden mit einer nicht HbA1c analogen Aminosäurensequenz, z.B. Fructosyl-Valin-Glycin wurde zudem eine geringe HbA1c-Spezifität abgeleitet. Für den Immunosensor wurden zwei heterogene Immunoassay-Formate unter Verwendung von hochaffinen und spezifischen Antikörpern in Kombination mit Glucose Oxidase (GOD) als Markerenzym zum Nachweis von HbA1c untersucht. Beim indirekt-kompetitiven Immunoassay wurde anstelle des kompletten HbA1c-Moleküls das glykierte Pentapeptid

Plutonium

International Nuclear Information System (INIS)

Anon.

1995-01-01

Plutonium, which was obtained and identified for the first time in 1941 by chemist Glenn Seaborg - through neutron irradiation of uranium 238 - is closely related to the history of nuclear energy. From the very beginning, because of the high radiotoxicity of plutonium, a tremendous amount of research work has been devoted to the study of the biological effects and the consequences on the environment. It can be said that plutonium is presently one of the elements, whose nuclear and physico-chemical characteristics are the best known. The first part of this issue is a survey of the knowledge acquired on the subject, which emphasizes the sanitary effects and transfer into the environment. Then the properties of plutonium related to energy generation are dealt with. Fissionable, like uranium 235, plutonium has proved a high-performance nuclear fuel. Originally used in breeder reactors, it is now being more and more widely recycled in light water reactors, in MOX fuel. Reprocessing, recycling and manufacturing of these new types of fuel, bound of become more and more widespread, are now part of a self-consistent series of operations, whose technical, economical, industrial and strategical aspects are reviewed. (author)

Learning more about plutonium

International Nuclear Information System (INIS)

2005-01-01

This document offers chemical, metallurgical and economical information on the plutonium, a hard white radioelement. It deals also on the plutonium formation in the earth, the plutonium use in the nuclear industry, the plutonium in the environment and the plutonium toxicity. (A.L.B.)

Physikochemische Untersuchung der Analyt – HKUST-1 Wechselwirkung unter Verwendung der inversen Gaschromatographie

OpenAIRE

Münch, Alexander

2013-01-01

Die vorliegende Arbeit hat neben der Untersuchung der Synthese über den Controlled SBU-Approach von HKUST-1, ein poröses Kupfertrimesat, die Abscheidung dieses Metal-Organic Frameworks in dünnen Quarzglaskapillaren mit einer Länge von 10 bis 30 m und Innendurchmessern zwischen 0,53 und 0,25 mm zum Thema. Diese Säulen werden zur gaschromatographischen Trennung wie auch zur Bestimmung physikochemischer Kenngrößen, die den Adsorptionsvorgang verschiedener Analyten auf der HKUST-1 Oberfläche besc...

Civil plutonium management

International Nuclear Information System (INIS)

Sicard, B.; Zaetta, A.

2004-01-01

During 1960 and 1970 the researches on the plutonium recycling in fast neutrons reactors were stimulated by the fear of uranium reserves diminishing. At the beginning of 1980, the plutonium mono-recycling for water cooled reactors is implementing. After 1990 the public opinion concerning the radioactive wastes management and the consequences of the disarmament agreements between Russia and United States, modified the context. This paper presents the today situation and technology associated to the different options and strategical solutions of the plutonium management: the plutonium use in the world, the neutronic characteristics, the plutonium effect on the reactors characteristics, the MOX behavior in the reactors, the MOX fabrication and treatment, the possible improvements to the plutonium use, the concepts performance in a nuclear park. (A.L.B.)

The plutonium society

International Nuclear Information System (INIS)

Mez, L.; Richter, M.

1981-01-01

The lectures of an institute are reported on, which took place between 25th and 27th January 1980 in Berlin. The subsequent public panel discussion with representations from the political parties is then documentated in a few press-reports. The themes of the 8 lectures are: views and facts on plutonium, plutonium as an energy resource, military aspects of the production of plutonium, economic aspects of the plutonium economy, the position of the trade unions on the industrial reconversion, the alleged inevitability of a plutonium society and the socio-political alternatives and perspectives of nuclear waste disposal. (UA) [de

What is plutonium stabilization, and what is safe storage of plutonium?

International Nuclear Information System (INIS)

Forsberg, C.W.

1995-01-01

The end of the cold war has resulted in the shutdown of nuclear weapons production and the start of dismantlement of significant numbers of nuclear weapons. This, in turn, is creating an inventory of plutonium requiring interim and long-term storage. A key question is, ''What is required for safe, multidecade, plutonium storage?'' The requirements for storage, in turn, define what is needed to stabilize the plutonium from its current condition into a form acceptable for interim and long-term storage. Storage requirements determine if research is required to (1) define required technical conditions for interim and long-term storage and (2) develop or improve current stabilization technologies. Storage requirements depend upon technical, policy, and economic factors. The technical issues are complicated by several factors. Plutonium in aerosol form is highly hazardous. Plutonium in water is hazardous. The plutonium inventory is in multiple chemical forms--some of which are chemically reactive. Also, some of the existing storage forms are clearly unsuitable for storage periods over a few years. Gas generation by plutonium compounds complicates storage: (1) all plutonium slowly decays creating gaseous helium and (2) the radiation from plutonium decay can initiate many chemical reactions-some of which generate significant quantities of gases. Gas generation can pressurize sealed storage packages. Last nuclear criticality must be avoided

Comparison of different methods of assessing the tar content of gases from wood gasification; Vergleich verschiedener Methoden zur Bestimmung des Teergehalts in Gasen aus der Holzvergasung

Energy Technology Data Exchange (ETDEWEB)

Moersch, O; Spliethoff, H; Hein, K R.G. [Stuttgart Univ. (Germany). Inst. fuer Verfahrenstechnik und Dampfkesselwesen

1998-09-01

The authors present a method developed at the Institute of Chemical Engineering and Steam Boiler Technology (IVD) of Stuttgart University for quasi-continuous online measurement of tar concentrations in gases from biomass gasification. The method is compared with other methods in terms of time requirements, accuracy, and cost: Gravimetry, wet chemical analysis, solid phase amino-adsorption (SPA), and online process gas chromatography. The measurements were carried out on the fluidized-bed combustion system of the IVD. Wood was gasified at 800 degrees centigrade with a fuel/air ratio of 0.25. The measured tar concentrations differed widely, i.e. between 0.8 and 6.8 g per cubic metre. (orig.) [Deutsch] In dieser Arbeit wird ein am Institut fuer Verfahrenstechnik und Dampfkesselwesen (IVD) entwickeltes Verfahren zur quasikontinuierlichen Online-Messung des Teergehalts im Gas aus der Biomassevergasung vorgestellt und mit anderen Methoden aus der Literatur im Hinblick auf Zeitaufwand, Genauigkeit und Kosten verglichen. Untersucht wurden dabei eine gravimetrische Methode, die nasschemische Bestimmung, das Solid-Phase-Amino Adsorptionsverfahren (SPA), sowie die Online Analyse mittels Prozess-Gaschromatograph. Die Messungen wurden an der Wirbelschichtvergasungsanlage des IVD durchgefuehrt. Vergast wurde Holz bei 800 C und einer Luftzahl von 0.25. Der mit den verschiedenen Verfahren ermittelte Teergehalt unterscheidet sich zum Teil erheblich. Es ergaben sich Werte zwischen 0.8 und 6.8 g/m{sup 3}. (orig.)

Investigations of the applicability of a model-supported friction coefficient prediction model in a moving vehicle; Untersuchungen zum Einsatz eines modellunterstuetzten Reibwertvorhersagemodells im fahrenden Fahrzeug

Energy Technology Data Exchange (ETDEWEB)

Klempau, F. [TU Darmstadt, Fachgebiet Fahrzeugtechnik (Germany)

2000-07-01

In recent years driving-stability- and driver-assistance systems have become more and more common in new cars. Along with this development there is a growing demand for a system predicting the actual friction potential in the tyre contact patch. Within the European research project VERT (VEhicle Road Tyre Interaction) a big number of friction measurements were carried out to define the main influencing parameters of the tyre-road-friction-process. With the help of empirical and physical models it was possible to describe the effect of these main influencing parameters on friction values. The aim of the research work in this project is to implement these models in driving simulations as well as to consider the feasibility to implement them into real cars. This paper presents the possibilities developing a friction prediction model for implementation in a moving vehicle. (orig.) [German] U.a. wegen der zunehmenden Verbreitung von Fahrdynamik- und Fahrerassistenz - Systemen wird der Wunsch nach Kenntnis des Reibwertpotentials zwischen Reifen und Fahrbahn immer dringender. Zur Bestimmung der Einfluesse auf den Reibwert wurden im Rahmen des europaeischen Forschungsprojekts VERT, dessen Partner fzd ist, eine Vielzahl von Messungen durchgefuehrt. Ihre Auswertung ermoeglichte die Bestimmung von Haupteinflussgroessen und die Beschreibung ihrer Auswirkungen auf den Reibwert mittels empirischer und physikalischer (orig.)

Plutonium solubilities

International Nuclear Information System (INIS)

Puigdomnech, I.; Bruno, J.

1991-02-01

Thermochemical data has been selected for plutonium oxide, hydroxide, carbonate and phosphate equilibria. Equilibrium constants have been evaluated in the temperature range 0 to 300 degrees C at a pressure of 1 bar to T≤100 degrees C and at the steam saturated pressure at higher temperatures. Measured solubilities of plutonium that are reported in the literature for laboratory experiments have been collected. Solubility data on oxides, hydroxides, carbonates and phosphates have been selected. No solubility data were found at temperatures higher than 60 degrees C. The literature solubility data have been compared with plutonium solubilities calculated with the EQ3/6 geochemical modelling programs, using the selected thermodynamic data for plutonium. (authors)

Plutonium in uranium deposits

International Nuclear Information System (INIS)

Curtis, D.; Fabryka-Martin, J.; Aguilar, R.; Attrep, M. Jr.; Roensch, F.

1992-01-01

Plutonium-239 (t 1/2 , 24,100 yr) is one of the most persistent radioactive constituents of high-level wastes from nuclear fission power reactors. Effective containment of such a long-lived constituent will rely heavily upon its containment by the geologic environment of a repository. Uranium ore deposits offer a means to evaluate the geochemical properties of plutonium under natural conditions. In this paper, analyses of natural plutonium in several ores are compared to calculated plutonium production rates in order to evaluate the degree of retention of plutonium by the ore. The authors find that current methods for estimating production rates are neither sufficiently accurate nor precise to provide unambiguous measures of plutonium retention. However, alternative methods for evaluating plutonium mobility are being investigated, including its measurement in natural ground waters. Preliminary results are reported and establish the foundation for a comprehensive characterization of plutonium geochemistry in other natural environments

Conversion of metal plutonium to plutonium dioxide by pyrochemical method

Energy Technology Data Exchange (ETDEWEB)

Panov, A.V.; Subbotin, V.G. [Russian Federal Nuclear Center, ALL-Russian Science and Research Institute of Technical Physics, Snezhinsk (Russian Federation); Mashirev, V.P. [ALL-Russian Science and Research Institute of Chemical Technology, Moscow (Russian Federation)

2000-07-01

Report contains experimental results on metal plutonium of weapon origin samples conversion to plutonium dioxide by pyrochemical method. Circuits of processes are described. Their advantages and shortcomings are shown. Parameters of plutonium dioxide powders (phase and fraction compositions, poured density) manufactured by pyrochemical method in RFNC-VNIITF are shown as well. (authors)

The use of plutonium

International Nuclear Information System (INIS)

Marshall, W.

1980-01-01

The use of plutonium as a vital energy source producing maximum economic benefit with minimum proliferation risks is discussed. Having considered the production of plutonium, several possible plutonium fuel cycle options are identified and the economic value to be attached to plutonium for each examined. It is shown how the use of plutonium in fast reactors gives an opportunity for a non-proliferation policy not available when plutonium is used only in thermal reactors. From the technical considerations reviewed concerning plutonium and fast reactors it is shown that an economic regime involving international trade in spent thermal reactor fuel is possible which benefits equally those countries with fast reactors and those without and also assists in avoiding the proliferation of nuclear weapons. (U.K.)

Properties of plutonium

International Nuclear Information System (INIS)

Ahn, Jin Su; Yoon, Hwan Ki; Min, Kyung Sik; Kim, Hyun Tae; Ahn, Jong Sung; Kwag, Eon Ho; Ryu, Keon Joong

1996-03-01

Plutonium has unique chemical and physical properties. Its uniqueness in use has led to rare publications, in Korea. This report covers physical aspects of phase change of metal plutonium, mechanical properties, thermal conductivity, etc, chemical aspects of corrosion, oxidation, how to produce plutonium from spent fuels by describing various chemical treatment methods, which are currently used and were used in the past. It also contains characteristics of the purex reprocessing process which is the most widely used nowadays. And show processes to purify and metalize from recovered plutonium solution. Detection and analysis methods are introduced with key pints for handling, critical safety, toxicity, and effects on peoples. This report gives not only a general idea on what plutonium is, rather than deep technical description, but also basic knowledge on plutonium production and safeguards diversion from the view point of nonproliferation. 18 refs. (Author) .new

Properties of plutonium

Energy Technology Data Exchange (ETDEWEB)

Ahn, Jin Su; Yoon, Hwan Ki; Min, Kyung Sik; Kim, Hyun Tae; Ahn, Jong Sung; Kwag, Eon Ho; Ryu, Keon Joong [Korea Atomic Energy Research Institute, Daeduk (Korea, Republic of)

1996-03-01

Plutonium has unique chemical and physical properties. Its uniqueness in use has led to rare publications, in Korea. This report covers physical aspects of phase change of metal plutonium, mechanical properties, thermal conductivity, etc, chemical aspects of corrosion, oxidation, how to produce plutonium from spent fuels by describing various chemical treatment methods, which are currently used and were used in the past. It also contains characteristics of the purex reprocessing process which is the most widely used nowadays. And show processes to purify and metalize from recovered plutonium solution. Detection and analysis methods are introduced with key pints for handling, critical safety, toxicity, and effects on peoples. This report gives not only a general idea on what plutonium is, rather than deep technical description, but also basic knowledge on plutonium production and safeguards diversion from the view point of nonproliferation. 18 refs. (Author) .new.

Plutonium-238 and plutonium-239 metabolism in dairy cows following ingestion of mixed oxides

International Nuclear Information System (INIS)

Patzer, R.G.; Mullen, A.A.; Sutton, W.W.; Potter, G.D.; Mosley, R.E.; Efurd, D.W.; Stalnaker, N.D.

1985-01-01

Dairy cows were given oral dosage of plutonium-238 and plutonium-239 dioxide particles in a study to determine the relative gastrointestinal absorption and tissue distribution of the nuclides. Two cows were given particles in which the two isotopes were homogeneously mixed within the particles. A third cow was given two batches of particles which contained either plutonium-238 or plutonium-239. Results indicate that, when the two isotopes of plutonium are homogeneous within the particles, there is no difference between plutonium-238 and plutonium-239 in the relative gastrointestinal absorption and tissue distribution

High-temperature enthalpies of plutonium monocarbide and plutonium sesquicarbide

International Nuclear Information System (INIS)

Oetting, F.L.

1979-01-01

The high-temperature enthalpies of plutonium monocarbide and plutonium sesquicarbide have been determined with a copper-block calorimeter of the isoperibol type. The experimental enthalpy data, which was measured relative to 298 K, covered the temperature range from 400 to 1500 K. The calculation of the temperature rise of the calorimeter takes into account the added heat evolution from the radioactive decay of the plutonium samples. These enthalpy results, combined with the heat capacity and entropy of the respective carbide at 298 K available from the literature, has made it possible to generate tables of thermodynamic functions for the plutonium carbides. The behavior of the heat capacity of both of the plutonium carbides, i.e., a relatively steep increase in the heat capacity as the temperature increases, may be attributed to a premelting effect with the formation of vacancies within the crystal lattice although a theoretical treatment of this phenomenon is not given

Plutonium

International Nuclear Information System (INIS)

Koelzer, W.

1989-03-01

This report contains with regard to 'plutonium' statements on chemistry, occurrence and reactions in the environment, handling procedures in the nuclear fuel cycle, radiation protection methods, biokinetics, toxicology and medical treatment to make available reliable data for the public discussion on plutonium especially its use in nuclear power plants and its radiological assessment. (orig.) [de

Plutonium

International Nuclear Information System (INIS)

Mueller-Christiansen, K.; Wollesen, M.

1979-01-01

As emotions and fear of plutonium are neither useful for the non-professionals nor for the political decision makers and the advantages and disadvantages of plutonium can only put against each other under difficulties, the paper wants to present the most essential scientific data of plutonium in a generally understandable way. Each of the individual sections is concluded and they try to give an answer to the most discussed questions. In order to make understanding easier, the scientific facts are only brought at points where it cannot be done without for the correctness of the presentation. Many details were left out knowingly. On the other hand, important details are dealt with several times if it seems necessary for making the presentation correct. The graphical presentations and the figures in many cases contain more than said in the text. They give the interested reader hints to scientific-technical coherences. The total material is to enable the reader to form his own opinion on plutonium problems which are being discussed in public. (orig./HP) [de

PRODUCTION OF PLUTONIUM METAL

Science.gov (United States)

Lyon, W.L.; Moore, R.H.

1961-01-17

A process is given for producing plutonium metal by the reduction of plutonium chloride, dissolved in alkali metal chloride plus or minus aluminum chloride, with magnesium or a magnesium-aluminum alloy at between 700 and 800 deg C and separating the plutonium or plutonium-aluminum alloy formed from the salt.

Plutonium storage phenomenology

International Nuclear Information System (INIS)

Szempruch, R.

1995-12-01

Plutonium has been produced, handled, and stored at Department of Energy (DOE) facilities since the 1940s. Many changes have occurred during the last 40 years in the sources, production demands, and end uses of plutonium. These have resulted in corresponding changes in the isotopic composition as well as the chemical and physical forms of the processed and stored plutonium. Thousands of ordinary food pack tin cans have been used successfully for many years to handle and store plutonium. Other containers have been used with equal success. This paper addressees the exceptions to this satisfactory experience. To aid in understanding the challenges of handling plutonium for storage or immobilization the lessons learned from past storage experience and the necessary countermeasures to improve storage performance are discussed

Plutonium controversy

International Nuclear Information System (INIS)

Richmond, C.R.

1980-01-01

The toxicity of plutonium is discussed, particularly in relation to controversies surrounding the setting of radiation protection standards. The sources, amounts of, and exposure pathways of plutonium are given and the public risk estimated

Perspective on plutonium

International Nuclear Information System (INIS)

Sun, L.S.

1993-01-01

This paper is intended as a brief overview on the element plutonium. Plutonium is the first primarily man-made element to play a significant role not only in technological development, but also in the economic growth of many countries. The importance of plutonium centers around its enormous energy making it ideal for wide-scale use in reactors, while the nuclear industry continues to work toward improving safety and efficiency of plutonium as a reactor fuel politicians and the public still debate over the safety and benefits of nuclear power. (30 refs.)

Plutonium controversy

Energy Technology Data Exchange (ETDEWEB)

Richmond, C.R.

1980-01-01

The toxicity of plutonium is discussed, particularly in relation to controversies surrounding the setting of radiation protection standards. The sources, amounts of, and exposure pathways of plutonium are given and the public risk estimated. (ACR)

Plutonium, nuclear fuel; Le plutonium, combustible nucleaire

Energy Technology Data Exchange (ETDEWEB)

Grison, E [Commissariat a l' Energie Atomique, Fontenay aux Roses (France). Centre d' Etudes Nucleaires, Saclay

1960-07-01

A review of the physical properties of metallic plutonium, its preparation, and the alloys which it forms with the main nuclear metals. Appreciation of its future as a nuclear fuel. (author) [French] Apercu sur les proprietes physiques du plutonium metallique, sa preparation, ses alliages avec les principaux metaux nucleaires. Consideration sur son avenir en tant que combustible nucleaire. (auteur)

Fused salt processing of impure plutonium dioxide to high-purity plutonium metal

International Nuclear Information System (INIS)

Mullins, L.J.; Christensen, D.C.; Babcock, B.R.

1982-01-01

A process for converting impure plutonium dioxide (approx. 96% pure) to high-purity plutonium metal (>99.9%) was developed. The process consists of reducing the oxide to an impure plutonium metal intermediate with calcium metal in molten calcium chloride. The impure intermediate metal is cast into an anode and electrorefined to produce high-purity plutonium metal. The oxide reduction step is being done now on a 0.6-kg scale with the resulting yield being >99.5%. The electrorefining is being done on a 4.0-kg scale with the resulting yield being 80 to 85%. The purity of the product, which averages 99.98%, is essentially insensitive to the purity of the feed metal. The yield, however, is directly dependent on the chemical composition of the feed. To date, approximately 250 kg of impure oxide has been converted to pure metal by this processing sequence. The availability of impure plutonium dioxide, together with the need for pure plutonium metal, makes this sequence a valuable plutonium processing tool

Standard test method for plutonium assay by plutonium (III) diode array spectrophotometry

CERN Document Server

American Society for Testing and Materials. Philadelphia

2002-01-01

1.1 This test method describes the determination of total plutonium as plutonium(III) in nitrate and chloride solutions. The technique is applicable to solutions of plutonium dioxide powders and pellets (Test Methods C 697), nuclear grade mixed oxides (Test Methods C 698), plutonium metal (Test Methods C 758), and plutonium nitrate solutions (Test Methods C 759). Solid samples are dissolved using the appropriate dissolution techniques described in Practice C 1168. The use of this technique for other plutonium-bearing materials has been reported (1-5), but final determination of applicability must be made by the user. The applicable concentration range for plutonium sample solutions is 10–200 g Pu/L. 1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropria...

Plutonium storage criteria

Energy Technology Data Exchange (ETDEWEB)

Chung, D. [Scientech, Inc., Germantown, MD (United States); Ascanio, X. [Dept. of Energy, Germantown, MD (United States)

1996-05-01

The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less than 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.

Bromide as a tracer for studying water movement and nitrate displacement in soils: comparison with stable isotope tracers; Bromid als Tracer zur Untersuchung der Wasserbewegung und der Nitratverlagerung in Boeden: Vergleich mit stabilisotopen Tracern

Energy Technology Data Exchange (ETDEWEB)

Russow, R.; Knappe, S. [UFZ - Umweltforschungszentrum Leipzig-Halle GmbH, Bad Lauchstaedt (Germany). Sektion Bodenforschung

1999-02-01

Tracers are an ideal means of studying water movement and associated nitrate displacement. Often bromide is preferred as a tracer because it is considered a representative tracer for water and because, being a conservative tracer (i.e. not involved in chemical and biological soil processes), it can be used for studying anion transport in soils. Moreover, it is less expensive and easier to measure than the stable isotopes deuterium and {sup 15}N. Its great advantage over radioactive tracers (e.g. tritium), which outweighs their extreme sensitivity and ease of measurement and which it has in common with stable isotopes, is that it does not require radiation protection measures. However, there are also constraints on the use of bromide as a tracer in soil/water/plant systems. Our own studies on different soils using D{sub 2}O, bromide and [{sup 15}N]-nitrate in lysimeters suggest that the above assumptions on bromide tracers need not always be valid under conditions as they prevail in biologically active soils. As the present paper shows, these studies permit a good assessment of the possibilities and limits to these tracers. [Deutsch] Fuer die Untersuchung der Wasserbewegung sowie der daran gekoppelten Nitrat-Verlagerung ist der Einsatz von Tracern das Mittel der Wahl. Dabei wird Bromid als Tracer haeufig bevorzugt, da es allgemein als ein repraesentativer Tracer fuer Wasser und als konservativer Tracer (nicht involviert in chemische und biologische Bodenprozesse) zur Untersuchung des Anionentransportes in Boeden angesehen wird und es gegenueber den stabilen Isotopen Deuterium und {sup 15}N billiger und einfacher zu bestimmen ist. Gegenueber den radioaktiven Tracern (z.B. Tritium), die zwar sehr empfindlich und einfach messbar sind, besteht der grosse Vorteil, dass, wie bei den stabilen Isotopen, keine Strahlenschutzmassnahmen ergriffen werden muessen. Es gibt jedoch auch einschraenkende Hinweise fuer die Verwendung von Bromid als Tracer im System Boden

Toxicology of plutonium

International Nuclear Information System (INIS)

Bair, W.J.

1974-01-01

Data are reviewed from studies on the toxicity of Pu in experimental animals. Of the several plutonium isotopes, only 238 Pu and 239 Pu have been studied well. Sufficient results have been obtained to show that the behavior of 238 Pu in biological systems and the resulting biological effects cannot be precisely predicted from studies of 239 Pu. This probably applies also to other radiologically important plutonium isotopes which have half-lives ranging from 45 days to 10 7 years and decay by β-emission, electron capture, and spontaneous fission, as well as by emission of α-particles. All the biological effects of plutonium described in this review are attributed to alpha-particle radiation emitted by the plutonium. However, since plutonium is a chemically active heavy metal, one cannot ignore the possibility of chemical toxicity of the low-specific-activity isotopes, 239 Pu, 242 Pu, and 244 Pu. The preponderance of our knowledge of plutonium toxicology has come from short-term studies of relatively high dosage levels in several animal species. The consequences of high-level internal exposures can be predicted with confidence in experimental animals and probably also in man. However, considering the care with which plutonium is handled in the nuclear industry, a high-level contamination event is unlikely. Considerably less is known about the long-term effects of low levels of contamination. (250 references) (U.S.)

Dynamics of very small soot particles during soot burnout in diesel engines; Dynamik kleinster Russteilchen waehrend der Russausbrandphase im Dieselmotor

Energy Technology Data Exchange (ETDEWEB)

Bockhorn, H. [Karlsruhe Univ. (T.H.) (Germany). Inst. fuer Chemische Technik; Peters, N. [RWTH Aachen (DE). Institut fuer Technische Mechanik (ITM); Pittermann, R. [WTZ fuer Motoren- und Maschinenforschung Rosslau gGmbH (Germany); Hentschel, J.; Weber, J.

2003-07-01

The investigations used advanced laser-optical methods for measuring soot particle size distributions, temporally and spectrally resolved measurements of engine combustion, measurements of composition and size distribution of particles in exhaust, and further development and validation of reaction-kinetic models. In all, it can be stated that mixing will affect not only soot particle formation but also soot particle emissions. Mixing can be influenced by using a fuel-water emulsion and by CR injection. Experiments and models both showed the advantageous effects of water added to the diesel fuels and of CR injection. The higher OH radical concentrations in the later combustion stages also serve to ensure faster oxidation of soot. (orig.) [German] Ziel des Projektes war es, Informationen ueber die Bildung und Oxidation von Russ sowie die Teilchendynamik der Russteilchen waehrend der Ausbrandphase zu erhalten. Dies wurde erreicht durch die Weiterentwicklung laseroptischer Methoden zur Bestimmung der Groessenverteilung von Russpartikeln, durch zeit- und spektral aufgeloeste Erfassung der motorischen Verbrennung, durch die Bestimmung von Zusammensetzung und Groessenverteilung von Partikeln im Abgas sowie durch die Weiterentwicklung und Validierung von reaktionskinetischen Modellen. Zusammenfassend laesst sich sagen, dass sich die Gemischbildung im Dieselmotor nicht nur auf die Bildung der Russpartikel sondern auch auf die Russpartikelemission auswirkt. Die Verwendung einer Kraftstoff-Wasser-Emulsion und die Common-Rail-Einspritzung stellen zwei Verfahren zur Beeinflussung der Gemischbildung dar. Sowohl die experimentellen Untersuchungen als auch die Modellierung zeigen den die Gemischbildung foerdernden Einfluss des Zusatzes von Wasser zum Dieselbrennstoff. Ein erhoehter Anteil an vorgemischter Verbrennung, wie er auch durch die Verwendung hoher Einspritzdruecke bei der Common-Rail-Einspritzung erreicht werden kann, verringert die waehrend der Verbrennung entstehende

Cycle downstream: the plutonium question; Aval du cycle la question du plutonium

Energy Technology Data Exchange (ETDEWEB)

Zask, G [Electricite de France, EDF/DAC, 75 - Paris (France); Rome, M [Electricite de France, EDF, Service Etudes et Projets Thermiques et Nucleaires, 92 - Courbevoie (France); Delpech, M [CEA Cadarache, Dept. d' Etudes des Reacteurs/SPRC, 13 - Saint-Paul-lez-Durance (France); and others

1998-06-29

This day, organized by the SFEN, took place at Paris the 4 june 1998. Nine papers were presented. They take stock on the plutonium physics and its utilization as a nuclear fuel. This day tried to bring information to answer the following questions: do people have to keep the plutonium in the UOX fuel or in the MOX fuel in order to use it for future fast reactors? Do people have to continue obstinately the plutonium reprocessing in the MOX for the PWR type reactors? Will it be realized a underground disposal? Can it be technically developed plutonium incinerators and is it economically interesting? The plutonium physics, the experimental programs and the possible solutions are presented. (A.L.B.)

Probing phonons in plutonium

International Nuclear Information System (INIS)

Wong, Joe; Krisch, M.; Farber, D.; Occelli, F.; Schwartz, A.; Chiang, T.C.; Wall, M.; Boro, C.; Xu, Ruqing

2010-01-01

) capability on ID28. The complete PDCs for an fcc Pu-0.6 wt% Ga alloy are plotted in Figure 2, and represent the first full set of phonon dispersions ever determined for any Pu-bearing materials. The solid curves (red) are calculated using a standard Born-von Karman (B-vK) force constant model. An adequate fit to the experimental data is obtained if interactions up to the fourth-nearest neighbours are included. The dashed curves (blue) are recent dynamical mean field theory (DMFT) results by Dai et al. The elastic moduli calculated from the slopes of the experimental phonon dispersion curves near the Λ point are: C 11 = 35.3 ± 1.4 GPa, C 12 = 25.5 ± 1.5 GPa and C 44 = 30.53 ± 1.1 GPa. These values are in excellent agreement with those of the only other measurement on a similar alloy (1 wt % Ga) using ultrasonic techniques as well as with those recently calculated from a combined DMFT and linear response theory for pure (delta)-Pu. Several unusual features, including a large elastic anisotropy, a small shear elastic modulus C(prime), a Kohn-like anomaly in the T 1 [011] branch, and a pronounced softening of the [111] transverse modes are found. These features can be related to the phase transitions of plutonium and to strong coupling between the lattice structure and the 5f valence instabilities. The HRIXS results also provide a critical test for theoretical treatments of highly correlated 5f electron systems as exemplified by recent dynamical mean field theory (DMFT) calculations for (delta)-plutonium. The experimental-theoretical agreements shown in Figure 2 in terms of a low shear elastic modulus C(prime), a Kohn-like anomaly in the T 1 [011] branch, and a large softening of the T[111] modes give credence to the DMFT approach for the theoretical treatment of 5f electron systems of which (delta)-Pu is a classic example. However, quantitative differences remain. These are the position of the Kohn anomaly along the T 1 [011] branch, the energy maximum of the T[111] mode s

Kontinuierliche Wanddickenbestimmung und Visualisierung des linken Herzventrikels

Science.gov (United States)

Dornheim, Lars; Hahn, Peter; Oeltze, Steffen; Preim, Bernhard; Tönnies, Klaus D.

Zur Bestimmung von Defekten in der Herztätigkeit kann die Veränderung der Wanddicke des linken Ventrikels in zeitlichen MRTAufnahmesequenzen gemessen werden. Derzeit werden für diese Bestimmung im allgemeinen nur die aufwändig manuell erstellte Segmentierungen der Endsystole und Enddiastole benutzt. Wir stellen ein bis auf die Startpunktinitialisierung automatisches Verfahren zur Bestimmung der Wanddicke des linken Ventrikels und ihrer Veränderung vor, das auf einer vollständigen Segmentierung der Herzwand in allen Zeitschritten durch ein dynamisches dreidimensionales Formmodell (Stabiles Feder-Masse-Modell) basiert. Dieses Modell nutzt bei der Segmentierung neben der Grauwertinformation eines Zeitschrittes auch die Segmentierungen der anderen Zeitschritte und ist so aufgebaut, dass die Wanddicken direkt gemessen und visualisiert werden können. Auf diese Weise werden die lokalen Wanddickenextrema über den gesamten Aufnahmezeitraum detektiert, auch wenn sie nicht in die Endsystole bzw. -diastole fallen. Das Verfahren wurde auf sechs 4D-Kardio-MRT-Datensätzen evaluiert und stellte sich als sehr robust bzgl. der einzig nötigen Interaktion heraus.

The handling of plutonium hexafluoride (1962); Manipulation de l'hexafluorure de plutonium (1962)

Energy Technology Data Exchange (ETDEWEB)

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

1961-11-15

The major problem posed in this work is the instability of plutonium hexafluoride. The influence of various factors on the decomposition of the fluoride has been studied: physical aspect of the walls, nature of the metal and its pretreatment, influence of the temperature. A means of detecting plutonium-239 in a metallic apparatus by {gamma}-ray counting has been developed; the sensitivity is of the order of half a milligram, but the precision is very low (about 50 per cent). Yields of over 95 per cent have been obtained for the transfer of plutonium during the preparation and sublimation of the hexafluoride. This study confirms the possibility of using plutonium hexafluoride for the extraction of plutonium from irradiated fuel elements by a dry method. (author) [French] Le probleme majeur de cette etude a ete l'instabilite de l'hexafluorure de plutonium. Nous avons etudie l'influence de divers facteurs sur la decomposition de l'hexafluorure: aspect physique des parois, nature du metal et de son pretraitement, influence de la temperature. Nous avons mis au point un mode de detection du plutonium-239 dans un appareillage metallique par comptage du rayonnement {gamma}; la sensibilite est de l'ordre du demi-milligramme, mais la precision est tres faible (50 pour cent environ). Nous avons obtenu des rendements depassant 95 pour cent dans le transfert du plutonium au cours de la fabrication et de la sublimation de l'hexafluorure. Cette etude confirme la possibilite d'utiliser l'hexafluorure de plutonium dans l'extraction du plutonium des combustibles irradies par voie seche. (auteur)

Plutonium re-cycle in HTR

Energy Technology Data Exchange (ETDEWEB)

Desoisa, J. A.

1974-03-15

The study of plutonium cycles in HTRs using reprocessed plutonium from Magnox and AGR fuel cycles has shown that full core plutonium/uranium loadings are in general not feasible, burn-up is limited due the need for lower loadings of plutonium to meet reload core reactivity limits, on-line refueling is not practicable due to the need for higher burnable poison loadings, and low conversion rates in the plutonium-uranium cycles cannot be mitigated by axial loading schemes so that fissile make-up is needed if HTR plutonium recycle is desired.

PLUTONIUM-ZIRCONIUM ALLOYS

Science.gov (United States)

Schonfeld, F.W.; Waber, J.T.

1960-08-30

A series of nuclear reactor fuel alloys consisting of from about 5 to about 50 at.% zirconium (or higher zirconium alloys such as Zircaloy), balance plutonium, and having the structural composition of a plutonium are described. Zirconium is a satisfactory diluent because it alloys readily with plutonium and has desirable nuclear properties. Additional advantages are corrosion resistance, excellent fabrication propenties, an isotropie structure, and initial softness.

Optimization and plutonium equilibrium

International Nuclear Information System (INIS)

Silver, G.L.

1976-01-01

The sequential simplex method has been used to estimate the extent of disproportionation of tetravalent plutonium in dilute acid. A method for simulating potentiometric titrations is proposed, and this method suggests that the stoichiometric end point and the inflection point may not always correspond in the potentiometric titration of plutonium. A possible characteristic equation for the nitrite-plutonium reaction is illustrated, and the method of proportional equations is extended to the iron-plutonium reaction

Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options

International Nuclear Information System (INIS)

Brownson, D.A.; Hanson, D.J.; Blackman, H.S.

1993-06-01

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with plutonium-based fuel. Of these four options, the Advanced Light Water Reactor and the Modular High Temperature Gas-Cooled Reactor do not propose reprocessing of their irradiated fuel. Time constraints and lack of detailed information did not allow for any further ratings among these four options. The INEL recommends these four options be investigated further to determine the optimum reactor design for plutonium disposition

Weapons-grade plutonium dispositioning. Volume 2: Comparison of plutonium disposition options

Energy Technology Data Exchange (ETDEWEB)

Brownson, D.A.; Hanson, D.J.; Blackman, H.S. [and others

1993-06-01

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate disposition options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) offered to assist the NAS in this evaluation by investigating the technical aspects of the disposition options and their capability for achieving plutonium annihilation levels greater than 90%. This report was prepared for the NAS to document the gathered information and results from the requested option evaluations. Evaluations were performed for 12 plutonium disposition options involving five reactor and one accelerator-based systems. Each option was evaluated in four technical areas: (1) fuel status, (2) reactor or accelerator-based system status, (3) waste-processing status, and (4) waste disposal status. Based on these evaluations, each concept was rated on its operational capability and time to deployment. A third rating category of option costs could not be performed because of the unavailability of adequate information from the concept sponsors. The four options achieving the highest rating, in alphabetical order, are the Advanced Light Water Reactor with plutonium-based ternary fuel, the Advanced Liquid Metal Reactor with plutonium-based fuel, the Advanced Liquid Metal Reactor with uranium-plutonium-based fuel, and the Modular High Temperature Gas-Cooled Reactor with plutonium-based fuel. Of these four options, the Advanced Light Water Reactor and the Modular High Temperature Gas-Cooled Reactor do not propose reprocessing of their irradiated fuel. Time constraints and lack of detailed information did not allow for any further ratings among these four options. The INEL recommends these four options be investigated further to determine the optimum reactor design for plutonium disposition.

Assesment of Plutonium 238 and Plutonium 239+240 in soils of different agricultural regions of Guatemala

International Nuclear Information System (INIS)

Gutierrez Martinez, E.A.

1998-02-01

In this report an assesment and measurement of PLUTONIUM 238, PLUTONIUM 239, and PLUTONIUM 240 are made. Samples of cultivated soils in 15 provinces of Guatemala were taken. To separate plutonium isotopes a radiochemical method was made using extraction, precipitation and ionic interchange. By electrodeposition the plutonium was measured using an alpha spectroscopy by PIPS method. The radioactivity ranges from 2.84 mBq/Kg to 36.38 mBq/Kg for plutonium 238, and 8.46 mBq/Kg to 26.61 mBq/Kg for plutonium 239+240

Total emissivity and spectral emissivity of high-temperature materials; Gesamtemissionsgrad und spektraler Emissionsgrad von Hochtemperaturmaterialien

Energy Technology Data Exchange (ETDEWEB)

Neuer, G.; Pohlmann, P.; Schreiber, E.

1998-05-01

A new emissivity measurement device with inductive sample heating is described. The disc shaped samples can be measured between 800 C and 2000 C in vacuum or in each available gas atmosphere. Two kinds of surface temperature measurement methods are described, one by measuring in a blackbody hole and one by measuring at the surface without additional measures to correct emissivity. Total normal and spectral emissivity at wavelengths between 0,5 {mu}m and 8,3 {mu}m of various high temperature materials like platinum and Pt-Rh-alloys, siliconcarbide and molybdenum disilicide have been measured. From the investigated materials a few have been selected as reference samples for comparative emissivity measurements fullfilling the requirement of stability on air up to 400 C to 1000 C in order to ensure reproducibility of the results at different measurement conditions in air and in vacuum. (orig.) [Deutsch] Der Aufbau einer neuen Messapparatur fuer Emissionsgradmessungen bei Temperaturen zwischen 1000 C und 2000 C wird beschrieben. Die scheibenfoermigen Proben werden induktiv beheizt, und die Messungen koennen entweder in Vakuum oder einer beliebigen Gasatmosphaere durchgefuehrt werden. Es werden zwei verschiedene Verfahren zur Bestimmung der Oberflaechentemperatur bechrieben, wobei entweder in einer oder direkt an der Oberflaeche ohne zusaetzliche Massnahmen zur Emissionsgradkorrektur gemessen wird. An verschiedenen Hochtemperaturwerkstoffen wie Platin und Platin-Rhodium-Legierungen, Siliziumkarbid mit unterschiedlichen Herstellungsarten und Molybdaen-Disilizid wurden der Gesamtemissionsgrad und der spektrale Emissionsgrad bei Wellenlaengen von 0,5 {mu}m bis 8,3 {mu}m senkrecht zur Oberflaeche gemessen. Aus den untersuchten Materialien wurden solche als Referenzmaterialien fuer vergleichende Emissionsgradmessungen ausgewaehlt, die sowohl im Vakuum als auch in Luft und bei Temperaturen von 1400 C bis 1600 C unter verschiedenen Messbedingungen reproduzierbare Ergebnisse

Plutonium roundtable discussion

International Nuclear Information System (INIS)

Penneman, R.A.

1982-01-01

The roundtable discussion began with remarks by the chairman who pointed out the complicated nature of plutonium chemistry. Judging from the papers presented at this symposium, he noticed a pattern which indicated to him the result of diminished funding for investigation of basic plutonium chemistry and funding focused on certain problem areas. Dr. G.L. silver pointed to plutonium chemists' erroneous use of a simplified summary equation involving the disproportionation of Pu(EV) and their each of appreciation of alpha coefficients. To his appreciation of alpha coefficients. To his charges, Dr. J.T. Bell spoke in defense of the chemists. This discussion was followed by W.W. Schulz's comments on the need for experimental work to determine solubility data for plutonium in its various oxidation states under geologic repository conditions. Discussion then turned to plutonium pyrachemical process with Dana C. Christensen as the main speaker. This paper presents edited versions of participants' written version

Investigation of plutonium (4) hydroxoformates

International Nuclear Information System (INIS)

Andryushin, V.G.; Belov, V.A.; Galaktionov, S.V.; Kozhevnikov, P.B.; Matyukha, V.A.; Shmidt, V.S.

1982-01-01

Deposition processes of plutonium (4) hydroxoformates in the system Pu(NO 3 ) 4 -HNO 3 -HCoOH-N6 4 OH-H 2 O have been studied in pH range 0.2-10.7 at total plutonium concentration in the system 100 g/l. It is shown that under the conditions plutonium (4) hydrolysis takes place with the formation of hydroxoformates. A local maximum of plutonium (4) hydroxoformate solubility in the range pH=3.8-4.8, which is evidently conditioned by the formation of soluble formate complex of plutonium in the region, is pointed out. The basic plutonium (4) formates of the composition PuOsub(x)(OH)sub(y)(COOH)sub(4-2x-y)xnHsub(2)O, where 1,3 >=x >= 0.7, 1.7 >= y >= 1.0 and n=1.5-7.0, are singled out, their thermal stability being studied. Density of the crystals and plutonium dioxide, formed during their thermal decomposition, is measured. It is established that for plutonium (4) hydroxoformates common regularities of the influence of salt composition (OH - -, CHOO - - and H 2 O-group numbers in the mulecule) on position of temperature decomposition effects and on the density of compounds, which have been previously found during the study of thorium and plutonium hydroxosalts are observed. It is shown that the density of plutonium dioxide decreases with the increase of hydration and hydrolysis degree of the initial plutonium hydroxoformate

Diffusion in the uranium - plutonium system and self-diffusion of plutonium in epsilon phase; Diffusion dans le systeme uranium-plutonium et autodiffusion du plutonium epsilon

Energy Technology Data Exchange (ETDEWEB)

Dupuy, M [Commissariat a l' Energie Atomique, Fontenay-Aux-Roses (France). Centre d' Etudes Nucleaires

1967-07-01

A survey of uranium-plutonium phase diagram leads to confirm anglo-saxon results about the plutonium solubility in {alpha} uranium (15 per cent at 565 C) and the uranium one in {zeta} phase (74 per cent at 565 C). Interdiffusion coefficients, for concentration lower than 15 per cent had been determined in a temperature range from 410 C to 640 C. They vary between 0.2 and 6 10{sup 12} cm{sup 2} s{sup -1}, and the activation energy between 13 and 20 kcal/mole. Grain boundary, diffusion of plutonium in a uranium had been pointed out by micrography, X-ray microanalysis and {alpha} autoradiography. Self-diffusion of plutonium in {epsilon} phase (bcc) obeys Arrhenius law: D = 2. 10{sup -2} exp -(18500)/RT. But this activation energy does not follow empirical laws generally accepted for other metals. It has analogies with 'anomalous' bcc metals ({beta}Zr, {beta}Ti, {beta}Hf, U{sub {gamma}}). (author) [French] Une etude du diagramme d'equilibre uranium-plutonium conduit a confirmer les resultats anglo-saxons relatifs a la solubilite du plutonium dans l'uranium {alpha} (15 pour cent a 565 C) et de l'uranium dans la phase {zeta} (74 pour cent a 565 C). Les coefficients de diffusion chimique, pour des concentrations inferieures a 15 pour cent ont ete determines a des temperatures comprises entre 410 et 640 C. Ils se situent entre 0.2 et 6. 10{sup 12} cm{sup 2} s{sup -1}. L'energie d'activation varie entre 13 et 20 kcal/mole. La diffusion intergranulaire du plutonium dans l'uranium a a ete mise en evidence par micrographie, microanalyse X et autoradiographie {alpha}. L' autodiffusion du plutonium {beta} cubique centree obeit a la loi d'Arrhenius D = 2. 10{sup -2} exp - (18500)/RT. Son energie d'activation n'obeit pas aux lois empiriques generalement admises pour les autres metaux. Elle possede des analogies avec les cubiques centres ''anormaux'' (Zr{beta}, Ti{beta}, Hf{beta}, U{gamma}). (auteur)

Rapid method to predict the storage stability of middle distillates; Schnelltest zur Vorhersage der Lagerstabilitaet von Mitteldestillaten

Energy Technology Data Exchange (ETDEWEB)

Depta, H.; Wehn, R. [RWE - Gesellschaft fuer Forschung und Entwicklung mbH, Wesseling (Germany); Kohlmeyer, U. [Deutsche Shell AG, Hamburg (Germany)

1998-12-01

und zwar: - die colorimetrische/spektralphotometrische Methode nach R.K. Solly und S.J. Marshman, - die Quantifizierung der SMORS nach M.A. Wechter und D.R. Hardy und - die Bestimmung von Phenalen und Phenalenon sowie von nichtbasischen stickstoffhaltigen Aromaten. Als Referenztest diente die ASTM D 4625-92 (Lagerung bei 43 C ueber einen Zeitraum von 12 Wochen mit Luftkontakt). Nach den vorliegenden Ergebnissen ist keine dieser Methoden als zuverlaessiger Schnelltest geeignet, da die Regressionsanalyse keine akzeptable Korrelation zwischen den Messwerten und den Unloeslichen aus dem Referenztest ausweist. Die Hypothese des Alterungsmechanismus von Pedley et al. konnte nicht bestaetigt werden. Die besten Resultate liefert die spektralphotometrische Methode, mit der unter Einbeziehung des Gesamtstickstoffgehaltes eine Vorhersagegenauigkeit der Testergebnisse nach ASTM von etwa 75% erzielt werden kann. Der zusaetzlich durchgefuehrte Rancimat-Test korreliert ueberhaupt nicht mit den Unloeslichen nach ASTM D 4625-92. Ebensowenig korrelieren die Unloeslichen nach ASTM D 4625 mit dem Gehalt an Sedimenten, die sich nach einem Jahr natuerlicher Lagerung gebildet haben und mittels DIN 51419 bestimmt wurden. Der ergaenzend durchgefuehrte `Shell Fenstertest` hingegen ermoeglicht eine Sicherheit in der Vorhersage der Langzeitstabilitaet von 78%, die sich nach einer Ueberarbeitung des Verfahrens im Hinblick auf reproduzierbare Testbedingungen vermutlich noch verbessern liesse. (orig.)

A method for the gravimetric determination of plutonium in pure plutonium nitrate concentrate solution

International Nuclear Information System (INIS)

Mair, M.A.; Savage, D.J.

1986-12-01

Plutonium nitrate solution is treated with sulphuric acid before being heated and finally ignited. The stoichiometric plutonium dioxide so formed is weighed and hence the plutonium content is calculated. (author)

F. Biological hazards of plutonium

International Nuclear Information System (INIS)

1976-01-01

Plutonium is an unavoidable result of present nuclear power programmes. Its predominant isotopes are extremely long-lived and very toxic if absorbed in the body. In view of the increasing potential for plutonium and man to come into contact, the consequences of any plutonium release into the environment should be scientifically examined. This report is an attempt to place in one document a fully referenced account of the on-going work in many areas. There are three sections. Part 1 deals with the amounts of plutonium available in the fuel cycle, its properties and the probability of routine or accidental release. Part 2 examines the ways in which plutonium can reach man, in particular through food chains or inhalation. Part 3 details the biological effects of plutonium once it is absorbed into the body, assesses the amounts likely to be harmful and discusses the adequacy of present standards for plutonium burdens. There are two appendices. The likely differences between Pu-239, the most studied isotope, and other plutonium isotopes or transuranic nuclides are outlined in Appendix A. Appendix B contains a fuller account of the ways in which the fate of ingested or inhaled plutonium have been determined

Use of plutonium for power production

International Nuclear Information System (INIS)

1965-01-01

The panel reviewed available information on various aspects of plutonium utilization, such as physics of plutonium, technology of plutonium fuels in thermal and fast reactors, behaviour of plutonium fuel under reactor irradiation, technological and economic aspects of plutonium fuel cycle. Refs, figs and tabs

World status report: plutonium

International Nuclear Information System (INIS)

Dircks, W.

1992-01-01

In a recent speech in Japan, the Deputy Director General of the International Atomic Energy Agency (IAEA) said that the economic case for reprocessing spent nuclear fuel had been severely eroded. An edited version of the speech is given. The changed prospects for nuclear energy is given as the reason why the demand for plutonium has declined sharply. The oil crisis of the 1970s reduced the demand for electric power and the economic justification for the use of recycled plutonium. The stockpile of isolated plutonium is growing rapidly giving rise to worries about its security. From this point of view, isolated plutonium is best kept in reactor fuel not separated out. In this connection the IAEA has offered to help in the storage of plutonium so that vigorous safety and security requirements are met. In Japan there is a debate about the plutonium which is dependent on the future of the fast breeder reactor programme. (UK)

Plutonium Finishing Plant

Data.gov (United States)

Federal Laboratory Consortium — The Plutonium Finishing Plant, also known as PFP, represented the end of the line (the final procedure) associated with plutonium production at Hanford.PFP was also...

Double shell tanks plutonium inventory assessment

International Nuclear Information System (INIS)

Tusler, L.A.

1995-01-01

This report provides an evaluation that establishes plutonium inventory estimates for all DSTs based on known tank history information, the DST plutonium inventory tracking system, tank characterization measurements, tank transfer records, and estimated average concentration values for the various types of waste. These estimates use data through December 31, 1994, and give plutonium estimates as of January 1, 1995. The plutonium inventory values for the DSTs are given in Section 31. The plutonium inventory estimate is 224 kg for the DSTs and 854 kg for the SSTs for a total of 1078 kg. This value compares favorably with the total plutonium inventory value of 981 kg obtained from the total plutonium production minus plutonium recovery analysis estimates

Gas sealing efficiency of cap rocks. Pt. 1: Experimental investigations in pelitic sediment rocks. - Pt. 2: Geochemical investigations on redistribution of volatile hydrocarbons in the overburden of natural gas reservoirs; Gas sealing efficiency of cap rocks. T. 1: Experimentelle Untersuchungen in pelitischen Sedimentgesteinen. - T.2: Geochemische Untersuchungen zur Umverteilung leichtfluechtiger Kohlenwasserstoffe in den Deckschichten von Erdgaslagerstaetten. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Leythaeuser; Konstanty, J.; Pankalla, F.; Schwark, L.; Krooss, B.M.; Ehrlich, R.; Schloemer, S.

1997-09-01

New methods and concepts for the assessment of sealing properties of cap rocks above natural gas reservoirs and of the migration behaviour of low molecular-weight hydrocarbons in sedimentary basins were developed and tested. The experimental work comprised the systematic assesment of gas transport parameters on representative samples of pelitic rocks at elevated pressure and temperature conditions, and the characterization of their sealing efficiency as cap rocks overlying hydrocarbon accumulations. Geochemical case histories were carried out to analyse the distribution of low molecular-weight hydrocarbons in the overburden of known natural gas reservoirs in NW Germany. The results were interpreted with respect to the sealing efficiency of individual cap rock lithologies and the type and extent of gas losses. (orig.) [Deutsch] Zur Beurteilung der Abdichtungseigenschaften von Caprocks ueber Gaslagerstaetten und des Migrationsverhaltens niedrigmolekularer Kohlenwasserstoffe in Sedimentbecken wurden neue Methoden und Konzepte entwickelt und angewendet. In experimentellen Arbeiten erfolgte die systematische Bestimmung von Gas-Transportparametern an repraesentativen Proben pelitischer Gesteine unter erhoehten Druck- und Temperaturbedingungen und die Charakterisierung ihrer Abdichtungseffizienz als Deckschicht ueber Kohlenwasserstofflagerstaetten. In geochemischen Fallstudien wurde die Verteilung niedrigmolekularer Kohlenwasserstoffe in den Deckschichten ueber bekannten Erdgaslagerstaetten in NW-Deutschland analysiert und im Hinblick auf die Abdichtungseffizienz einzelner Caprock-Lithologien bzw. Art und Ausmass von Gasverlusten interpretiert. (orig.)

Determination of plutonium in environment

International Nuclear Information System (INIS)

Sakanoue, Masanobu

1978-01-01

Past and present methods of determining the amount of plutonium in the environment are summarized. Determination of the amount of plutonium in uranium ore began in 1941. Plutonium present in polluted environments due to nuclear explosions, nuclear power stations, etc. was measured in soil and sand in Nagasaki in 1951 and in ash in Bikini in 1954. Analytical methods of measuring the least amount of plutonium in the environment were developed twenty years later. Many studies on and reviews of these methods have been reported all over the world, and a standard analytical procedure has been adopted. A basic analytical method of measurement was drafted in Japan in 1976. The yield, treatment of samples, dissolution, separation, control of measurable ray sources determination by α spectrometry, cross-check determination, and treatment of samples containing hardly soluble plutonium were examined. At present, the amount of plutonium can be determined by all of these methods. The presence of plutonium was studied further, and the usefulness of determination of the plutonium isotope ratio is discussed. (Kumagai, S.)

Multi-generational stewardship of plutonium

International Nuclear Information System (INIS)

Pillay, K.K.S.

1997-01-01

The post-cold war era has greatly enhanced the interest in the long-term stewardship of plutonium. The management of excess plutonium from proposed nuclear weapons dismantlement has been the subject of numerous intellectual discussions during the past several years. In this context, issues relevant to long-term management of all plutonium as a valuable energy resource are also being examined. While there are differing views about the future role of plutonium in the economy, there is a recognition of the environmental and health related problems and proliferation potentials of weapons-grade plutonium. The long-term management of plutonium as an energy resource will require a new strategy to maintain stewardship for many generations to come

Plutonium in the marine environment

International Nuclear Information System (INIS)

Jarvis, N.V.; Linder, P.W.; Wade, P.W.

1994-01-01

The shipping of plutonium from Europe to Japan around the Cape is a contentious issue which has raised public concern that South Africa may be at risk to plutonium exposure should an accident occur. The paper describes the containers in which the plutonium (in the form of plutonium oxide, PuO 2 ) is housed and consequences of the unlikely event of these becoming ruptured. Wind-borne pollution is considered not to be a likely scenario, with the plutonium oxide particles more likely to remain practically insoluble and sediment. Plutonium aqueous and environmental chemistry is briefly discussed. Some computer modelling whereby plutonium oxide is brought into contact with seawater has been performed and the results are presented. The impact on marine organisms is discussed in terms of studies performed at marine dump sites and after the crash of a bomber carrying nuclear warheads in Thule, Greenland in 1968. Various pathways from the sea to land are considered in the light of studies done at Sellafield, a reprocessing plant in the United Kingdom. Some recent debates in the popular scientific press, such as that on the leukemia cluster at Sellafield, are described. Plutonium biochemistry and toxicity are discussed as well as medical histories of workers exposed to plutonium. 35 refs., 2 tabs., 1 fig

Plutonium Training Opportunities

Energy Technology Data Exchange (ETDEWEB)

Balatsky, Galya Ivanovna [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Wolkov, Benjamin [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-03-26

This report was created to examine the current state of plutonium training in the United States and to discover ways in which to ensure that the next generation of plutonium workers are fully qualified.

DMSA-scintigraphy in paediatrics: is the evaluation of the geometric mean necessary for the calculation of the differential renal function?; Partialfunktionsberechnung der Nieren mit DMSA in der Paediatrie: ist fuer die Bestimmung das geometrische Mittel notwendig?

Energy Technology Data Exchange (ETDEWEB)

Porn, U.; Alalp, S.; Fischer, S.; Dresel, S. [Klinik und Poliklinik fuer Nuklearmedizin, Klinikum der Ludwig-Maximilians-Univ. Muenchen (Germany); Rossmueller, B. [Inst. fuer Radiologische Diagnostik, Klinikum der Ludwig-Maximilians-Univ. Muenchen (Germany); Hahn, K. [Klinik und Poliklinik fuer Nuklearmedizin, Klinikum der Ludwig-Maximilians-Univ. Muenchen (Germany); Inst. fuer Radiologische Diagnostik, Klinikum der Ludwig-Maximilians-Univ. Muenchen (Germany)

2001-08-01

cases with an obvious anatomical abnormality. (orig.) [German] Bei der statischen Nierenfunktionsszintigraphie mit Tc-99m-Dimercaptobernsteinsaeure (DMSA) wird zur moeglichst exakten Bestimmung der seitengetrennten Partialfunktion (PF) die Berechnung des geometrischen Mittels aus dorsaler und ventraler Projektion empfohlen. Ziel unserer Untersuchung war es, die allein aus der dorsalen Projektion ermittelte Partialfunktion (PF{sub dors}) mit der aus dem geometrischen Mittel berechneten PF (PF{sub geom}) zu vergleichen, um die Notwendigkeit der zusaetzlichen ventralen Projektion zu ueberpruefen. Methode: Es wurden 164 DMSA-Untersuchungen von 151 Kindern (86 w, 65 m) mit einem Alter von 16 d bis 16 a (4,7 {+-} 3,9 a) ausgewertet. Die Akquisition erfolgte mit einer Doppelkopfkamera aus ventraler und dorsaler Projektion (Picker Prism 2000 XP, LEUHR, Matrix: 256 x 256, 300 kcts/view, Zoom: 1,6-2,0). Mittels ROI-Auswertung wurden die Hintergrund-korrigierten Zaehlraten der beiden Nieren von ventral und dorsal bestimmt und die dorsalen Zaehlratenverhaeltnisse mit dem geometrischen Mittel (SQR[Cts{sub dors} x Cts{sub ventr}]) verglichen. Ergebnisse: Die PF{sub dors} ergab statistisch signifikant niedrigere Werte fuer die rechte Niere (bzw. entsprechend hoehere Werte fuer die linke Niere) im Vergleich zur PF{sub geom} (p<0,01). Die mittlere Differenz zwischen der PF{sub geom} und der PF{sub dors} betrug 1,5 {+-} 1,4%. Nur in 6/164 Faellen (3,7%) ergab sich ein Unterschied von {>=}5% (5,0-9,5%). Bei 3 dieser 6 Faelle lag die mit der PF{sub dors} unterschaetzte Niere (2 x links, 1 x rechts) kaudal dystop. Die uebrigen 3 Patienten mit einer Differenz von >5% zeigten keine Lage- oder Strukturanomalie. Schlussfolgerung: Die Berechnung der Partialfunktion ausschliesslich aus den dorsalen Projektionen fuehrt im Vgl. zur Berechnung durch das geometrische Mittel zu einer Unterschaetzung der PF der rechten Niere im Vergleich zur linken Niere. Dieser Effekt fuehrt jedoch bei orthotop

Bestimmung der Mas'se des neutralen Bs-Mesons mit dem ALEPH-Experiment

CERN Document Server

Stehle, M

2001-01-01

Gegenstand der vorliegenden Arbeit ist die Bestimmung der Masse des neutralen Bs-Mesons. Dazu wurden B~-Mesonen in den beiden Zerfallskanalen B~ -+ J/W P und B~ -+ W(2S) P rekonstruiert, wobei die Subresonanzen in den Zerfallsmoden J /w -+ l+ l-, W(2S) -+ l+ l- und P -+ K+ K- untersucht wurden. Diese beiden Kanale werden auf Grund ihrer eindeutigen Signatur auch als "goldene Kanale" bezeichnet und eignen sich deshalb sehr gut fur eine exklusive Rekonstruktion, wie sie hier angewendet wurde. Grundlage der Analyse waren ca. 4 Millionen hadronische ZO-Zerfalle, die in den Jahren 1991 1995 mit dem ALEPH-Detektor am e+e--Speicherring LEP am CERN aufgezeichnet wurden. Die zwischenzeitliche Reprozessierung der Daten ermoglichte eine prazisere und effizientere Rekonstruktion als das in fruheren Messungen der Fall war. Wegen der niedrigen Verzweigungsverhaltnisse der untersuchten Zerfallsmoden wurden nur wenige einzelne Ereignisse in den Daten erwartet. Die selektierten Kandidaten wurden durch Schnitte in mehreren Ere...

Optimizing Plutonium stock management

International Nuclear Information System (INIS)

Niquil, Y.; Guillot, J.

1997-01-01

Plutonium from spent fuel reprocessing is reused in new MOX assemblies. Since plutonium isotopic composition deteriorates with time, it is necessary to optimize plutonium stock management over a long period, to guarantee safe procurement, and contribute to a nuclear fuel cycle policy at the lowest cost. This optimization is provided by the prototype software POMAR

Assessment of technical-scale dewatering results in decanters on the basis of measurements of water types in sewage sludge; Bestimmung grosstechnischer Entwaesserungsergebnisse in Dekantern basierend auf der Messung der Wasserarten von Klaerschlaemmen

Energy Technology Data Exchange (ETDEWEB)

Kopp, J.; Dichtl, N. [Technische Univ. Braunschweig (Germany). Inst. fuer Siedlungswasserwirtschaft

1999-07-01

In a sewage sludge suspension, three water portions can be measured and distinguished from each other. The free water portion is not bound to sludge particles and can be separated by mechanical dewatering. The interstitial water portion bound by capillary forces and bound water (on surfaces and in cells) remain in the sludge cake after dewatering. The described measuring system for thermo-gravimetric determination of the water portions of sewage sludge was adjusted and calibrated at Braunschweig Technical University and permits prognosticating the maximum attainable content of solids through mechanical dewatering in high-performance decanters. (orig.) [German] In einer Klaerschlammsuspension koennen drei Wasseranteile messtechnisch unterschieden werden. Der freie Wasseranteil ist nicht an die Schlammpartikel gebunden und ist bei einer maschinellen Entwaesserung abtrennbar. Der kapillar gehaltene Zwischenraumwasseranteil und das gebundene Wasser (auf Oberflaechen und in Zellen) verbleibt nach der Entwaesserung im Schlammkuchen. Die an der TU Braunschweig angepasste und kalibrierte Messanlage zur thermo-gravimetrischen Bestimmung der Wasseranteile eines Klaerschlammes ermoeglicht es, den maximal bei der maschinellen Entwaesserung in Hochleistungsdekantern erreichbaren Feststoffgehalt zu prognostizieren. (orig.)

Treatment of plutonium contaminations

International Nuclear Information System (INIS)

Lafuma, J.

1983-01-01

Three kinds of plutonium contaminations were considered: skin contamination; contaminated wounds; contamination by inhalation. The treatment of these contaminations was studied for insoluble (oxide and metal forms) and soluble plutonium (complexes). The use of DTPA and therapeutic problems encountered with stable plutonium complexes were analyzed. The new possibilities of internal decontamination using Puchel and LICAM were evaluated [fr

Plutonium uptake by plants from soil containing plutonium-238 dioxide particles. Final report

International Nuclear Information System (INIS)

Brown, K.W.; McFarlane, J.C.

1977-05-01

Three plant species--alfalfa, lettuce, and radishes were grown in soils contaminated with plutonium-238 dioxide (238)PuO2 at concentrations of 23, 69, 92, and 342 nanocuries per gram (nCi/g). The length of exposure varied from 60 days for the lettuce and radishes to 358 days for the alfalfa. The magnitude of plutonium incorporation as indicated by the discrimination ratios for these species, after being exposed to the relatively insoluble PuO2, was similar to previously reported data using different chemical forms of plutonium. Evidence indicates that the predominant factor in plutonium uptake by plants may involve the chelation of plutonium contained in the soils by the action of compounds such as citric acid and/or other similar chelating agents released from the plant roots

Plutonium isotopes in the environment

International Nuclear Information System (INIS)

Holm, E.

1977-12-01

Determination of plutonium and americium by ion exchange and alpha-spectrometry. Deposition of global fall-out and accumulated area-content of 238 Pu, 239 Pu, 240 Pu, 241 Pu, 242 Pu and 241 Am in central Sweden (62.3 deg N, 12.4 deg E), by using the lichen species Cladonia alpestris as bioindicator. Retention and distribution of plutonium in carpets of lichen and soil. Transfer of plutonium from lichen to reindeer and man. Absorbed dose in reindeer and man from plutonium. Basic studies of plutonium and americium in the western Mediterranean surface waters, with emphases on particulate form of the transuranics. (author)

The first metallurgical tests on plutonium; Premiers essais metallurgiques sur le plutonium

Energy Technology Data Exchange (ETDEWEB)

Grison, E; Abramson, R; Anselin, F; Monti, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

Metallic plutonium was first prepared in France in January 1956, as soon as we had access to quantities of the order of several grams of plutonium, which had been extracted from the rods of the pile EL2 at Saclay. Since up to the present this reactor, of thermal power 2 000 kW, has been our only source of plutonium, we have so far only worked on experimental quantities sufficient for the basic tests but not for tests on a scale of possible applications. It is this work, carried out during this phase of preliminary research, which is described below. With the starting up of the plutonium extraction plant at Marcoule, where the reactor G1 has been operating at power for more than a year, we shall go on next to a another order of magnitude which will allow the manufacture and experimentation of prototype fuel elements. (author) [French] La premiere elaboration de plutonium metallique en France fut faite en janvier 1956, des que nous pumes disposer de quantites de plutonium de l'ordre de quelques grammes, qui avaient ete retires des barreaux de la pile EL2 de Saclay. Ce reacteur, d'une puissance thermique de 2 000 kW, ayant ete jusqu'a present notre seule source de plutonium, nous n'avons encore travaille que sur des quantites experimentales suffisantes pour les essais de base, mais non pour des essais a l'echelle d'applications possibles. Ce sont les travaux effectues pendant cette phase de recherches preliminaires qui seront evoques ci-dessous. Avec la mise eu route de l'usine d'extraction de plutonium de Marcoule, ou le reacteur G1 fonctionne en puissance depuis plus d'un an, nous allons passer prochainement a un autre ordre de grandeur, qui nous permettra la fabrication et l'experimentation d'elements combustibles prototypes. (auteur)

Plutonium oxides and uranium and plutonium mixed oxides. Carbon determination

International Nuclear Information System (INIS)

Anon.

Determination of carbon in plutonium oxides and uranium plutonium mixed oxides, suitable for a carbon content between 20 to 3000 ppm. The sample is roasted in oxygen at 1200 0 C, the carbon dioxide produced by combustion is neutralized by barium hydroxide generated automatically by coulometry [fr

Cigarette smoke and plutonium

International Nuclear Information System (INIS)

Filipy, R.E.

1985-01-01

Autoradiographic techniques with liquid photographic emulsion and cellulose nitrate track-etch film are being used to investigate the spatial distribution of inhaled plutonium in the lungs of beagle dogs exposed to cigarette smoke or to the plutonium aerosol only. More plutonium than expected was detected on the inner surfaces of bronchi, and particles were observed beneath the bronchial mucosa. 2 figures, 2 tables

Results obtained with LEGe detectors applied for partial-body counting in the low-energy range (3-150 keV); Erfahrungen mit LEGe-Detektoren bei Teilkoerpermessungen im Bereich niedriger Energien (3-150 keV)

Energy Technology Data Exchange (ETDEWEB)

Dettmann, K. [Bundesamt fuer Strahlenschutz, Berlin (Germany)

1997-12-01

Due to a change in the field of duties, the Phoswich detector hitherto used for organ and partial-body scanning for measuring low-energy {gamma} radiation and X-radiation had to be replaced by a modern detector system. A key application of the new system is detection and in vivo measurement of {sup 210}Pb in the human skeleton. This method of measuring {sup 210}Pb as a long-lived daughter product of radon is applied for retrospective assessment of radiation doses emanatingfrom the radon decay chain, applied to former uranium miners (WISMUT) and members of the population living or having lived in houses with high radon concentrations. The bone activities to be expected from relevant exposures are only slightly above those of the normal {sup 210}Pb content in the bones (10-30 Bq), and the Phoswich detector system was not able to detect incorporated activity down to these low levels. The new system was also tested for its suitability and efficiency in detecting radionuclide depositions in body organs, particularly the actinides that are difficult to identify, in compliance with the relevant regulatory guide. (orig./CB) [Deutsch] In der Inkorporationsmessstelle musste auf Grund neuer Aufgabenstellungen der fuer Organ- und Teilkoerpermessungen zum Nachweis niederenergetischer {gamma}- und Roentgenstrahlung eingesetzte Phoswich-Detektor durch ein modernes Detektorsystem ersetzt werden. Ein wichtiges Einsatzgebiet des neuen Systems ist die Bestimmung von {sup 210}Pb im menschlichen Skelett ueber In-vivo-Messungen. Diese Methode der Bestimmung von {sup 210}Pb als langlebiges Folgeprodukt des Radons dient der retrospektiven Ermittlung der Exposition durch Radon-Zerfallsprodukte bei ehemaligen Uranbergleuten (WISMUT) und Personen aus der Bevoelkerung, die in Wohnhaeusern mit hohen Radonkonzentrationen leben bzw. gelebt haben. Die fuer relevante Expositionen zu erwartenden Skelettaktivitaeten liegen nur wenig ueber dem {sup 210}Pb-Normalgehalt (10-30 Bq). Mit einer

Online measuring devices at sewage treatment plants - state of the art and future market potential; On-Line-Messtechnik auf Klaeranlagen - Aktueller Stand und Marktpotential fuer die Zukunft

Energy Technology Data Exchange (ETDEWEB)

Baumann, P [Inst. fuer Siedlungswasserbau, Wasserguete- und Abfallwirtschaft der Univ. Stuttgart, Abt. Abwassertechnik (Germany); Schlegel, S [Emschergenossenschaft, Essen (Germany)

1998-12-31

By means of a survey commissioned by ATV/GFA, the purposes of use and spheres of use as well as the operating experience with online measuring devices for the determination of ammonium, oxidized nitrogen compounds and orthophosphate were established and evaluated. In addition, data were acquired with the aid of other units for the continuous recording of chemical and physical parameters of sewage treatment. Finally, the future market potentials and development pospects of online measuring devices were evaluated. (orig.) [Deutsch] Anhand einer im Auftrag der ATV/GFA durchgefuehrten Umfrage wurden Einsatzzweck, Einsatzbereiche und Betriebserfahrungen von On-line-Messgeraeten zur Bestimmung von Ammonium, oxidierten Stickstoffverbindungen und Orthophosphat dargestellt und bewertet. Zusaetzlich wurden auch Daten von anderen Geraeteeinheiten zur kontinuierlichen Erfassung von chemischen und physikalischen Parametern bei der Abwasserreinigung erhoben. Anschliessend wurde das zukuenftige Marktpotential und die Entwicklungsmoeglichkeiten bei der On-line-Messtechnik bewertet. (orig.)

Online measuring devices at sewage treatment plants - state of the art and future market potential; On-Line-Messtechnik auf Klaeranlagen - Aktueller Stand und Marktpotential fuer die Zukunft

Energy Technology Data Exchange (ETDEWEB)

Baumann, P. [Inst. fuer Siedlungswasserbau, Wasserguete- und Abfallwirtschaft der Univ. Stuttgart, Abt. Abwassertechnik (Germany); Schlegel, S. [Emschergenossenschaft, Essen (Germany)

1997-12-31

By means of a survey commissioned by ATV/GFA, the purposes of use and spheres of use as well as the operating experience with online measuring devices for the determination of ammonium, oxidized nitrogen compounds and orthophosphate were established and evaluated. In addition, data were acquired with the aid of other units for the continuous recording of chemical and physical parameters of sewage treatment. Finally, the future market potentials and development pospects of online measuring devices were evaluated. (orig.) [Deutsch] Anhand einer im Auftrag der ATV/GFA durchgefuehrten Umfrage wurden Einsatzzweck, Einsatzbereiche und Betriebserfahrungen von On-line-Messgeraeten zur Bestimmung von Ammonium, oxidierten Stickstoffverbindungen und Orthophosphat dargestellt und bewertet. Zusaetzlich wurden auch Daten von anderen Geraeteeinheiten zur kontinuierlichen Erfassung von chemischen und physikalischen Parametern bei der Abwasserreinigung erhoben. Anschliessend wurde das zukuenftige Marktpotential und die Entwicklungsmoeglichkeiten bei der On-line-Messtechnik bewertet. (orig.)

Hazards of plutonium and fuel reprocessing

International Nuclear Information System (INIS)

Watson, G.M.

1978-01-01

Apart from the possibility that civil plutonium may be diverted to military use the main argument against the introduction of a plutonium economy seems to be the supposedly unmanageable biological risk attached to plutonium itself. The author points out weaknesses in many of the opponents' arguments against the increased use of plutonium and argues that current safety practices are more than adequate in handling plutonium and other radioactive materials

Uncertainty and sensitivity analysis of applications of the PARK program system; Unsicherheits- und Sensitivitaetsanalyse von Anwendungen des Programmsystems PARK

Energy Technology Data Exchange (ETDEWEB)

Luczak-Urlik, D.; Bleher, M.; Jacob, P.; Mueller, H. [GSF - Forschungszentrum fuer Umwelt und Gesundheit Neuherberg GmbH, Oberschleissheim (Germany). Inst. fuer Strahlenschutz; Hofer, E.; Krzykacz, B. [Gesellschaft fuer Reaktorsicherheit mbH (Greece)

1997-11-01

von Futter- und Lebensmitteln und potentiellen Strahlenexpositionen der Bevoelkerung durchgefuehrt. Fuer verschiedene Immissions-Szenarien (Nuklidspektren fuer zwei Freisetzungsarten, fuer nasse und fuer trockene Ablagerung und fuer drei Zeitpunkte im Jahr) wurden die Unsicherheiten in Modell-Inputparametern, d.h. Messwerten und radiooekologischen Parametern durch subjektive Wahrscheinlichkeitsverteilungen ausgedrueckt. Die daraus resultierenden Verteilungen der Outputgroessen wurden mit Monte Carlo Simulationen bestimmt. Die Ergebnisse der Unsicherheits- und Sensitivitaetsanalyse haengen im allgemeinen von dem betrachteten Immissions-Szenario ab. Die groessten Beitraege zur Unsicherheit der berechneten Groessen kamen in den meisten Faellen von Messwerten (insbesondere der in-situ Messung der Bodenaktivitaet) und vom Aktivitaetstransfer vom Futter zum Nahrungsmittel. Im Fall der nassen Deposition kommen die Unsicherheiten von Parametern hinzu, die zur Bestimmung des Interzeptionsfaktors (Anteil der nass deponierten Aktivitaet, der vom Plfanzenbestand zurueckgehalten wird) dienen. Die an Mess-Stationen der Gammadosisleistung fehlende Information ueber Niederschlaege macht die Aussagen auf Kreisebene sehr unsicher. Der Unsicherheitsbereich der PARK-Rechenergebnisse nimmt mit der abgeschaetzten Regenmenge zu. (orig.)

Plutonium spectrophotometric analysis

International Nuclear Information System (INIS)

Esteban, A.; Cassaniti, P.; Orosco, E.H.

1990-01-01

Plutonium ions in solution have absorption spectra so different that it is possible to use them for analytical purposes. Detailed studies have been performed in nitric solutions. Some very convenient methods for the determination of plutonium and its oxidation states, especially the ratios Pu(III):Pu(IV) and Pu(IV):Pu(VI) in a mixture of both, have been developed. These methods are described in this paper, including: a) Absorption spectra for plutonium (III), (IV), (VI) and mixtures. b) Relative extinction coefficients for the above mentioned species. c) Dependences of the relative extinction coefficients on the nitric acid concentration and the plutonium VI deviation from the Beer-Lambert law. The developed methods are simple and rapid and then, suitable in process control. Accuracy is improved when relative absorbance measurements are performed or controlled the variables which have effect on the spectra and extinction coefficients. (Author) [es

Plutonium safe handling

International Nuclear Information System (INIS)

Tvehlov, Yu.

2000-01-01

The abstract, prepared on the basis of materials of the IAEA new leadership on the plutonium safe handling and its storage (the publication no. 9 in the Safety Reports Series), aimed at presenting internationally acknowledged criteria on the radiation danger evaluation and summarizing the experience in the safe management of great quantities of plutonium, accumulated in the nuclear states, is presented. The data on the weapon-class and civil plutonium, the degree of its danger, the measures for provision of its safety, including the data on accident radiation consequences with the fission number 10 18 , are presented. The recommendations, making it possible to eliminate the super- criticality danger, as well as ignition and explosion, to maintain the tightness of the facility, aimed at excluding the radioactive contamination and the possibility of internal irradiation, to provide for the plutonium security, physical protection and to reduce irradiation are given [ru

Some of the properties of plutonium and the aluminium-plutonium alloy; Quelques proprietes du plutonium et de l'alliage aluminium-plutonium

Energy Technology Data Exchange (ETDEWEB)

Abramson, R; Boucher, R; Fabre, R; Monti, H [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1959-07-01

1- Study of the physical properties of plutonium. 1) Study of the allotropy of plutonium. a) Thermal analysis: the apparatus used and the measurement technique are briefly described. The transition point temperatures and the corresponding heats of transformation have been determined. Finally, the results of the particular study of certain transition points are given. b) Dilatometry. The dilatometric analysis of the phase changes of plutonium has been carried out by means of the Chevenard dilatometer with photographic recording. The testing conditions (heating and cooling speeds, isotherm plateaux) have been varied in order to determine accurately the characteristics of each transition, particularly the {delta} {yields} {gamma} transition on cooling. 2) Micrography of plutonium. For the accurate preparation of metallographic samples the electrolytic polishing must be rapid, which implies a mechanical polishing of excellent quality. Information is given on new attacking reagents which show the structure of the metal very clearly. 2- Study of aluminium-plutonium alloys. Comparative study of Al-Pu and Al-U alloys rich in aluminium. a) Thermal analysis. The liquids and fusion temperatures of the eutectic Al-XAl{sub 4}, have been accurately determined. From the measurement of the heats of fusion the exact composition of the eutectic alloy has been determined. b) Thermal treatments. The eutectic coalescence kinetics have been studied by a micrographic method and by following the evolution of hardness. The results obtained show that the phenomenon is more rapid in Al-Pu alloys than in Al-U alloys. c) Micrographic study of the transition XAl{sub 3} {yields} XAl{sub 4}. The peritectic reaction XAl{sub 3} + liq. {yields} XAl{sub 4} has been suppressed by quenching. The transformation of the XAl{sub 3} phase to the solid phase has been studied as well as the effect of small additions of silicon on the kinetics of this reaction. (author) [French] 1- Etude des proprietes

Biomagnification of hexachlorobenzene: influence of uptake routes in a laboratory test; Aufnahmepfade von POPs in Biota. Biomagnifikation von Hexachlorobenzol im Labortest

Energy Technology Data Exchange (ETDEWEB)

Egeler, P.; Meller, M.; Roembke, J.; Spoerlein, P. [ECT Oekotoxikologie GmbH, Floersheim/Main (Germany)

2001-07-01

In order to evaluate such a potential biomagnification, a laboratory test was developed. It consisted of a two-step food chain including the sediment dwelling freshwater oligochaete Tubifex tubifex (Mueller) and the three-spined stickleback (Gasterosteus aculeatus, Linne), a small teleost fish which often feeds primarily on benthic invertebrates. Artificial sediment and reconstituted water were used. To examine the influence of benthic prey on the bioaccumulation of a POP in the predator, fish were exposed to {sup 14}C-labelled hexachlorobenzene via spiked water, spiked sediment, pre-contaminated prey organisms, and to combinations of these exposure routes. Summarising the results of these experiments, it could be shown that the exposure to HCB via different routes resulted in a significantly higher accumulation in fish than an exposure to single pathways. It was concluded that the major uptake routes for fish were the overlying water and the food, whereas the contribution of spiked sediment itself was relatively small. HCB was biomagnified in the tested laboratory food chain. Therefore, concerning secondary poisoning, the environmental risk assessment of POPs like HCB should not be based on existing bioaccumulation tests alone, since they focus only on exposure via the water pathway. Instead, the influence of food and sediment as exposure routes should be considered as well, using comprehensive food chain modelling and/or laboratory studies. (orig.) [German] Zur standardisierten Bestimmung der Bioakkumulation und - magnifikation wurde eine einfache, zwei trophische Stufen umfassende Labornahrungskette etabliert. Diese bestand aus dem endobenthischen Oligochaeten Tubifex tubifex und dem Dreistachligen Stichling (Gasterosteus aculeatus) als Praedator. Die Experimente wurden mit {sup 14}C-markiertem Hexachlorbenzol in dotiertem kuenstlichem Sediment und rekonstituiertem Wasser durchgefuehrt. Um den Einfluss benthischer Beuteorganismen zu quantifizeren, wurden die

Burning weapons-grade plutonium in reactors

International Nuclear Information System (INIS)

Newman, D.F.

1993-06-01

As a result of massive reductions in deployed nuclear warheads, and their subsequent dismantlement, large quantities of surplus weapons- grade plutonium will be stored until its ultimate disposition is achieved in both the US and Russia. Ultimate disposition has the following minimum requirements: (1) preclude return of plutonium to the US and Russian stockpiles, (2) prevent environmental damage by precluding release of plutonium contamination, and (3) prevent proliferation by precluding plutonium diversion to sub-national groups or nonweapons states. The most efficient and effective way to dispose of surplus weapons-grade plutonium is to fabricate it into fuel and use it for generation of electrical energy in commercial nuclear power plants. Weapons-grade plutonium can be used as fuel in existing commercial nuclear power plants, such as those in the US and Russia. This recovers energy and economic value from weapons-grade plutonium, which otherwise represents a large cost liability to maintain in safeguarded and secure storage. The plutonium remaining in spent MOX fuel is reactor-grade, essentially the same as that being discharged in spent UO 2 fuels. MOX fuels are well developed and are currently used in a number of LWRs in Europe. Plutonium-bearing fuels without uranium (non-fertile fuels) would require some development. However, such non-fertile fuels are attractive from a nonproliferation perspective because they avoid the insitu production of additional plutonium and enhance the annihilation of the plutonium inventory on a once-through fuel cycle

Process for recovery of plutonium from fabrication residues of mixed fuels consisting of uranium oxide and plutonium oxide

International Nuclear Information System (INIS)

Heremanns, R.H.; Vandersteene, J.J.

1983-01-01

The invention concerns a process for recovery of plutonium from fabrication residues of mixed fuels consisting of uranium oxide and plutonium oxide in the form of PuO 2 . Mixed fuels consisting of uranium oxide and plutonium oxide are being used more and more. The plants which prepare these mixed fuels have around 5% of the total mass of fuels as fabrication residue, either as waste or scrap. In view of the high cost of plutonium, it has been attempted to recover this plutonium from the fabrication residues by a process having a purchase price lower than the price of plutonium. The problem is essentially to separate the plutonium, the uranium and the impurities. The residues are fluorinated, the UF 6 and PuF 6 obtained are separated by selective absorption of the PuF 6 on NaF at a temperature of at least 400 0 C, the complex obtained by this absorption is dissolved in nitric acid solution, the plutonium is precipitated in the form of plutonium oxalate by adding oxalic acid, and the precipitated plutonium oxalate is calcined

METHOD OF PRODUCING PLUTONIUM TETRAFLUORIDE

Science.gov (United States)

Tolley, W.B.; Smith, R.C.

1959-12-15

A process is presented for preparing plutonium tetrafluoride from plutonium(IV) oxalate. The oxalate is dried and decomposed at about 300 deg C to the dioxide, mixed with ammonium bifluoride, and the mixture is heated to between 50 and 150 deg C whereby ammonium plutonium fluoride is formed. The ammonium plutonium fluoride is then heated to about 300 deg C for volatilization of ammonium fluoride. Both heating steps are preferably carried out in an inert atmosphere.

Plutonium Plant, Trombay

International Nuclear Information System (INIS)

Yadav, J.S.; Agarwal, K.

2017-01-01

The journey of Indian nuclear fuel reprocessing started with the commissioning of Plutonium Plant (PP) at Trombay on 22"n"d January, 1965 with an aim to reprocess the spent fuel from research reactor CIRUS. The basic process chosen for the plant was Plutonium Uranium Reduction EXtraction (PUREX) process. In seventies, the plant was subjected to major design modifications and replacement of hardware, which later met the additional demand from research reactor DHRUVA. The augmented plutonium plant has been operating since 1983. Experience gained from this plant was very much helpful to design future reprocessing plant in the country

The toxicity of plutonium

International Nuclear Information System (INIS)

Crouse, P.L.

1994-01-01

Shipments of plutonium occasionally pass around the Cape coastal waters on its way to Japan from Europe. This invariably leads to a great deal of speculation of the dangers involved and of the extreme toxicity of plutonium, with the media and environmental groups claiming that (a) plutonium is the most toxic substance known to man, and that (b) a few kilograms of plutonium ground finely and dispersed in the atmosphere could kill every human being on earth. Comparisons with other poisons are drawn, e.g. common inorganic chemicals and biological agents. The original scare around the extraordinary toxicity of Pu seems to have started in 1974 with the claims of Tamplin and Cochran's hot particle theory about plutonium lodging in the sensitive portions of the lungs in small concentrated aggregates where they are much more effective in producing cancers. This theory, however, is regarded as thoroughly discredited by the experts in the field of radiotoxicity. 8 refs

von Neumann Morgenstern Preferences

DEFF Research Database (Denmark)

Vind, Karl

von Neumann Morgenstern utility is generalized to von Neumann Morgenstern preferences. The proof is an application of simple hyperplane theorems......von Neumann Morgenstern utility is generalized to von Neumann Morgenstern preferences. The proof is an application of simple hyperplane theorems...

von Neumann Morgenstern Preferences

DEFF Research Database (Denmark)

Vind, Karl

2000-01-01

von Neumann Morgenstern utility is generalized to von Neumann Morgenstern preferences. The proof is an application of simple hyperplane theorems......von Neumann Morgenstern utility is generalized to von Neumann Morgenstern preferences. The proof is an application of simple hyperplane theorems...

Plutonium use in foreign countries (03)

International Nuclear Information System (INIS)

Otagaki, Takao

2004-03-01

European countries and Japan had been implementing the strategy of spent fuel reprocessing in order to use nuclear material to the maximum. Plutonium recovered from reprocessing, however, must be recycle on light water reactors (LWRs) because of considerable delay of fast reactor development. In Europe, much of experiences of plutonium recycling have been accumulated until now. Thus, the status of plutonium recycling up to the end of 2003 in France, Germany, The U.K., Belgium, Switzerland and other countries were studied based on the following scope. (1) Basic policy and present status of plutonium recycling in primary countries of France, Germany, The U.K., Belgium, Switzerland, and Sweden which plans to recycle a part of plutonium: Backend policy and the status of spent fuel management were studied, then integrated analysis and evaluation of the position of plutonium recycling in backend and the status of plutonium recycling development were performed. (2) Plan and experience of Mixed Oxide (MOX) fuel fabrication and reprocessing of spent fuels: The data and information on plan and experience of MOX fuel fabrication and reprocessing in foreign countries were collected. (3) Plutonium inventories: The data and information of plutonium inventories of foreign countries were collected. (author)

Cigarette smoke and plutonium

International Nuclear Information System (INIS)

Filipy, R.E.

1983-01-01

The major objective of this project is to obtain experimental data that are directly applicable to resolving the question of whether cigarette smokers are at greater risk than nonsmokers to potential health effects of inhaled plutonium. Because cigarette smokers constitute a large fraction of the population, a synergistic effect of plutonium and cigarette smoke might influence estimates of the health risk for plutonium and other transuranics released to the environment

Cycle downstream: the plutonium question

International Nuclear Information System (INIS)

Zask, G.; Rome, M.; Delpech, M.

1998-01-01

This day, organized by the SFEN, took place at Paris the 4 june 1998. Nine papers were presented. They take stock on the plutonium physics and its utilization as a nuclear fuel. This day tried to bring information to answer the following questions: do people have to keep the plutonium in the UOX fuel or in the MOX fuel in order to use it for future fast reactors? Do people have to continue obstinately the plutonium reprocessing in the MOX for the PWR type reactors? Will it be realized a underground disposal? Can it be technically developed plutonium incinerators and is it economically interesting? The plutonium physics, the experimental programs and the possible solutions are presented. (A.L.B.)

Aqueous Solution Chemistry of Plutonium

Energy Technology Data Exchange (ETDEWEB)

Clark, David L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2014-01-28

Things I have learned working with plutonium: Chemistry of plutonium is complex; Redox equilibria make Pu solution chemistry particularly challenging in the absence of complexing ligands; Understanding this behavior is key to successful Pu chemistry experiments; There is no suitable chemical analog for plutonium.

Plutonium Proliferation: The Achilles Heel of Disarmament

International Nuclear Information System (INIS)

Leventhal, Paul

2001-01-01

Plutonium is a byproduct of nuclear fission, and it is produced at the rate of about 70 metric tons a year in the world's nuclear power reactors. Concerns about civilian plutonium ran high in the 1970s and prompted enactment of the Nuclear Non-Proliferation Act of 1978 to give the United States a veto over separating plutonium from U.S.-supplied uranium fuel. Over the years, however, so-called reactor-grade plutonium has become the orphan issue of nuclear non-proliferation, largely as a consequence of pressures from plutonium-separating countries. The demise of the fast breeder reactor and the reluctance of utilities to introduce plutonium fuel in light-water reactors have resulted in large surpluses of civilian, weapons-usable plutonium, which now approach in size the 250 tons of military plutonium in the world. Yet reprocessing of spent fuel for recovery and use of plutonium proceeds apace outside the United States and threatens to overwhelm safeguards and security measures for keeping this material out of the hands of nations and terrorists for weapons. A number of historical and current developments are reviewed to demonstrate that plutonium commerce is undercutting efforts both to stop the spread of nuclear weapons and to work toward eliminating existing nuclear arsenals. These developments include the breakdown of U.S. anti-plutonium policy, the production of nuclear weapons by India with Atoms-for-Peace plutonium, the U.S.-Russian plan to introduce excess military plutonium as fuel in civilian power reactors, the failure to include civilian plutonium and bomb-grade uranium in the proposed Fissile Material Cutoff Treaty, and the perception of emerging proliferation threats as the rationale for development of a ballistic missile defense system. Finally, immobilization of separated plutonium in high-level waste is explored as a proliferation-resistant and disarmament-friendly solution for eliminating excess stocks of civilian and military plutonium.

Gamma ray NDA assay system for total plutonium and isotopics in plutonium product solutions

International Nuclear Information System (INIS)

Cowder, L.R.; Hsue, S.T.; Johnson, S.S.; Parker, J.L.; Russo, P.A.; Sprinkle, J.K.; Asakura, Y.; Fukuda, T.; Kondo, I.

1979-01-01

A LASL-designed gamma-ray NDA instrument for assay of total plutonium and isotopics of product solutions at Tokai-Mura is currently installed and operating. The instrument is, optimally, a densitometer that uses radioisotopic sources for total plutonium measurements at the K absorption edge. The measured transmissions of additional gamma-ray lines from the same radioisotopic sources are used to correct for self-attenuation of passive gamma rays from plutonium. The corrected passive data give the plutonium isotopic content of freshly separated to moderately aged solutions. This off-line instrument is fully automated under computer control, with the exception of sample positioning, and operates routinely in a mode designed for measurement control. A one-half percent precision in total plutonium concentration is achieved with a 15-minute measurement

An autoradiographical method using an imaging plate for the analyses of plutonium contamination in a plutonium handling facility

International Nuclear Information System (INIS)

Takasaki, Koji; Sagawa, Naoki; Kurosawa, Shigeyuki; Mizuniwa, Harumi

2011-01-01

An autoradiographical method using an imaging plate (IP) was developed to analyze plutonium contamination in a plutonium handling facility. The IPs were exposed to ten specimens having a single plutonium particle. Photostimulated luminescence (PSL) images of the specimens were taken using a laser scanning machine. One relatively large spot induced by α-radioactivity from plutonium was observed in each PSL image. The plutonium-induced spots were discriminated by a threshold derived from background and the size of the spot. A good relationship between the PSL intensities of the spots and α-radioactivities measured using a radiation counter was obtained by least-square fitting, taking the fading effect into consideration. This method was applied to workplace monitoring in an actual uranium-plutonium mixed oxide (MOX) fuel fabrication facility. Plutonium contaminations were analyzed in ten other specimens having more than two plutonium spots. The α-radioactivities of plutonium contamination were derived from the PSL images and their relative errors were evaluated from exposure time. (author)

Recovery of plutonium by pyroredox processing

International Nuclear Information System (INIS)

McNeese, J.A.; Bowersox, D.F.; Christensen, D.C.

1985-09-01

Using pyrochemical oxidation and reduction, we have developed a process to recover the plutonium in impure scrap with less than 95% plutonium. This plutonium metal was further purified by pyrochemical electrorefining. During development of the procedures, depleted electrorefining anodes were processed, and over 80% of the plutonium was recovered as high-purity metal in one electrorefining cycle. Over 40 kg of plutonium has been recovered from 55 kg of impure anodes with our procedures. 6 refs., 7 figs., 4 tabs

Recovery of plutonium by pyroredox processing

International Nuclear Information System (INIS)

McNeese, J.A.; Bowersox, D.F.; Christensen, D.C.

1985-01-01

Using pyrochemical oxidation and reduction, we have developed a process to recover the plutonium in impure scrap with less than 95% plutonium. This plutonium metal was further purified by pyrochemical electrorefining. During development of the procedures, depleted electrorefining anodes were processed, and over 80% of the plutonium was recovered as high-purity metal in one electrorefining cycle. Over 40 kg of plutonium has been recovered from 55 kg of impure anodes with our procedures. 6 refs., 2 figs., 5 tabs

The use of calorimetry for plutonium assay

International Nuclear Information System (INIS)

Mason, J.A.

1982-12-01

Calorimetry is a technique for measuring the thermal power of heat-producing substances. The technique may be applied to the measurement of plutonium-bearing materials which evolve heat as a result of alpha and beta decay. A calorimetric measurement of the thermal power of a plutonium sample, combined with a knowledge or measurement of the plutonium isotopic mass ratios of the sample provides a convenient and accurate, non-destructive measure of the total plutonium mass of the sample. The present report provides a description, and an assessment of the calorimetry technique applied to the assay of plutonium-bearing materials. Types and characteristics of plutonium calorimeters are considered, as well as calibration and operating procedures. The instrumentation used with plutonium calorimeters is described and the use of computer control for calorimeter automation is discussed. A critical review and assessment of plutonium calorimetry literature since 1970 is presented. Both fuel element and plutonium-bearing material calorimeters are considered. The different types of plutonium calorimeters are evaluated and their relative merits are discussed. A combined calorimeter and gamma-ray measurement assay system is considered. The design principles of plutonium assay calorimeters are considered. An automatic, computer-based calorimeter control system is proposed in conjunction with a general plutonium assay calorimeter design. (author)

Analytic determination of plutonium in the environment; Determination analytique du plutonium dans l'environnement

Energy Technology Data Exchange (ETDEWEB)

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

1967-07-01

The work described in this report was undertaken with a view to determining the plutonium content in the fall-out from nuclear explosions. In the first part are described in turn the importance of the problems due to the plutonium, the physico-chemical properties of the radioelement and the biological dangers which it presents. A detailed and critical analysis is made of the radio-toxicological determination of the plutonium as reported in the literature prior to this report. The second part consists in the presentation of a judicious choice of techniques making it possible to determine plutonium in air, rain-water, soils and ash. After a detailed description of the measurement equipment and the operational techniques which have been developed, a justification of these techniques is given with particular reference to their sensitivity and specificity. After a brief conclusion concerning the preceding chapters, the results are presented. These are then discussed in the ease of each element in which the plutonium has been determined. This discussion is concluded by a consideration of the importance of the occurrence of fall-out plutonium on problems relating to public health. From a consideration of 200 analyses carried out, it is concluded that the contribution of plutonium to the exposure of populations is still very small compared to that of natural radiation and that due to such fission products as strontium 90. The report includes 63 literature references, 26 figures and 11 tables. (author) [French] Les travaux decrits dans ce memoire ont ete entrepris et eflectues dans le but de mettre en evidence le plutonium des retombees radioactives consecutives aux explosions nucleaires. Dans la premiere partie nous etudions successivement l'importance des problemes poses par le plutonium puis les proprietes physicochimiques du radioelement et les dangers qu'il presente du point de vue biologique. Nous effectuons une analyse detaillee et critique des techniques

Weapons-grade plutonium dispositioning. Volume 4

International Nuclear Information System (INIS)

Sterbentz, J.W.; Olsen, C.S.; Sinha, U.P.

1993-06-01

This study is in response to a request by the Reactor Panel Subcommittee of the National Academy of Sciences (NAS) Committee on International Security and Arms Control (CISAC) to evaluate the feasibility of using plutonium fuels (without uranium) for disposal in existing conventional or advanced light water reactor (LWR) designs and in low temperature/pressure LWR designs that might be developed for plutonium disposal. Three plutonium-based fuel forms (oxides, aluminum metallics, and carbides) are evaluated for neutronic performance, fabrication technology, and material and compatibility issues. For the carbides, only the fabrication technologies are addressed. Viable plutonium oxide fuels for conventional or advanced LWRs include plutonium-zirconium-calcium oxide (PuO 2 -ZrO 2 -CaO) with the addition of thorium oxide (ThO 2 ) or a burnable poison such as erbium oxide (Er 2 O 3 ) or europium oxide (Eu 2 O 3 ) to achieve acceptable neutronic performance. Thorium will breed fissile uranium that may be unacceptable from a proliferation standpoint. Fabrication of uranium and mixed uranium-plutonium oxide fuels is well established; however, fabrication of plutonium-based oxide fuels will require further development. Viable aluminum-plutonium metallic fuels for a low temperature/pressure LWR include plutonium aluminide in an aluminum matrix (PuAl 4 -Al) with the addition of a burnable poison such as erbium (Er) or europium (Eu). Fabrication of low-enriched plutonium in aluminum-plutonium metallic fuel rods was initially established 30 years ago and will require development to recapture and adapt the technology to meet current environmental and safety regulations. Fabrication of high-enriched uranium plate fuel by the picture-frame process is a well established process, but the use of plutonium would require the process to be upgraded in the United States to conform with current regulations and minimize the waste streams

Recovery studies for plutonium machining oil coolant

International Nuclear Information System (INIS)

Navratil, J.D.; Baldwin, C.E.

1977-01-01

Lathe coolant oil, contaminated with plutonium and having a carbon tetrachloride diluent, is generated in plutonium machining areas at Rocky Flats. A research program was initiated to determine the nature of plutonium in this mixture of oil and carbon tetrachloride. Appropriate methods then could be developed to remove the plutonium and to recycle the oil and carbon tetrachloride. Studies showed that the mixtures of spent oil and carbon tetrachloride contained particulate plutonium and plutonium species that are soluble in water or in oil and carbon tetrachloride. The particulate plutonium was removed by filtration; the nonfilterable plutonium was removed by adsorption on various materials. Laboratory-scale tests indicated the lathe-coolant oil mixture could be separated by distilling the carbon tetrachloride to yield recyclable products

Plutonium use in foreign countries (01)

International Nuclear Information System (INIS)

Otagaki, Takao

2002-03-01

European countries and Japan had been implementing the strategy of spent fuel reprocessing in order to use nuclear material to the maximum. Plutonium recovered from reprocessing, however, must be recycle on light water reactors (LWRs) because of considerable delay of fast reactor development. In Europe, much of experience of plutonium recycling have been accumulated until now. Thus, the status of plutonium recycling up to the end of 2001 in France, Germany, The U.K., Belgium, Switzerland and other countries were studied based on the following scope. (1) Basic policy and present status of plutonium recycling in primary countries of France, Germany, The U.K., Belgium, Switzerland, and Sweden which recently appears the move of recycling a part of plutonium. Backend policy and the status of spent fuel management were studied, then integrated analysis and evaluation of the position of plutonium recycling in backend and the status of plutonium recycling development were performed. (2) Plan and experience of Mixed Oxide (MOX) fuel fabrication and reprocessing of spent fuels. The data and information on plan and experience of MOX fuel fabrication and reprocessing in foreign countries were collected. (3) Plutonium inventories. The data and information on plutonium inventories of foreign countries were collected. (author)

Plutonium use in foreign countries (99)

International Nuclear Information System (INIS)

Otagaki, Takao

2000-03-01

European countries and Japan had been implementing the strategy of spent fuel reprocessing in order to use nuclear material to the maximum. Plutonium recovered from reprocessing, however, must be recycle on light water reactors (LWRs) because of considerable delay of fast reactor development. In Europe, much of experience of plutonium recycling have been accumulated until now. Thus, the status of plutonium recycling up to the end of 1999 in France, Germany, The U.K., Belgium, Switzerland and other countries were studied based on the following scope. (1) Basic policy and present status of plutonium recycling in primary countries of France, Germany, The U.K., Belgium, Switzerland, and Sweden which recently appears the move to recycling a part of plutonium backend policy and the status of spent fuel management were studied, then integrated analysis and evaluation of the position of plutonium recycling in backend and the status of plutonium recycling development were performed. (2) Plan and experience of Mixed Oxide (MOX) fuel fabrication and reprocessing of spent fuels. The data and information on plan and experience of MOX fuel fabrication and reprocessing in foreign countries were collected. (3) Plutonium inventories. The data and information on plutonium inventories of foreign counties were collected. (author)

Plutonium use in foreign countries (02)

International Nuclear Information System (INIS)

Otagaki, Takao

2003-02-01

European countries and Japan had been implementing the strategy of spent fuel reprocessing in order to use nuclear material to the maximum. Plutonium recovered from reprocessing, however, must be recycle on light water reactors (LWRs) because of considerable delay of fast reactor development. In Europe, much of experience of plutonium recycling have been accumulated until now. Thus, the status of plutonium recycling up to the end of 2002 in France, Germany, The U.K., Belgium, Switzerland and other countries were studied based on the following scope. (1) Basic policy and present status of plutonium recycling in primary countries of France, Germany, The U.K., Belgium, Switzerland, and Sweden which recently appears the move of recycling a part of plutonium. Backend policy and the status of spent fuel management were studied, then integrated analysis and evaluation of the position of plutonium recycling in backend and the status of plutonium recycling development were performed. (2) Plan and experience of Mixed Oside (MOX) fuel fabrication and reprocessing of spent fuels. The data and information on plan and experience of MOX fuel fabrication and reprocessing in foreign countries were collected. (3) Plutonium inventories. The data and information on plutonium inventories of foreign countries were collected. (author)

Plutonium use in foreign countries. (04)

International Nuclear Information System (INIS)

Otagaki, Takao

2005-03-01

European countries and Japan had been implementing the strategy of spent fuel reprocessing in order to use nuclear material to the maximum. Plutonium recovered from reprocessing, however, must be recycle on light water reactors (LWRs) because of considerable delay of fast reactor development. In Europe, much of experience of plutonium recycling have been accumulated until now. Thus, the status of plutonium recycling up to the end of 2004 in France, Germany, The U.K., Belgium, Switzerland and other countries were studied based on the following scope. (1) Basic policy and present status of plutonium recycling in primary countries of France, Germany, the U.K., Belgium, Switzerland, and Sweden which plans to recycle a limited amount of plutonium: Backend policy and the status of spent fuel management were studied, then integrated analysis and evaluation of the position of plutonium recycling in backend and the status of plutonium recycling development were performed. (2) Plan and experience of Mixed Oxide (MOX) fuel fabrication and reprocessing of spent fuels: The data and information on plan and experience of MOX fuel fabrication and reprocessing in foreign countries were collected. (3) Plutonium inventories: The data and information on plutonium inventories of foreign countries were collected. (author)

Laboratory-scale evaluations of alternative plutonium precipitation methods

International Nuclear Information System (INIS)

Martella, L.L.; Saba, M.T.; Campbell, G.K.

1984-01-01

Plutonium(III), (IV), and (VI) carbonate; plutonium(III) fluoride; plutonium(III) and (IV) oxalate; and plutonium(IV) and (VI) hydroxide precipitation methods were evaluated for conversion of plutonium nitrate anion-exchange eluate to a solid, and compared with the current plutonium peroxide precipitation method used at Rocky Flats. Plutonium(III) and (IV) oxalate, plutonium(III) fluoride, and plutonium(IV) hydroxide precipitations were the most effective of the alternative conversion methods tested because of the larger particle-size formation, faster filtration rates, and the low plutonium loss to the filtrate. These were found to be as efficient as, and in some cases more efficient than, the peroxide method. 18 references, 14 figures, 3 tables

The plutonium danger

International Nuclear Information System (INIS)

Ruiter, W. de

1983-01-01

Nobody can ignore the fact that plutonium is potentially very dangerous and the greatest danger concerning it lies in the spreading of nuclear weapons via nuclear energy programmes. The following seven different attitudes towards this problem are presented and discussed: 1) There is no connection between peaceful and military applications; 2) The problem cannot be prevented; 3) A technical solution must be found; 4) plutonium must be totally inaccessible to countries involved in acquiring nuclear weapons; 5) The use of plutonium for energy production should only occur in one multinational centre; 6) Dogmas in the nuclear industry must be enfeebled; 7) All developments in this area should stop. (C.F.)

Studies on O/M ratio determination in uranium oxide, plutonium oxide and uranium-plutonium mixed oxide

International Nuclear Information System (INIS)

Sampath, S.; Chawla, K.L.

1975-01-01

Thermogravimetric studies were carried out in unsintered and sintered samples of uranium oxide, plutonium oxide and uranium-plutonium mixed oxide under different atmospheric conditions (air, argon and moist argon/hydrogen). Moisture loss was found to occur below 200 0 C for uranium dioxide samples, upto 700 0 C for sintered plutonium dioxide and negligible for sintered samples. The O/M ratios for non-stoichiometric uranium dioxide (sintered and unsintered), plutonium dioxide and mixed uranium and plutonium oxides (sintered) could be obtained with a precision of +- 0.002. Two reference states UOsub(2.000) and UOsub(2.656) were obtained for uranium dioxide and the reference state MOsub(2.000) was used for other cases. For unsintered plutonium dioxide samples, accurate O/M ratios could not be obtained of overlap of moisture loss with oxygen loss/gain. (author)

The plutonium challenge for the future

International Nuclear Information System (INIS)

Gray, L.W.

2000-01-01

In this paper author deal with the weapons-usable plutonium and with the possibilities of their managing. Russia has not disclosed the amount of plutonium produced, but various estimates indicate that the production was about 130 tonnes. Production has been curtailed in Russia; three dual-purpose reactors still produce weapons-grade plutonium - two at Tomsk-7 (renamed Seversk) and one at Krasnoyarsk-26 (renamed Zheleznogorsk Mining and Chemical Combine). In a 1994 United States-Russian agreement that has yet to enter into force, Russia agreed to close the remaining operating reactors by the year 2000. Treaties between the United States and Russia have already cut the number of nuclear warheads from more than 10,000 to about 6,000 under START 1, which has been ratified, and to about 3,500 under START 2, which still awaits approval. If Russia and the United States conclude START 3, that number could drop to between 2,000 and 2,500. On September 2, 1998, the Presidents of the United States and Russia signed the 'Joint statement of principles for Management and Disposition of Plutonium, Designated as No Longer Required for Defense Purposes.' In this joint statement the Presidents affirm the intention of each country to remove by stages approximately 50 metric tons of plutonium and to convert the nuclear weapons programs, and to convert this material so that it can never be used in nuclear weapons. These 100 tonne of plutonium must be managed in proper way such that it becomes neither a proliferation for an environmental risk. The United States has proposed that it manage it's 50 tonnes by a dual approach-once through MOX burning of a portion of the plutonium and immobilization in a ceramic matrix followed by en- casement in high level waste glass. Russia has proposed that it manage its full 50 tonnes by burning in a reactor. The MOX program in the United States would bum the cleaner plutonium metal and residues. Weapons components would be converted to plutonium oxide

Air quality III - experiments on emission and sensory perception of olfactory substances from ventilation systems. Final report; Luftqualitaet III - Experimentelle Untersuchungen zur Emission und Wahrnehmung von Geruchsstoffen aus Lueftungsgeraeten. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Fitzner, K.; Boettcher, O.

2001-08-01

Room air quality is highly important in Germany as people living here will spend 90 percent of their lives inside rooms. Air quality is defined to a large extent via the nose. This research project, in continuation of AiF 10525, involved investigations of materials and components of space HVAC systems with varying air temperatures, humidities and air flow rates for a subjective assessment of the air quality. The main goals were the definition of laws for identification of odorants and the derivation of laws for calculating pollutant-level-dependent ambient air rates for mechanically ventilated rooms. The experiments showed that both adsorption and desorption had a significant part in the addition of odorangs, causing deviations between theoretical and experimental values of felt air quality. The temperature and the relative humidity had an effect as well. Most measurements were made near the olfactory threshold, so that a number of participants were unable to complete the test. Later investigations will rely on analytical methods in addition to test persons. (orig.) [German] Das Thema der Luftqualitaet in Innenraeumen hat in Deutschland grosse Bedeutung, da sich die Bevoelkerung zu 90 Prozent ihres Lebens in Innenraeumen aufhaelt. Die Behaglichkeit der Atemluft wird in grossem Masse durch die mit der Nase wahrgenommenen Bestandteile der Luft beeinflusst. In Fortsetzung zum Forschungsvorhaben AiF 10525 wurden in diesem Forschungsvorhaben Untersuchungen mit Materialien und Komponenten aus RLT-Anlagen unter Veraenderung von Lufttemperatur, Luftfeuchte und Luftgeschwindigkeit zur subjektiven Beurteilung der Luftqualitaet durchgefuehrt. Die Hauptziele dieser Untersuchungen waren das Auffinden der Gesetzmaessigkeiten zur Wahrnehmung von Geruchsstoffen und das Ableiten von Rechenregeln zur Bestimmung verunreinigungslastabhaengiger Aussenluftraten fuer maschinell belueftete Raeume. Die Versuche zeigten, dass Adsorption und Desorption bei der Addition von Geruchsstoffen

Method to manufacture a nuclear fuel from uranium-plutonium monocarbide or uranium-plutonium mononitride

International Nuclear Information System (INIS)

Krauth, A.; Mueller, N.

1977-01-01

Pure uranium carbide or nitride is converted with plutonium oxide and carbon (all in powder form) to uranium-plutonium monocarbide or mononitride by cold pressing and sintering at about 1600 0 C. Pure uranium carbide or uranium nitride powder is firstly prepared without extensive safety measures. The pure uranium carbide or nitride powder can also be inactivated by using chemical substances (e.g. stearic acid) and be handled in air. The sinterable uranium carbide or nitride powder (or also granulate) is then introduced into the plutonium line and mixed with a nonstoichiometrically adjusted, prereacted mixture of plutonium oxide and carbon, pressed to pellets and reaction sintered. The surface of the uranium-plutonium carbide (higher metal content) can be nitrated towards the end of the sinter process in a stream of nitrogen. The protective layer stabilizes the carbide against the water and oxygen content in air. (IHOE) [de

Monitoring the risks of plutonium

International Nuclear Information System (INIS)

Holliday, B.

1978-01-01

The difficulties in monitoring the environment in work areas where plutonium is handled are identified and both continuous and personal air sampling techniques considered. Methods of estimating the amounts of plutonium retained in the body are: (1) Direct external counting over the chest of the 'soft' low energy X-rays and gamma rays emitted by the plutonium deposited in the lungs. (2) Measuring plutonium excreted in urine. (3) Analysing faeces soon after a suspected contamination. Limitation of these techniques are discussed and it is shown that estimating the amount of plutonium in the body, or a specific organ, is extremely difficult, both because of the lack of sensitivity of the measuring techniques (especially chest scanning) and because of the problems in interpreting data, stemming from a lack of knowledge of crucial characteristics of the inhaled plutonium (such as particle size and solubility). Nevertheless it is felt that the judicious integration of all the options creates a level of certainty that no individual technique can possibly inspire. (U.K.)

Progress on plutonium stabilization

Energy Technology Data Exchange (ETDEWEB)

Hurt, D. [Defense Nuclear Facilities Safety Board, Washington, DC (United States)

1996-05-01

The Defense Nuclear Facilities Safety Board has safety oversight responsibility for most of the facilities where unstable forms of plutonium are being processed and packaged for interim storage. The Board has issued recommendations on plutonium stabilization and has has a considerable influence on DOE`s stabilization schedules and priorities. The Board has not made any recommendations on long-term plutonium disposition, although it may get more involved in the future if DOE develops plans to use defense nuclear facilities for disposition activities.

Progress on plutonium stabilization

International Nuclear Information System (INIS)

Hurt, D.

1996-01-01

The Defense Nuclear Facilities Safety Board has safety oversight responsibility for most of the facilities where unstable forms of plutonium are being processed and packaged for interim storage. The Board has issued recommendations on plutonium stabilization and has has a considerable influence on DOE's stabilization schedules and priorities. The Board has not made any recommendations on long-term plutonium disposition, although it may get more involved in the future if DOE develops plans to use defense nuclear facilities for disposition activities

Arbeitsgemeinschaft fuer die Reinhaltung der Elbe - multi-element analysis of water samples from the Elbe and selected tributaries; Arbeitsgemeinschaft fuer die Reinhaltung der Elbe - Multielementanalysen von Wasserproben der Elbe und ausgewaehlter Nebenfluesse. Laengsprofilbeprobung vom September 1997

Energy Technology Data Exchange (ETDEWEB)

Krueger, F.; Berger, H. [Umweltbehoerde Hamburg (Germany). Amt fuer Umweltschutz, Umweltuntersuchungen; Aulinger, A.; Stachel, B.; Reincke, H. [Wasserguetestelle Elbe, Hamburg (Germany)

2000-10-01

This special report focuses on measurements of elements whose scope goes far beyond the routine monitoring for metals. The present studies are intended to extend the existing knowledge on the pollution situation of the Elbe and certain of its tributaries as well as provide a basis for formulating future guidelines for action. The first step towards this goal is sampling by means of an helicopter. The sampling is followed by a very involved and costly analysis programme, accompanied by extensive quality assurance measures. This is the only way of reliably analysing a large number of elements occurring in extremely low concentrations. Once the data have been recorded the question arises how they are to be evaluated. What schemes are suitable for categorising a large number of elements measured in either the suspended matter or the water compartment? What elements are to be regarded as the result of anthropogenic influences and what are their respective background concentrations in the fluvial system under study? These questions are approached by means of statistical methods which permit identifying elemental patterns and pollution sources as well as optimising the selection of measuring points for future studies. [German] In diesem Sonderbericht steht die Bestimmung von Elementen, die in ihrem Umfang ueber die routinemaessig erfassten Metalle deutlich hinausgeht, im Vordergrund. Die vorliegenden Untersuchungen sollen das bereits vorhandene Wissen zur Beschreibung der Immissionssituation der Elbe und von bestimmten Nebenfluessen erweitern, verbunden mit der Moeglichkeit, zukuenftige Handlungsmaximen zu erarbeiten. Zur Erreichung dieses Ziels steht zu Beginn die Probenahme mit einem Helicopter. Im Anschluss an die Probenahme folgt eine sehr aufwendige und teure Analytik, die begleitet wird von umfassenden Massnahmen zur Qualitaetssicherung. Nur so ist es moeglich, eine grosse Vielzahl von Elementen in extrem niedrigen Konzentrationen sicher analysieren zu koennen. Sind

Excess Weapons Plutonium Immobilization in Russia

International Nuclear Information System (INIS)

Jardine, L.; Borisov, G.B.

2000-01-01

The joint goal of the Russian work is to establish a full-scale plutonium immobilization facility at a Russian industrial site by 2005. To achieve this requires that the necessary engineering and technical basis be developed in these Russian projects and the needed Russian approvals be obtained to conduct industrial-scale immobilization of plutonium-containing materials at a Russian industrial site by the 2005 date. This meeting and future work will provide the basis for joint decisions. Supporting R and D projects are being carried out at Russian Institutes that directly support the technical needs of Russian industrial sites to immobilize plutonium-containing materials. Special R and D on plutonium materials is also being carried out to support excess weapons disposition in Russia and the US, including nonproliferation studies of plutonium recovery from immobilization forms and accelerated radiation damage studies of the US-specified plutonium ceramic for immobilizing plutonium. This intriguing and extraordinary cooperation on certain aspects of the weapons plutonium problem is now progressing well and much work with plutonium has been completed in the past two years. Because much excellent and unique scientific and engineering technical work has now been completed in Russia in many aspects of plutonium immobilization, this meeting in St. Petersburg was both timely and necessary to summarize, review, and discuss these efforts among those who performed the actual work. The results of this meeting will help the US and Russia jointly define the future direction of the Russian plutonium immobilization program, and make it an even stronger and more integrated Russian program. The two objectives for the meeting were to: (1) Bring together the Russian organizations, experts, and managers performing the work into one place for four days to review and discuss their work with each other; and (2) Publish a meeting summary and a proceedings to compile reports of all the

Plutonium use - Present status and prospects

International Nuclear Information System (INIS)

Dievoet, J. van; Fossoul, E.; Jonckheere, E.; Bemden, E. van den

1977-01-01

The use of plutonium in thermal and fast reactors is a demonstrated, if not proven, technology. Moreover, plutonium is being produced in increasing quantities. Evaluation of this production on a world scale shows that it would be theoretically possible to construct numerous breeders and thus to make the best use of plutonium, while considerably reducing uranium consumption. This source of plutonium is nevertheless dependent on the reprocessing of irradiated fuel. Long delays in installing and adequate world reprocessing capacity are weakening the prospects for introducing breeders. Furthermore, the critical situation regarding reprocessing may delay the development of complementary reprocessing methods for fuels with a high plutonium content and high burnup. The recycling of plutonium is now a well-known technique and any objections to it hardly bear analysis. Utilization of plutonium offers an appreciable saving in terms of uranium and separative work units; and it can also be shown that immediate reprocessing of the recycling fuel is not essential for the economics of the concept. Temporary storage of recycled fuel is a particularly safe form of concentrating plutonium, namely in irradiated plutonium-bearing fuel assemblies. Finally, recycling offers such flexibility that it represents no obstacle to fuel management at power plants with light-water reactors. These strategic considerations imply that the technology of using plutonium for fabricating thermal or fast reactor fuels is both technically reliable and economically viable. The methods used in industrial facilities are fully reassuring in this respect. Although various unsolved problems exist, none seems likely to impede current developments, while the industrial experience gained has enabled the economics and reliability of the methods to be improved appreciably. Apart from the techno-economic aspects, the plutonium industry must face extremely important problems in connection with the safety of personnel

Plutonium recovery from carbonate wash solutions

International Nuclear Information System (INIS)

Gray, J.H.; Reif, D.J.; Chostner, D.F.; Holcomb, H.P.

1991-01-01

540Periodically higher than expected levels of plutonium are found in carbonate solutions used to wash second plutonium cycle solvent. The recent accumulation of plutonium in carbonate wash solutions has led to studies to determine the cause of that plutonium accumulation, to evaluate the quality of all canyon solvents, and to develop additional criteria needed to establish when solvent quality is acceptable. Solvent from three canyon solvent extraction cycles was used to evaluate technology required to measure tributyl phosphate (TBP) degradation products and was used to evaluate solvent quality criteria during the development of plutonium recovery processes. 1 fig

Solubility of plutonium from rumen contents of cattle grazing on plutonium-contaminated desert vegetation in in vitro bovine gastrointestinal fluids

International Nuclear Information System (INIS)

Barth, J.

1975-01-01

Rumen contents of cattle grazing on plutonium-contaminated desert vegetation at the Nevada Test Site were incubated in simulated bovine gastrointestinal fluids to study the alimentary solubility of plutonium. Trials were run during November 1973, and during February, May, July and August 1974. During the May and July trials, a large increase in plutonium solubility accompanied by a marked reduction in plutonium concentration of the rumen contents was observed concurrently with a reduction in intake of Eurotia lanata and an increase in the intake of Oryzopsis hymenoides or Sitanion jubatum. However, during the November, February, and August trials, comparatively high concentration of plutonium, but low plutonium solubility, was associated with high levels of Eurotia lanata in the rumen contents. Plutonium-238 was generally more soluble than plutonium-239 in these fluids. Ratios of the percentage of soluble plutonium-238 to the percentage of soluble plutonium-239 varied fro []1:1 to 18:1 on a radioactivity basis. (auth)

Plutonium metal burning facility

International Nuclear Information System (INIS)

Hausburg, D.E.; Leebl, R.G.

1977-01-01

A glove-box facility was designed to convert plutonium skull metal or unburned oxide to an oxide acceptable for plutonium recovery and purification. A discussion of the operation, safety aspects, and electrical schematics are included

Analytic determination of plutonium in the environment; Determination analytique du plutonium dans l'environnement

Energy Technology Data Exchange (ETDEWEB)

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

1967-07-01

The work described in this report was undertaken with a view to determining the plutonium content in the fall-out from nuclear explosions. In the first part are described in turn the importance of the problems due to the plutonium, the physico-chemical properties of the radioelement and the biological dangers which it presents. A detailed and critical analysis is made of the radio-toxicological determination of the plutonium as reported in the literature prior to this report. The second part consists in the presentation of a judicious choice of techniques making it possible to determine plutonium in air, rain-water, soils and ash. After a detailed description of the measurement equipment and the operational techniques which have been developed, a justification of these techniques is given with particular reference to their sensitivity and specificity. After a brief conclusion concerning the preceding chapters, the results are presented. These are then discussed in the ease of each element in which the plutonium has been determined. This discussion is concluded by a consideration of the importance of the occurrence of fall-out plutonium on problems relating to public health. From a consideration of 200 analyses carried out, it is concluded that the contribution of plutonium to the exposure of populations is still very small compared to that of natural radiation and that due to such fission products as strontium 90. The report includes 63 literature references, 26 figures and 11 tables. (author) [French] Les travaux decrits dans ce memoire ont ete entrepris et eflectues dans le but de mettre en evidence le plutonium des retombees radioactives consecutives aux explosions nucleaires. Dans la premiere partie nous etudions successivement l'importance des problemes poses par le plutonium puis les proprietes physicochimiques du radioelement et les dangers qu'il presente du point de vue biologique. Nous effectuons une analyse detaillee et critique des techniques

Solvent anode for plutonium purification

International Nuclear Information System (INIS)

Bowersox, D.F.; Fife, K.W.; Christensen, D.C.

1986-01-01

The purpose of this study is to develop a technique to allow complete oxidation of plutonium from the anode during plutonium electrorefining. This will eliminate the generation of a ''spent'' anode heel which requires further treatment for recovery. Our approach is to employ a solvent metal in the anode to provide a liquid anode pool throughout electrorefining. We use molten salts and metals in ceramic crucibles at 700 0 C. Our goal is to produce plutonium metal at 99.9% purity with oxidation and transfer of more than 98% of the impure plutonium feed metal from the anode into the salt and product phases. We have met these criteria in experiments on the 100 to 1000 g scale. We plan to scale our operations to 4 kg of feed plutonium and to optimize the process parameters

Design-Only Conceptual Design Report: Plutonium Immobilization Plant

International Nuclear Information System (INIS)

DiSabatino, A.; Loftus, D.

1999-01-01

This design-only conceptual design report was prepared to support a funding request by the Department of Energy Office of Fissile Materials Disposition for engineering and design of the Plutonium Immobilization Plant, which will be used to immobilize up to 50 tonnes of surplus plutonium. The siting for the Plutonium Immobilization Plant will be determined pursuant to the site-specific Surplus Plutonium Disposition Environmental Impact Statement in a Plutonium Deposition Record of Decision in early 1999. This document reflects a new facility using the preferred technology (ceramic immobilization using the can-in-canister approach) and the preferred site (at Savannah River). The Plutonium Immobilization Plant accepts plutonium from pit conversion and from non-pit sources and, through a ceramic immobilization process, converts the plutonium into mineral-like forms that are subsequently encapsulated within a large canister of high-level waste glass. The final immobilized product must make the plutonium as inherently unattractive and inaccessible for use in nuclear weapons as the plutonium in spent fuel from commercial reactors and must be suitable for geologic disposal. Plutonium immobilization at the Savannah River Site uses: (1) A new building, the Plutonium Immobilization Plant, which will convert non-pit surplus plutonium to an oxide form suitable for the immobilization process, immobilize plutonium in a titanate-based ceramic form, place cans of the plutonium-ceramic forms into magazines, and load the magazines into a canister; (2) The existing Defense Waste Processing Facility for the pouring of high-level waste glass into the canisters; and (3) The Actinide Packaging and Storage Facility to receive and store feed materials. The Plutonium Immobilization Plant uses existing Savannah River Site infra-structure for analytical laboratory services, waste handling, fire protection, training, and other support utilities and services. The Plutonium Immobilization Plant

Doença de von Willebrand e anestesia Enfermedad de von Willebrand y anestesia Von Willebrand's disease and anesthesia

Directory of Open Access Journals (Sweden)

Fabiano Timbó Barbosa

2007-06-01

Full Text Available JUSTIFICATIVA E OBJETIVOS: A doença de von Willebrand ocorre devido à mutação no cromossomo 12 e é caracterizada por deficiência qualitativa ou quantitativa do fator de von Willebrand. A diversidade de mutações leva ao aparecimento das mais variadas manifestações clínicas possibilitando a divisão dos pacientes em vários tipos e subtipos clínicos. A coagulopatia se manifesta basicamente através da disfunção plaquetária associada à diminuição dos níveis séricos do fator VIII coagulante. O objetivo dessa revisão foi mostrar os cuidados relacionados aos pacientes portadores da doença de von Willebrand durante o período perioperatório. CONTEÚDO: Foram definidas as características da doença de von Willebrand quanto à fisiopatologia, à classificação, ao diagnóstico laboratorial, ao tratamento atual e aos cuidados com o manuseio do paciente no período perioperatório. CONCLUSÕES: A doença de von Willebrand é o distúrbio hemorrágico hereditário mais comum, porém ela é subdiagnosticada pela complexidade da própria doença. A correta classificação do paciente, o uso apropriado da desmopressina e a transfusão do fator de von Willebrand são medidas fundamentais para a realização do procedimento anestésico bem-sucedido.JUSTIFICATIVA Y OBJETIVOS: La enfermedad de von Willebrand ocurre debido a la mutación en el cromosoma 12 y se caracteriza por la deficiencia cualitativa o cuantitativa del factor de von Willebrand. La diversidad de mutaciones conlleva al aparecimiento de las más variadas manifestaciones clínicas posibilitando la división de los pacientes en varios tipos y subtipos clínicos. La coagulopatía se manifiesta básicamente a través de la disfunción plaquetaria asociada con la disminución de los niveles séricos del factor VIII coagulante. El objetivo de esa revisión fue mostrar los cuidados relacionados con las pacientes portadoras de la enfermedad de von Willebrand durante el per

Plutonium isotopic measurements by gamma-ray spectroscopy

International Nuclear Information System (INIS)

Haas, F.X.; Lemming, J.F.

1976-01-01

A nondestructive technique is described for calculating plutonium-238, plutonium-240, plutonium-241 and americium-241 relative to plutonium-239 from measured peak areas in the high resolution gamma-ray spectra of solid plutonium samples. Gamma-ray attenuation effects were minimized by selecting sets of neighboring peaks in the spectrum whose components are due to the different isotopes. Since the detector efficiencies are approximately the same for adjacent peaks, the accuracy of the isotopic ratios is dependent on the half-lives, branching intensities, and measured peak areas. The data presented describe the results obtained by analyzing gamma-ray spectra in the energy region from 120 to 700 keV. Most of the data analyzed were obtained from plutonium material containing 6 percent plutonium-240. Sample weights varied from 0.25 g to approximately 1.2 kg. The methods were also applied to plutonium samples containing up to 23 percent plutonium-240 with weights of 0.25 to 200 g. Results obtained by gamma-ray spectroscopy are compared to chemical analyses of aliquots taken from the bulk samples

Bibliography on plutonium and its compounds; Bibliographie sur le plutonium et ses composes

Energy Technology Data Exchange (ETDEWEB)

Dirian, J; Choquet, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

Collection of bibliographical references on plutonium and its principal compounds from 1942 to end of 1957. (author) [French] Compilation de references bibliographiques sur le plutonium et ses principaux composes de 1942 a fin 1957. (auteur)

Plutonium speciation affected by environmental bacteria

International Nuclear Information System (INIS)

Neu, M.P.; Icopini, G.A.; Boukhalfa, H.

2005-01-01

Plutonium has no known biological utility, yet it has the potential to interact with bacterial cellular and extracellular structures that contain metal-binding groups, to interfere with the uptake and utilization of essential elements, and to alter cell metabolism. These interactions can transform plutonium from its most common forms, solid, mineral-adsorbed, or colloidal Pu(IV), to a variety of biogeochemical species that have much different physico-chemical properties. Organic acids that are extruded products of cell metabolism can solubilize plutonium and then enhance its environmental mobility, or in some cases facilitate plutonium transfer into cells. Phosphate- and carboxylate-rich polymers associated with cell walls can bind plutonium to form mobile biocolloids or Pu-laden biofilm/mineral solids. Bacterial membranes, proteins or redox agents can produce strongly reducing electrochemical zones and generate molecular Pu(III/IV) species or oxide particles. Alternatively, they can oxidize plutonium to form soluble Pu(V) or Pu(VI) complexes. This paper reviews research on plutonium-bacteria interactions and closely related studies on the biotransformation of uranium and other metals. (orig.)

Plutonium vulnerability issues at Hanford's Plutonium Finishing Plant

International Nuclear Information System (INIS)

Feldt, E.; Templeton, D.W.; Tholen, E.

1995-01-01

The Plutonium Finishing Plant (PFP) at the Hanford, Washington Site was operated to produce plutonium (Pu) metal and oxide for national defense purposes. Due to the production requirements and methods utilized to meet national needs and the abrupt shutdown of the plant in the late 1980s, the plant was left in a condition that poses a risk of radiation exposure to plant workers, of accidental radioactive material release to the environment, and of radiation exposure to the public. In early 1994, an Environmental Impact Statement (EIS) to determine the best methods for cleaning out and stabilizing Pu materials in the PFP was started. While the EIS is being prepared, a number of immediate actions have been completed or are underway to significantly reduce the greatest hazards in the PFP. Recently, increased attention his been paid to Pu risks at Department of Energy (DOE) facilities resulting in the Department-wide Plutonium Vulnerability Assessment and a recommendation by the Defense Nuclear Facilities Safety Board (DNFSB) for DOE to develop integrated plans for managing its nuclear materials

Physics of Plutonium Recycling in Thermal Reactors

International Nuclear Information System (INIS)

Kinchin, G.H.

1967-01-01

A substantial programme of experimental reactor physics work with plutonium fuels has been carried out in the UK; the purpose of this paper is to review the experimental and theoretical work, with emphasis on plutonium recycling in thermal reactors. Although the main incentive for some of the work may have been to study plutonium build-up in uranium-fuelled reactors, it is nevertheless relevant to plutonium recycling and no distinction is drawn between build-up and enrichment studies. A variety of techniques have been for determining reactivity, neutron spectrum and reaction rates in simple assemblies of plutonium-aluminium fuel with water, graphite and beryllia moderators. These experiments give confidence in the basic data and methods of calculation for near-homogeneous mixtures of plutonium and moderator. In the practical case of plutonium recycling it is necessary to confirm that satisfactory predictions can be made for heterogeneous lattices enriched with plutonium. In this field, experiments have been carried out with plutonium-uranium metal and oxide-cluster fuels in graphite-moderated lattices and in SGHW lattices, and the effects of 240 Pu have been studied by perturbation measurements with single fuel elements. The exponential and critical experiments have used tonne quantities of fuel with plutonium contents ranging from 0.25 to 1.2% and the perturbation experiments have extended both the range of plutonium contents and the range of isotopic compositions of plutonium. In addition to reactivity and reactivity coefficients, such as the temperature coefficients, attention has been concentrated on relative reaction rate distributions which provide evidence for variations of neutron spectrum. .Theoretical comparisons, together with similar comparisons for non-uniform lattices, establish the validity of methods of calculation which have been used to study the feasibility of plutonium recycling in thermal reactors. (author)

Physics of Plutonium Recycling in Thermal Reactors

Energy Technology Data Exchange (ETDEWEB)

Kinchin, G. H. [Atomic Energy Establishment, Winfrith, Dorchester, Dorset (United Kingdom)

1967-09-15

A substantial programme of experimental reactor physics work with plutonium fuels has been carried out in the UK; the purpose of this paper is to review the experimental and theoretical work, with emphasis on plutonium recycling in thermal reactors. Although the main incentive for some of the work may have been to study plutonium build-up in uranium-fuelled reactors, it is nevertheless relevant to plutonium recycling and no distinction is drawn between build-up and enrichment studies. A variety of techniques have been for determining reactivity, neutron spectrum and reaction rates in simple assemblies of plutonium-aluminium fuel with water, graphite and beryllia moderators. These experiments give confidence in the basic data and methods of calculation for near-homogeneous mixtures of plutonium and moderator. In the practical case of plutonium recycling it is necessary to confirm that satisfactory predictions can be made for heterogeneous lattices enriched with plutonium. In this field, experiments have been carried out with plutonium-uranium metal and oxide-cluster fuels in graphite-moderated lattices and in SGHW lattices, and the effects of {sup 240}Pu have been studied by perturbation measurements with single fuel elements. The exponential and critical experiments have used tonne quantities of fuel with plutonium contents ranging from 0.25 to 1.2% and the perturbation experiments have extended both the range of plutonium contents and the range of isotopic compositions of plutonium. In addition to reactivity and reactivity coefficients, such as the temperature coefficients, attention has been concentrated on relative reaction rate distributions which provide evidence for variations of neutron spectrum. .Theoretical comparisons, together with similar comparisons for non-uniform lattices, establish the validity of methods of calculation which have been used to study the feasibility of plutonium recycling in thermal reactors. (author)

Reservoir patterns of soot, organic particles, total carbon, soluble substances and aerosols (numbers and mass) in the droplet and interstitial phase of clouds; Reservoiraufteilung von Russ, organischen Bestandteilen, Gesamtkohlenstoff, loeslichen Substanzen und Aerosolpartikeln (Anzahl und Masse) in der Tropfen- und Zwischenraumphase von Wolken. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Wieprecht, W.; Acker, K.; Moeller, D.; Auel, R.; Hofmeister, J.; Kalass, D.

2002-07-01

The reservoir patterns of the constitutents of representative clouds over Germany were investigated for a better characterisation of their optical, microphysical and chemical properties. One of the key points of interest was the distribution of carbonaceous aerosol particles in the droplet and interstitial phase, which was to provide information on the role of absorbing (soot or BC) and organic carbon (OC) in cloud formation. Data about the effects of potential CCN on cloud characteristics and about the changes in aerosol particles induced by cloud processes are required as input for models of the chemical and climate effects of atmospheric aerosol. [German] Ziel des Projektes war eine moeglichst umfassende experimentelle Ermittlung der Reservoiraufteilung der Inhaltsstoffe repraesentativer Wolken ueber der Bundesrepublik Deutschland, um ihre optischen, mikrophysikalischen und chemischen Eigenschaften besser zu charakterisieren. Ein besonderer Schwerpunkt des Gesamtprojekts lag auf der Bestimmung der Verteilung kohlenstoffhaltiger Aerosolpartikel auf die Tropfen- und interstitielle Phase, um Aufschluesse ueber die Rolle von absorbierendem (Russ oder BC) und organischem Kohlenstoff (OC) bei der Wolkenbildung zu erhalten. Erkenntnisse sowohl ueber die Beeinflussung potentieller CCN auf Wolkeneigenschaften als auch ueber die Veraenderung der Aerosolpartikel durch Wolkenprozesse sind erforderlich als Eingangsdaten in entsprechende Modelle, um die chemischen und klimatischen Effekte des atmosphaerischen Aerosols zu bestimmen. (orig.)

In vivo measurement of Pb-210 in the skull for retrospective assessment of exposure to radon; Die in-vivo Messung von Pb-210 im Schaedel zur retrospektiven Bestimmung von Radon-Expositionen

Energy Technology Data Exchange (ETDEWEB)

Doerfel, H. [Forschungszentrum Karlsruhe GmbH (Germany). Hauptabteilung Sicherheit/Dosimetrie

1997-12-01

The study shows that the new HPGe detectors with a larger surface are significantly better in terms of results and performance than the Phoswich detectors hitherto used for in vivo measurement of Pb-210 in the human skull. The experimental evaluations indicate that smaller HPGe detectors likewise are better than the Phoswich detectors, but some additional studies are required for final evaluation of these instruments. (orig./CB) [Deutsch] Die Untersuchungen haben gezeigt, dass die neuen grossflaechigen HPGe-Detektoren wesentlich besser zur in-vivo Messung von Pb-210 im Skelett geeignet sind als die bisher eingesetzten Phoswich-Detektoren. Auch kleinere HPGe-Detektoren sind offenbar besser geeignet als Phoswich-Detektoren, allerdings sind hier noch einige ergaenzende Untersuchungen erforderlich. (orig./SR)

Cigarette smoke and plutonium

International Nuclear Information System (INIS)

Filipy, R.E.

1982-01-01

The major objective of this project is to obtain experimental data that are directly applicable to resolving the question of whether cigarette smokers are at greater risk than nonsmokers to potential health effects of inhaled plutonium. Progress was made on two fronts during the past year. The autoradiographic technique developed from detection of plutonium on the interior surface of pulmonary airways (Annual Report, 1978) has been adapted to routine use in examining tracheas and bronchi of rats. Also, dogs exposed to cigarette smoke for over a year after inhalation of plutonium were killed and necropsied

Plutonium inventories for stabilization and stabilized materials

Energy Technology Data Exchange (ETDEWEB)

Williams, A.K.

1996-05-01

The objective of the breakout session was to identify characteristics of materials containing plutonium, the need to stabilize these materials for storage, and plans to accomplish the stabilization activities. All current stabilization activities are driven by the Defense Nuclear Facilities Safety Board Recommendation 94-1 (May 26, 1994) and by the recently completed Plutonium ES&H Vulnerability Assessment (DOE-EH-0415). The Implementation Plan for accomplishing stabilization of plutonium-bearing residues in response to the Recommendation and the Assessment was published by DOE on February 28, 1995. This Implementation Plan (IP) commits to stabilizing problem materials within 3 years, and stabilizing all other materials within 8 years. The IP identifies approximately 20 metric tons of plutonium requiring stabilization and/or repackaging. A further breakdown shows this material to consist of 8.5 metric tons of plutonium metal and alloys, 5.5 metric tons of plutonium as oxide, and 6 metric tons of plutonium as residues. Stabilization of the metal and oxide categories containing greater than 50 weight percent plutonium is covered by DOE Standard {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides{close_quotes} December, 1994 (DOE-STD-3013-94). This standard establishes criteria for safe storage of stabilized plutonium metals and oxides for up to 50 years. Each of the DOE sites and contractors with large plutonium inventories has either started or is preparing to start stabilization activities to meet these criteria.

Interference from radon-thoron daughters in plutonium channel of a continuous plutonium-in-air monitor

International Nuclear Information System (INIS)

Pendharkar, K.A.; Krishnamony, S.

1983-01-01

This paper summarises the results of a study conducted to define the extent of interference from the daughter products of radon/thoron to the plutonium channel of a continuous plutonium-in-air monitor. The effect on the detection limits of the instrument due to chemical form (transportable or non-transportable) and isotopic composition of plutonium aerosol are briefly discussed. (author)

Compositions of airborne plutonium-bearing particles from a plutonium finishing operation

International Nuclear Information System (INIS)

Sanders, S.M. Jr.

1976-11-01

The elemental composition of 111 plutonium-bearing particles was determined (using an electron microprobe) as part of a program to investigate the origin and behavior of the long-lived transuranic radionuclides released from fuel reprocessing facilities at the Savannah River Plant. These particles, collected from wet-cabinet and room-air exhausts from the plutonium finishing operation (JB-Line), were between 0.4 and 36 μm in diameter. Ninety-nine of the particles were found to be aggregates of various minerals and metals, six were quartz, and six were small (less than 2-μm-diameter) pieces of iron oxide. Collectively, these particles contained less minerals and more metals than natural dusts contain. The metallic constituents included elements normally not found in dusts, e.g., chromium, nickel, copper, and zinc. Concentrations of aluminum and iron exceeded those normally found in minerals. Elemental concentrations in individual particles covered a wide range: one 2-μm-diameter particle contained 97 percent NiO, a 9-μm-diameter particle contained 72 percent Cr 2 O 3 . Although the particles were selected because they produced plutonium fission tracks, the plutonium concentration was too low to be estimated by microprobe analysis in all but a 1-μm-diameter particle. This plutonium-bearing particle contained 73 percent PuO 2 by weight in combination with Fe 2 O 3 and mica; its activity was estimated at 0.17 pCi of 239 Pu

Plutonium use - present status and perspectives

International Nuclear Information System (INIS)

Dievoet, J. van; Fossoul, E.; Jonckheere, E.; Bemden, E. van den

1977-01-01

Plutonium is being produced in increasing quantities in the so-called proven reactors, which are mostly of the light-water type. Evaluation of this production on a world scale shows that it would be theoretically possible to construct a large number of breeders and thus to make the best use of the intrinsic qualities of plutonium as a fissionable material, while considerably reducing the consumption of uranium. This source of plutonium is nevertheless dependent on an essential stage of the fuel cycle, namely reprocessing of irradiated fuel. The long delays in installing an adequate world reprocessing capacity are substantially weakening the prospects for the introduction of breeders. Furthermore, the critical situation as regards reprocessing may delay the development of complementary reprocessing methods for fuels with a high plutonium content and high burn-up. When it is recalled that fast reactors themselves may suffer some delay in their technological development, if only because of the intention to build power plants of very high unit capacity immediately, it must be concluded that another use will have to be considered for the plutonium available in future -use in thermal reactors, i.e. recycling. The recycling of plutonium is a well-known technique today and the objections which could be raised against it hardly stand up to analysis. Utilization of plutonium offers an appreciable saving in terms of uranium and separative work units, the consumption being of a low order of magnitude in comparison with the total amount of plutonium needed for the eventual fabrication of the first fast reactor cores. It can also be shown that immediate reprocessing of the recycling fuel is not essential for the economics of the concept. Temporary storage of recycled fuel has the advantage of concentrating plutonium in a particularly safe form, namely in irradiated plutonium-bearing fuel assemblies. Lastly, recycling offers such flexibility that it does not in practice represent

Plutonium biokinetics in humans

International Nuclear Information System (INIS)

Popplewell, D.; Ham, G.; McCarthy, W.; Lands, C.

1994-01-01

By using an 'unusual' isotope it is possible to carry out experiments with plutonium in volunteers at minimal radiation dose levels. Measurements have been made of the gut transfer factor and the urinary excretion of plutonium after intravenous injection. (author)

Cigarette smoke and plutonium

International Nuclear Information System (INIS)

Anon.

1981-01-01

The overall objective of this study is to determine whether cigarette smoking increases the probability of plutonium-induced lung cancer. Initial experiments, designed to characterize the effect of chronic cigarette smoke exposure on pulmonary clearance of plutonium aerosols, are described

Polarographic study of the electrochemical properties of plutonium; Etude polarographique des proprietes electrochimiques du plutonium

Energy Technology Data Exchange (ETDEWEB)

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

1968-07-01

The behaviour of the different degrees of oxidation of plutonium have been studied using a falling drop mercury electrode in a non-complexing medium: dilute perchloric acid. In this medium it is possible to carry out the polarographic determination of plutonium using the reduction step situated at - 0.54 V/ECS which corresponds to the passage from the degree of oxidation(V) to the degree(III). The modifications brought about by a complexing ion, acetate, are then observed and interpreted. The existence of two plutonium(IV) acetic complexes has been shown; one is a polymerized substance. (author) [French] Le comportement des differents degres d'oxydation du plutonium est etudie a l'electrode a gouttes de mercure dans un milieu non complexant: l'acide perchlorique dilue. Il est possible dans ce milieu d'effectuer le dosage polarographique du plutonium en utilisant la vague de reduction situee a - 0.54 V/ECS qui correspond au passage du degre d'oxydation(V) au degre(III). Les modifications apportees par un ion complexant, l'acetate, sont ensuite observees et interpretees. Deux complexes acetiques du plutonium(IV) ont ete mis en evidence, dont l'un est un compose polymerise. (auteur)

Über die normativen Implikationen des Ordoliberalismus für die moderne Wirtschaftsethik

OpenAIRE

Klump, Rainer; Wörsdörfer, Manuel

2009-01-01

"Bei der Rezeption der ordoliberalen Freiburger Schule wurde bislang die wirtschaftsethische Perspektive weitgehend vernachlässigt. Der Aufsatz gibt vertiefte Einblicke in das ethisch-normative Denken des Ordoliberalismus am Beispiel des Werkes von Walter Eucken. Dabei wird es neben der Bestimmung der Sozialen Marktwirtschaft als funktionsfähige und menschenwürdige Ordnung um Euckens an Kant angelehntes Freiheitsverständnis gehen sowie um eine Einordnung Euckens in die moderne Wirtschafts- un...

Plutonium working group report on environmental, safety and health vulnerabilities associated with the Department's plutonium storage. Volume I: Summary

International Nuclear Information System (INIS)

1994-11-01

At the conclusion of the Cold War, the Department of Energy (DOE) stopped plutonium processing for nuclear weapons production. Facilities used for that purpose now hold significant quantities of plutonium in various forms. Unless properly stored and handled, plutonium can present environment, safety and health (ES ampersand H) hazards. Improperly stored plutonium poses a variety of hazards. When containers or packaging fail to fully protect plutonium metal from exposure to air, oxidation can occur and cause packaging failures and personnel contamination. Contamination can also result when plutonium solutions leak from bottles, tanks or piping. Plutonium in the form of scrap or residues generated by weapons production are often very corrosive, chemically reactive and difficult to contain. Buildings and equipment that are aging, poorly maintained or of obsolete design contribute to the overall problem. Inadvertent accumulations of plutonium of any form in sufficient quantities within facilities can result in nuclear criticality events that could emit large amounts of radiation locally. Contamination events and precursors of criticality events are causing safety and health concerns for workers at the Department's plutonium facilities. Contamination events also potentially threaten the public and the surrounding environment

Search for plutonium salt deposits in the plutonium extraction batteries of the Marcoule plant (1963); Recherche de depots de sels de plutonium dans les batteries d'extraction du plutonium de l'usine de Marcoule (1963)

Energy Technology Data Exchange (ETDEWEB)

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

1963-07-01

This report describes a method and a special apparatus making it possible to detach the insoluble plutonium salt deposits in the extraction chain of an irradiated fuel treatment plant. The process chosen allows the detection, in the extraction batteries or in the highly active chemical engineering equipment, of plutonium quantities of a few grains. After four years operation it has been impossible to detect measurable quantities of plutonium in any part of the extraction chain. The results have been confirmed by visual examinations carried out with a specially constructed endoscope. (authors) [French] Ce rapport decrit une methode et un montage special permettant de detacher les accumulations de sels de plutonium insolubles dans les chaines d'extraction d'une usine de traitement de combustible irradie. Le procede retenu permet de reperer, dans des batteries d'extraction ou dans l'appareillage de genie chimique fortement actif, des masses de plutonium de quelques grammes. Apres quatre annees de fonctionnement, il n'a pas ete possible de deceler des quantites ponderables de plutonium en aucun endroit de la chaine d'extraction. Ces resultats ont ete confirmes par les examens visuels effectues a l'aide d'un endoscope concu specialement pour cet usage. (auteurs)

A World made of Plutonium?

International Nuclear Information System (INIS)

Broda, E.

1976-01-01

This lecture by Engelbert Broda was written for the 26th Pugwash Conference in Mühlhausen, Germany, 26 – 31 August 1976: Public doubts about nuclear energy are generally directed at the problems of routine emissions of radionuclides, of catastrophic accidents, and of terminal waste disposal. Curiously, the most important problem is not being given sufficient attention: The use of plutonium from civilian reactors fpr weapons production. According to current ideas about a nuclear future, 5000 tons (order of magnitude) of plutonium are to be made annually by year 2000, and about 10 000 tons will all the time be in circulation (transport, reprocessing, reproduction of fuel elements, etc.). It is a misconception that plutonium from power reactors is unsuitable as a nuclear explosive. 5000 tons are enough for several hundred thousand (!) of bombs, Nagasaki type. By the year 2000 maybe 40 – 50 countries will have home-made plutonium. Plutonium production and proliferation are the most serious problems in a nuclear world. (author)

Using Biomolecules to Separate Plutonium

Science.gov (United States)

Gogolski, Jarrod

Used nuclear fuel has traditionally been treated through chemical separations of the radionuclides for recycle or disposal. This research considers a biological approach to such separations based on a series of complex and interdependent interactions that occur naturally in the human body with plutonium. These biological interactions are mediated by the proteins serum transferrin and the transferrin receptor. Transferrin to plutonium in vivo and can deposit plutonium into cells after interacting with the transferrin receptor protein at the cell surface. Using cerium as a non-radioactive surrogate for plutonium, it was found that cerium(IV) required multiple synergistic anions to bind in the N-lobe of the bilobal transferrin protein, creating a conformation of the cerium-loaded protein that would be unable to interact with the transferrin receptor protein to achieve a separation. The behavior of cerium binding to transferrin has contributed to understanding how plutonium(IV)-transferrin interacts in vivo and in biological separations.

Continuous precipitation process of plutonium salts; Procede continu de precipitation des sels de plutonium

Energy Technology Data Exchange (ETDEWEB)

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

1967-03-01

This work concerns the continuous precipitation process of plutonium oxalate. Investigations about the solubility of different valence states in nitric-oxalic and in nitric-sulfuric-oxalic medium lead to select the precipitation process of tetravalent plutonium oxalate. Settling velocity and granulometry of tetravalent oxalate plutonium have been studied with variation of several precipitation parameters such as: temperature, acidity, excess of oxalic acid and aging time. Then are given test results of some laboratory continuous apparatus. Conditions of operation with adopted tubular apparatus are defined in conclusion. A flow-sheet is given for a process at industrial scale. (author) [French] Cette etude porte sur la precipitation continue de l'oxalate de plutonium. L'etude de la solubilite des differentes valences du plutonium dans des milieux acides nitrique-oxalique, puis nitrique-sulfurique-oxalique conduit a choisir la precipitation de l'oxalate de plutonium tetravalent. L'etude porte ensuite sur la sedimentation et la granulometrie de l'oxalate de Pu{sup 4+} obtenue en faisant varier differents parametres de la precipitation : la temperature, l'acidite, l'exces oxalique et le temps de murissement. La derniere partie traite des resultats obtenus avec plusieurs types d'appareils continus essayes au laboratoire. En conclusion sont donnees les conditions de marche de l'appareil tubulaire adopte, ainsi qu'une extrapolation a l'echelle industrielle sous forme d'un flow-sheet. (auteur)

Plutonium helps probe protein, superconductor

International Nuclear Information System (INIS)

Anon.

1990-01-01

Scientists are finding that plutonium can be a useful research tool that may help them answer important questions in fields as diverse as biochemistry and solid-state physics. This paper reports that U.S. research involving plutonium is confined to the Department of Energy's national laboratories and centers around nuclear weapons technology, waste cleanup and disposal, and health effects. But at Los Alamos National Laboratory, scientists also are using plutonium to probe the biochemical behavior of calmodulin, a key calcium-binding protein that mediates calcium-regulated processes in biological systems. At Argonne National Laboratory, another team is trying to learn how a superconductor's properties are affected by the 5f electrons of an actinide like plutonium

Technological alternatives for plutonium transport

International Nuclear Information System (INIS)

1978-12-01

This paper considers alternative transport modes (air, sea, road, rail) for moving (1) plutonium from a reprocessing plant to a store or a fuel fabrication facility, and (2) MOX fuel from the latter to a reactor. These transport modes and differing forms of plutonium are considered in terms of: their proliferation resistance and safeguards; environmental and safety aspects; and economic aspects. It is tentatively proposed that the transport of plutonium could continue by air or sea where long distances are involved and by road or rail over shorter distances; this would be acceptable from the non-proliferation, environmental impact and economic aspects - there may be advantages in protection if plutonium is transported in the form of mixed oxide

Gamma spectrometric methods for measuring plutonium

International Nuclear Information System (INIS)

Gunnink, R.

1978-01-01

Nondestructive analyses of plutonium can be made by detecting and measuring the gamma rays emitted by a sample. Although qualitative and semiquantitative assays can be performed with relative ease, only recently have methods been developed, using computer analysis techniques, that provide quantitative results. This paper reviews some new techniques developed for measuring plutonium. The features of plutonium gamma-ray spectra are reviewed and some of the computer methods used for spectrum analysis are discussed. The discussion includes a description of a powerful computer method of unfolding complex peak multiplets that uses the standard linear least-squares techniques of data analysis. This computer method is based on the generation of response profiles for the isotopes composing a plutonium sample and requires a description of the peak positions, relative intensities, and line shapes. The principles that plutonium isotopic measurements are based on are also developed, followed by illustrations of the measurement procedures as applied to the quantitative analysis of plutonium liquid and solid samples

Plutonium

Energy Technology Data Exchange (ETDEWEB)

Miner, William N

1964-01-01

This pamphlet discusses plutonium from discovery to its production, separation, properties, fabrication, handling, and uses, including use as a reactor fuel and use in isotope power generators and neutron sources.

Plutonium Vulnerability Management Plan

International Nuclear Information System (INIS)

1995-03-01

This Plutonium Vulnerability Management Plan describes the Department of Energy's response to the vulnerabilities identified in the Plutonium Working Group Report which are a result of the cessation of nuclear weapons production. The responses contained in this document are only part of an overall, coordinated approach designed to enable the Department to accelerate conversion of all nuclear materials, including plutonium, to forms suitable for safe, interim storage. The overall actions being taken are discussed in detail in the Department's Implementation Plan in response to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1. This is included as Attachment B

Preparation of plutonium hexafluoride. Recovery of plutonium from waste dross (1962); Preparation de l'hexafluorure de plutonium. Recuperation du plutonium des scories d'elaboration (1962)

Energy Technology Data Exchange (ETDEWEB)

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

1962-07-01

The object of this work is to study the influence of various physical factors on the rate of fluorination of solid plutonium tetrafluoride by fluorine. In a horizontal oven with a circulation for pure fluorine at atmospheric pressure and 520 deg. C, at a fluorine rate of 9 litres/hour, it is possible to transform 3 g of tetrafluoride to hexafluoride with about 100 per cent transformation and a recovery yield of over 90 per cent, in 4 to 5 hours. The fluorination rate is a function of the temperature, of the fluorine flow-rate, of the crucible surface, of the depth of the tetrafluoride layer and of the reaction time. It does not depend on the diffusion of the fluorine into the solid but is determined by the reaction at the gas-solid interface and obeys the kinetic law (1 - T{sub T}){sup 1/3} = kt + 1. The existence of intermediate fluorides, in particular Pu{sub 4} F{sub 17}, is confirmed by a break in the Arrhenius plot at about 370 deg. C, by differences in the fluorination rates inside the tetrafluoride layer, and by reversible colour changes. The transformation to hexafluoride occurs with a purification with respect of the foreign elements present in the initial plutonium. Recovery of plutonium from waste dross: The study is based on the transformation of occluded plutonium particles to gaseous hexafluoride which is then decomposed thermally to the tetrafluoride which can be reintroduced directly in the production circuit. Under the conditions considered this process is not applicable industrially. After milling, it is possible to separate the dross into enriched (75 per cent Pu in 2.6 per cent by weight of dross) and depleted portions. By prolonged fluorination (16 hours) of the various fractions it is possible to recover about 80 per cent of the plutonium. A treatment plant using fluidization, as described at the end of this study, should make it possible to substantially improve the yield. (author) [French] L'objet de l'etude est l'influence des differents

Surplus plutonium disposition draft environmental impact statement. Summary

International Nuclear Information System (INIS)

1998-07-01

On May 22, 1997, DOE published a Notice of Intent (NOI) in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS). DOE's disposition strategy allows for both the immobilization of surplus plutonium and its use as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of the immobilized plutonium and MOX fuel (as spent nuclear fuel) in a geologic repository. The Surplus Plutonium Disposition Environmental Impact Statement analyzes alternatives that would use the immobilization approach (for some of the surplus plutonium) and the MOX fuel approach (for some of the surplus plutonium); alternatives that would immobilize all of the surplus plutonium; and the No Action Alternative. The alternatives include three disposition facilities that would be designed so that they could collectively accomplish disposition of up to 50 metric tons (55 tons) of surplus plutonium over their operating lives: (1) the pit disassembly and conversion facility would disassemble pits (a weapons component) and convert the recovered plutonium, as well as plutonium metal from other sources, into plutonium dioxide suitable for disposition; (2) the immobilization facility would include a collocated capability for converting nonpit plutonium materials into plutonium dioxide suitable for immobilization and would be located at either Hanford or SRS. DOE has identified SRS as the preferred site for an immobilization facility; (3) the MOX fuel fabrication facility would fabricate plutonium dioxide into MOX fuel

Modeling of Diffusion of Plutonium in Other Metals and of Gaseous Species in Plutonium-Based Systems

International Nuclear Information System (INIS)

Cooper, Bernard R.; Gayanath W. Fernando; Beiden, S.; Setty, A.; Sevilla, E.H.

2004-01-01

Establish standards for temperature conditions under which plutonium, uranium, or neptunium from nuclear wastes permeates steel, with which it is in contact, by diffusion processes. The primary focus is on plutonium because of the greater difficulties created by the peculiarities of face-centered-cubic-stabilized (delta) plutonium (the form used in the technology generating the waste)

Prospects for the Use of Plutonium in Reactors; Prospective d'Utilisation du Plutonium dans les Reacteurs

Energy Technology Data Exchange (ETDEWEB)

Fossoul, E.; Haubert, P. [BELGONUCLEAIRE (Belgium); Hirschberg, D.; Morlet, E. [International Business Machines of Belgium, Bruxelles (Belgium)

1967-09-15

The introduction, at an increasing rate, of power reactors using slightly enriched uranium will inevitably lead to the production of considerable quantities of plutonium over the next decade. Fast reactors will not be capable of absorbing this material before 1980. The question thus arises of whether one should store the plutonium far future use in fast reactors, recycle it in existing thermal reactors, or try to sell it. The problem has been studied for an electric power generating system that does not foresee selling the plutonium produced by its reactors and does not buy plutonium outside, which enables a good approximation to be made and eliminates the major unknown quantity represented by the future market price of plutonium. Assuming within this system a programme that provides for the construction of power reactors of a given type and capacity at specific dates, the utilization of the plutonium produced can be optimized by linear programming techniques so as to minimize the discounted total cost of the power generated over a given period. A later stage consists in optimizing, by various techniques, not only the utilization but also the production of plutonium by appropriate selection of the power reactor types to be constructed. (author) [French] L'implantation, a un rythme croissant, de centrales nucleaires a uranium legerement enrichi entrainera la production ineluctable d'une quantite importante de plutonium au cours de la prochaine decennie. Les reacteurs a neutrons rapides ne seront capables d'absorber cette production qu'apres 1980. La question se pose donc de savoir s'il est preferable de stocker le plutonium en vue de son utilisation ulterieure dans les reacteurs a neutrons rapides plutot que de le recycler dans les reacteurs actuels a neutrons thermiques ou d'essayer de le vendre. Ce probleme a ete etudie dans le cadre d'un systeme de production d'energie electrique qui ne prevoirait pas la vente du plutonium produit par ses reacteurs nucleaires ni

Radiological safety aspects of handling plutonium

International Nuclear Information System (INIS)

Sundararajan, A.R.

2016-01-01

Department of Atomic Energy in its scheme of harnessing the nuclear energy for electrical power generation and strategic applications has given a huge role to utilization of plutonium. In the power production programme, fast reactors with plutonium as fuel are expected to play a major role. This would require establishing fuel reprocessing plants to handle both thermal and fast reactor fuels. So in the nuclear fuel cycle facilities variety of chemical, metallurgical, mechanical operations have to be carried out involving significant inventories of "2"3"9 Pu and associated radionuclides. Plutonium is the most radiotoxic radionuclide and therefore any facility handling it has to be designed and operated with utmost care. Two problems of major concern in the protection of persons working in plutonium handling facilities are the internal exposure to the operating personnel from uptake of plutonium and transplutonic nuclides as they are highly radiotoxic and the radiation exposure of hands and eye lens during fuel fabrication operations especially while handling recycled high burn up plutonium. In view of the fact that annual limit for intake is very small for "2"3"9Pu and its radiation emission characteristics are such that it is a huge challenge for the health physicists to detect Pu in air and in workers. This paper discusses the principles and practices followed in providing radiological surveillance to workers in plutonium handling areas. The challenges in protecting the workers from receiving exposures to hands and eye lens in handling high burn up plutonium are also discussed. The sites having Pu fuel cycle facilities should have trained medical staff to handle cases involving excessive intake of plutonium. (author)

Plutonium-induced lymphadenitis in beagles

International Nuclear Information System (INIS)

Dagle, G.E.; Park, J.F.

1976-01-01

Plutonium oxide particles accumulate in the tracheobronchial lymph nodes of beagles exposed by inhalation and in the popliteal lymph nodes after subcutaneous injection in the hind paws. The sequence of histopathologic changes after phagocytosis of particles included necrosis, increased numbers of macrophages, and fibroplasia. Scar tissue eventually replaced the normal architecture of the lymph nodes and sequestered the plutonium particles from surrounding parenchyma. Electron microscopy showed that plutonium particles were aggregated in phagolysosomes of macrophages

Guidelines for international plutonium management: Overview and implications

International Nuclear Information System (INIS)

Bryson, M.C.; Fitzgerald, C.P.; Kincaid, C.

1998-01-01

In September, 1997, nine of the world's plutonium-using countries agreed to a set of guidelines for international plutonium management, with acceptances to be submitted to the International Atomic Energy Agency on December 1. Following three years of discussion, the guidelines provide a unified package of accepted rules for the storage, handling, and transportation of civil plutonium as well as military plutonium that has been declared as no longer required for defense purposes. New requirements include a formal declaration of national plutonium strategies, which will recognize the environmental, economic, and proliferation concerns and the consequent importance of balancing plutonium supply and demand. Nations will also make annual declaration of their non-military stockpiles of unirradiated plutonium, together with estimates of the plutonium content in spent reactor fuel. These guidelines represent the first formally accepted recognition of the need for plutonium management of this scope and could thus provide a partial basis for future monitoring and policy regimes

Six-kilogram-scale electrorefining of plutonium metal

International Nuclear Information System (INIS)

Mullins, L.J.; Morgan, A.N.; Apgar, S.A. III; Christensen, D.C.

1982-09-01

The electrorefining of metallic plutonium scrap to produce high purity metal has been an established procedure at Los Alamos since 1964. This is a batch process and was limited to 4-kg plutonium because of criticality safety considerations. Improvements in critical mass measurements have permitted us to develop a process for 6-kg plutonium. The 6-kg process is now operational. The increased size of the process, together with other improvements which have been made, makes plutonium electrorefining the principal industrial tool for processing and purifying metallic plutonium scrap

Erosional losses of fallout plutonium

International Nuclear Information System (INIS)

Foster, G.R.; Hakonson, T.E.

1987-01-01

Plutonium from fallout after atmospheric explosion of nuclear weapons in the 1950's and 1960s is being redistributed over the landscape by soil erosion and carried on sediment by streams to oceans. Erosion rates computed with the Universal Soil Loss Equation for more than 200,000 sample points on nonfederal land across the US were used to estimate plutonium removal rates by soil erosion. On the average, only about 4% of the eroded sediment reaches the outlet of a major river. The remaining sediment is deposited en route, and because deposition is a selective process, the sediment is enriched in fine particles having the highest concentration of plutonium because of the element's strong association with clay and silt-sized sediment. Estimated enrichment ratios, sediment delivery ratios, and erosion rates were used to estimate annual delivery of fallout plutonium. These estimates ranged from 0.002% of the initial fallout plutonium inventory for the Savannah River basin to 0.01% for the Columbia River basin, to 0.02% for the Hudson and Rio Grande River basins, to 0.08% for the Mississippi River basin. If the deposition of plutonium had been uniformly 1 mCi/km 2 , the estimated plutonium activity on suspended sediment would range from about 7 fCi/g of sediment of the Savannah River basin, to 9 fCi/g for the Mississippi River basin, to 12 fCi/g for the Hudson River basin, to 14 fCi/g for the Columbia and Rio Grande River basins. 45 references, 2 figures, 17 tables

Plutonium story

International Nuclear Information System (INIS)

Seaborg, G.T.

1981-09-01

The first nuclear synthesis and identification (i.e., the discovery) of the synthetic transuranium element plutonium (isotope 238 Pu) and the demonstration of its fissionability with slow neutrons (isotope 239 Pu) took place at the University of California, Berkeley, through the use of the 60-inch and 37-inch cyclotrons, in late 1940 and early 1941. This led to the development of industrial scale methods in secret work centered at the University of Chicago's Metallurgical Laboratory and the application of these methods to industrial scale production, at manufacturing plants in Tennessee and Washington, during the World War II years 1942 to 1945. The chemical properties of plutonium, needed to devise the procedures for its industrial scale production, were studied by tracer and ultramicrochemical methods during this period on an extraordinarily urgent basis. This work, and subsequent investigations on a worldwide basis, have made the properties of plutonium very well known. Its well studied electronic structure and chemical properties give it a very interesting position in the actinide series of inner transition elements

Plutonium research and related activities at the Amarillo National Resource Center for Plutonium

International Nuclear Information System (INIS)

Hartley, R.S.; Beard, C.A.; Barnes, D.L.

1998-01-01

With the end of the Cold War, the US and Russia are reducing their nuclear weapons stockpiles. What to do with the materials from thousands of excess nuclear weapons is an important international challenge. How to handle the remaining US stockpile to ensure safe storage and reliability, in light of the aging support infrastructure, is an important national challenge. To help address these challenges and related issues, the Amarillo National Resource Center for Plutonium is working on behalf of the State of Texas with the US Department of Energy (DOE). The center directs three major programs that address the key aspects of the plutonium management issue: (1) the Communications, Education, Training and Community Involvement Program, which focuses on informing the public about plutonium and providing technical education at all levels; (2) the Environmental, Safety, and Health (ES and H) Program, which investigates the key ES and H impacts of activities related to the DOE weapons complex in Texas; and (3) the Nuclear and Other Materials Program, which is aimed at minimizing safety and proliferation risks by helping to develop and advocate safe stewardship, storage, and disposition of nuclear weapons materials. This paper provides an overview of the center's nuclear activities described in four broad categories of international activities, materials safety, plutonium storage, and plutonium disposition

Determination of the neutron-induced fission cross section of {sup 242}Pu; Bestimmung des neutroneninduzierten Spaltquerschnitts von {sup 242}Pu

Energy Technology Data Exchange (ETDEWEB)

Koegler, Toni Joerg

2016-04-26

Neutron induced fission cross sections of actinides like the Pu-isotopes are of relevance for the development of nuclear transmutation technologies. For {sup 242}Pu, current uncertainties are of around 21%. Sensitivity studies show that the total uncertainty has to be reduced to below 5% to allow for reliable neutron physics simulations. This challenging task was performed at the neutron time-of-flight facility of the new German National Center for High Power Radiation Sources at HZDR, Dresden. Within the TRAKULA project, thin, large and homogeneous deposits of {sup 235}U and {sup 242}Pu have been produced successfully. Using two consecutively placed fission chambers allowed the determination of the neutron induced fission cross section of {sup 242}Pu relative to {sup 235}U. The areal density of the Plutonium targets was calculated using the measured spontaneous fission rate. Experimental results of the fast neutron induced fission of {sup 242}Pu acquired at nELBE will be presented and compared to recent experiments and evaluated data. Corrections addressing the neutron scattering are discussed by using results of different neutron transport simulations (Geant 4, MCNP 6 and FLUKA).

An Improved Plutonium Trifluoride Precipitation Flowsheet

Energy Technology Data Exchange (ETDEWEB)

Harmon, H.D.

2001-06-26

This report discusses results of the plutonium trifluoride two-stage precipitation study. A series of precipitation experiments was used to identify the significant process variables affecting precipitation performance. A mathematical model of the precipitation process was developed which is based on the formation of plutonium fluoride complexes. The precipitation model relates all process variables, in a single equation, to a single parameter which can be used to control the performance of the plutonium trifluoride precipitation process. Recommendations have been made which will optimize the FB-Line plutonium trifluoride precipitation process.

An Improved Plutonium Trifluoride Precipitation Flowsheet

International Nuclear Information System (INIS)

Harmon, H.D.

2001-01-01

This report discusses results of the plutonium trifluoride two-stage precipitation study. A series of precipitation experiments was used to identify the significant process variables affecting precipitation performance. A mathematical model of the precipitation process was developed which is based on the formation of plutonium fluoride complexes. The precipitation model relates all process variables, in a single equation, to a single parameter which can be used to control the performance of the plutonium trifluoride precipitation process. Recommendations have been made which will optimize the FB-Line plutonium trifluoride precipitation process

Plutonium valence state distributions

International Nuclear Information System (INIS)

Silver, G.L.

1974-01-01

A calculational method for ascertaining equilibrium valence state distributions of plutonium in acid solutions as a function of the plutonium oxidation number and the solution acidity is illustrated with an example. The method may be more practical for manual use than methods based upon polynomial equations. (T.G.)

PRISM reactor. An option for plutonium disposition?

Energy Technology Data Exchange (ETDEWEB)

Fehlinger, Sebastian; Friess, Friederike; Kuett, Moritz [IANUS, Technische Universitaet Darmstadt (Germany)

2015-07-01

The Power Reactor Innovative Small Module (PRISM) is sodium cooled fast reactor model. The energy output depends on the core configuration, however with an energy output of approximately 300 MWe, the PRISM reactor belongs to the class of small modular reactors. Beside using the reactor as a breeder reactor or for the transmutation of nuclear waste, it might also be used as a burner reactor for separated plutonium. This includes for example U.S.-American excess weapon-grade plutonium as well as separated reactor-grade plutonium. Recently, there has been an ongoing discussion in GB to use the PRISM reactor to dispose their excess civilian plutonium. Depending on the task, the core configuration varies slightly. We will present different layouts and the matching MCNP models, these models can then be used to conduct depletion calculations. From these results, analysis of the change in the plutonium isotopics in the spent fuel, the amount of fissioned plutonium, and the possible annual plutonium throughputs is possible.

The first milligrams of plutonium

International Nuclear Information System (INIS)

Goldschmidt, B.

1996-01-01

This paper relates the discovery of the different plutonium chemical extraction processes in their historical context. The first experiments started during the second world war in 1942 with the American ''Metallurgical Laboratory'' project which brought together Arthur Compton, Enrico Fermi and Glenn Seaborg. During the same period, a competitive English-Canadian project, the ''Montreal Project'', was carried out to test different plutonium solvent extraction techniques. The author participated in both projects and joined the CEA in 1946, where he was in charge of the uranium and plutonium chemistry. By the end of 1949, his team could isolate the first milligrams of French plutonium from uranium oxide pellets of the ZOE reactor. In the beginning of 1952 he developed with his team the PUREX process. (J.S.)

Chloride removal from plutonium alloy

International Nuclear Information System (INIS)

Holcomb, H.P.

1983-01-01

SRP is evaluating a program to recover plutonium from a metallic alloy that will contain chloride salt impurities. Removal of chloride to sufficiently low levels to prevent damaging corrosion to canyon equipment is feasible as a head-end step following dissolution. Silver nitrate and mercurous nitrate were each successfully used in laboratory tests to remove chloride from simulated alloy dissolver solution containing plutonium. Levels less than 10 ppM chloride were achieved in the supernates over the precipitated and centrifuged insoluble salts. Also, less than 0.05% loss of plutonium in the +3, +4, or +6 oxidation states was incurred via precipitate carrying. These results provide impetus for further study and development of a plant-scale process to recover plutonium from metal alloy at SRP

Gemeinsam hilfreich oder einsam lästig? Beurteilung von praktikumsbegleitenden Weblogs von angehenden Lehrpersonen

Directory of Open Access Journals (Sweden)

Nives Egger

2017-02-01

Full Text Available Weblogs werden an Hochschulen vermehrt zur Unterstützung von Lern- und Reflexionsprozessen eingesetzt, in der Lehrer/innenbildung auch zunehmend während der berufspraktischen Ausbildung. Die Studierenden beurteilen den Einsatz von Weblogs jedoch unterschiedlich. Dabei ist wenig bekannt, welchen Einfluss die Vergabe und das Erhalten von Peerfeedback auf den Beurteilungsprozess von praktikumsbegleitenden Weblogs sowie auf den Umfang von Blogpostings haben. Im folgenden Beitrag wird dieser Frage mittels einer Befragung von 74 angehenden Lehrpersonen nachgegangen, die praktikumsbegleitende Weblogs mit oder ohne Peerfeedback nutzten, um über herausfordernde Ereignisse im Praktikum zu reflektieren. Die Ergebnisse zeigen, dass Studierende, die Peerfeedback erhielten und andere Blogbeiträge kommentierten, den Weblogeinsatz nützlicher einschätzen sowie eine höhere Motivation und positivere Einstellung gegenüber den Einsatz von Weblogs aufweisen als Studierende, die ohne Peerfeedback bloggen. Keinen Einfluss hat Peerfeedback auf den Umfang der Blogbeiträge und auf die dafür aufgewendete Zeit.

Plutonium production and utilization forecasts in Europe

International Nuclear Information System (INIS)

Haijtink, B.

1976-01-01

The planned accelerated growth of nuclear energy generation in the near future will lead to a large production of plutonium in the thermal reactors. Therefore, up to 1985, the major part of the available plutonium will be plutonium recovered from spent uranium-metal, particularly in the United Kingdom and in France. Because of the low demand for fuelling the fast breeder reactors within the near future, a surplus of fissile plutonium will be accumulated in Europe. Even if the planned availability of the oxide reprocessing capacity will be delayed with two or three years, a plutonium surplus will still exist in Europe, e.g.; in 1985: 25-20 tons. On longer term, up to 2000, the plutonium production in thermal reactors will be sufficient to meet the estimated demand for fast breeder reactors at their commercial introduction foreseen for the nineties. That means that all the plutonium surplus needs not to be stocked for use in fast breeder reactors later on but could be recycled in thermal reactors. The magnitude of the available fissionable materials give an idea of the importance to promote, on an industrial scale, the plutonium recycling technology

Strategies for the plutonium utilization

International Nuclear Information System (INIS)

Zouain, D.M.; Lima, J.O.V.; Sakamoto, L.H.

1981-11-01

A review of the activities involving plutonium (its recycle, utilization and technological status and perspectives) is done. These informations are useful for an economic viability study for the plutonium utilization in thermal reactors (recycling) and in fast breeders reactor (FBR), trying to collect the major number of informations about these subjects. The initial phase describes the present status and projections of plutonium accumulation and requirements. Then, the technological process are described and some strategies are analyzed. (E.G.) [pt

Plutonium titration by controlled potential coulometry; Dosage du plutonium par coulometrie a potentiel impose

Energy Technology Data Exchange (ETDEWEB)

Leguay, N.

2011-07-01

The LAMMAN (Nuclear Materials Metrology Laboratory) is the support laboratory of the CETAMA (Analytical Method Committee), whose two main activities are developing analytic methods, and making and characterizing reference materials. The LAMMAN chose to develop the controlled potential coulometry because it is a very accurate analytical technique which allows the connection between the quantity of element electrolysed to the quantity of electricity measured thanks to the Faraday's law: it does not require the use of a chemical standard. This method was first used for the plutonium titration and was developed in the Materials Analysis and Metrology Laboratory (LAMM), for upgrading its performances and developing it to the titration of other actinides. The equipment and the material used were developed to allow the work in confined atmosphere (in a glove box), with all the restrictions involved. Plutonium standard solutions are used to qualify the method, and in particular to do titrations with an uncertainty better than 0.1 %. The present study allowed making a bibliographic research about controlled potential coulometry applied to the actinides (plutonium, uranium, neptunium, americium and curium). A full procedure was written to set all the steps of plutonium titration, from the preparation of samples to equipments storage. A method validation was done to check the full procedure, and the experimental conditions: working range, uncertainty, performance... Coulometric titration of the plutonium from pure solution (without interfering elements) was developed to the coulometric titration of the plutonium in presence of uranium, which allows to do accurate analyses for the analyses of some parts of the reprocessing of the spent nuclear fuel. The possibility of developing this method to other actinides than plutonium was highlighted thanks to voltammetric studies, like the coulometric titration of uranium with a working carbon electrode in sulphuric medium. (author)

Production of Plutonium Metal from Aqueous Solutions

Energy Technology Data Exchange (ETDEWEB)

Orth, D.A.

2003-01-16

The primary separation of plutonium from irradiated uranium by the Purex solvent extraction process at the Savannah River Plant produces a dilute plutonium solution containing residual fission products and uranium. A cation exchange process is used for concentration and further decontamination of the plutonium, as the first step in the final preparation of metal. This paper discusses the production of plutonium metal from the aqueous solutions.

Automation of plutonium spectrophotometry

International Nuclear Information System (INIS)

Perez, J.J.; Boisde, G.; Goujon de Beauvivier, M.; Chevalier, G.; Isaac, M.

1980-01-01

Instrumentation was designed and constructed for automatic control of plutonium by molecular absorption spectrophotometry, on behalf of the reprocessing facilities, to meet two objectives: on-line measurement, of the valency state of plutonium, on by-pass, with the measured concentration covering the process concentration range up to a few mg.l -1 ; laboratory measurement of plutonium adjusted to valency VI, with operation carried out using a preparative system meeting the required containment specifications. For this two objectives, the photometer, optical cell connections are made by optical fibers resistant to β, γ radiation. Except this characteristic the devices are different according to the quality required for result [fr

Civil plutonium amounts in the world

International Nuclear Information System (INIS)

Naudet, G.

1994-01-01

The experience of plutonium reprocessing in water reactors is positive and today the use of this nuclear fuel is at industrial level. Plutonium quantities in spent fuel go on increasing, plutonium stock coming from reprocessing can be controlled: according to conjuncture, it will evolve by stabilization or decreasing at the beginning of next century

Aggregation und Management von Metadaten im Kontext von Europeana

Directory of Open Access Journals (Sweden)

Gerda Koch

2017-09-01

Full Text Available Mit dem In-Beziehung-Setzen und Verlinken von Daten im Internet wird der Weg zur Umsetzung des semantischen Webs geebnet. Erst die semantische Verbindung von heterogenen Datenbeständen ermöglicht übergreifende Suchvorgänge und späteres „Machine Learning“. Im Artikel werden die Aktivitäten der Europäischen Digitalen Bibliothek im Bereich des Metadatenmanagements und der semantischen Verlinkung von Daten skizziert. Dabei wird einerseits ein kurzer Überblick zu aktuellen Forschungsschwerpunkten und Umsetzungsstrategien gegeben, und darüber hinaus werden einzelne Projekte und maßgeschneiderte Serviceangebote für naturhistorische Daten, regionale Kultureinrichtungen und Audiosammlungen beschrieben.

Geomorphology of plutonium in the Northern Rio Grande

Energy Technology Data Exchange (ETDEWEB)

Graf, W.L. [Arizona Univ., Tempe, AZ (United States). Dept., of Geography

1993-03-01

Nearly all of the plutonium in the natural environment of the Northern Rio Grande is associated with soils and sediment, and river processes account for most of the mobility of these materials. A composite regional budget for plutonium based on multi-decadal averages for sediment and plutonium movement shows that 90 percent of the plutonium moving into the system is from atmospheric fallout. The remaining 10 percent is from releases at Los Alamos. Annual variation in plutonium flux and storage exceeds 100 percent. The contribution to the plutonium budget from Los Alamos is associated with relatively coarse sediment which often behaves as bedload in the Rio Grande. Infusion of these materials into the main stream were largest in 1951, 1952, 1957, and 1968. Because of the schedule of delivery of plutonium to Los Alamos for experimentation and weapons manufacturing, the latter two years are probably the most important. Although the Los Alamos contribution to the entire plutonium budget was relatively small, in these four critical years it constituted 71--86 percent of the plutonium in bedload immediately downstream from Otowi.

Geomorphology of plutonium in the Northern Rio Grande

International Nuclear Information System (INIS)

Graf, W.L.

1993-03-01

Nearly all of the plutonium in the natural environment of the Northern Rio Grande is associated with soils and sediment, and river processes account for most of the mobility of these materials. A composite regional budget for plutonium based on multi-decadal averages for sediment and plutonium movement shows that 90 percent of the plutonium moving into the system is from atmospheric fallout. The remaining 10 percent is from releases at Los Alamos. Annual variation in plutonium flux and storage exceeds 100 percent. The contribution to the plutonium budget from Los Alamos is associated with relatively coarse sediment which often behaves as bedload in the Rio Grande. Infusion of these materials into the main stream were largest in 1951, 1952, 1957, and 1968. Because of the schedule of delivery of plutonium to Los Alamos for experimentation and weapons manufacturing, the latter two years are probably the most important. Although the Los Alamos contribution to the entire plutonium budget was relatively small, in these four critical years it constituted 71--86 percent of the plutonium in bedload immediately downstream from Otowi

Specification of a technically justified limiting value for sulphur concentrations in heating oil in order to enhance the use of high-efficiency boiler technology in oil heating systems; Ermittlung eines technisch begruendeten Grenzwertes fuer Schwefelgehalte im Heizoel zur Foerderung des Einsatzes von Brennwerttechnologie in Oelheizungsanlagen

Energy Technology Data Exchange (ETDEWEB)

Bellingen, E.-M.; Kuechen, C. [Institut fuer Wirtschaftliche Oelheizung e.V., Hamburg (Germany); Haase, F.; Wilckens, H. [Deutsche Shell AG, Hamburg (Germany); Sinnen, H.D. [VEBA AG, Duesseldorf (Germany)

2002-04-01

Different oil condensing boilers, which were available on the German market, have been investigated in order to determine the relevant limit for sulphur content in domestic heating oil. Up to now, the condensate from oil condensing boilers has to be neutralized in many cases due to local legislation. The composition of the condensates from oil boilers came out to be similar to the condensate from gas condensing boilers, as long as the sulphur content of heating oil is below 100 mg/kg. As the neutralization of condensate from gas condensing boilers is usually not required up to 200 kW-boilers, there should be no technical reason for neutralization, as long as the sulphur content is below 100 mg/kg. However, boiler manufactures are convinced, that only if the sulphur content is as low as 50 mg/kg, it will be possible to develop reliable oil condensing boilers for a reasonable price. Calculations of the total energy consumption came to the result, that primary energy can be saved. The increase of efficiency on the boiler side has more influence than the energy needed for desulphurization. (orig.) [German] Zur Bestimmung eines technisch begruendeten Schwefelgrenzwertes fuer ein neues 'schwefelarmes' Heizoel EL wurden Untersuchungen mit Heizoelen unterschiedlichen Schwefelgehaltes an verschiedenen auf dem Markt verfuegbaren Oelbrennwertgeraeten durchgefuehrt. Zur Zeit wird durch das ATV Arbeitsblatt A-251 eine Neutralisation von Kondensaten aus Oelbrennwertanlagen gefordert. Die Untersuchungen zeigen, dass bei Schwefelgehalten unter 100 mg/kg die Kondensate aehnliche Zusammensetzungen aufweisen wie Kondensate aus Gasbrennwertgeraeten. Die Voraussetzung fuer eine Befreiung von der Neutralisationsverpflichtung bei der Verwendung dieser Brennstoffe ist damit aus technischer Sicht gegeben. Fuer die Entwicklung von neuen, kompakten und preiswerten Oelbrennwertgeraeten wird von der Heizgeraeteindustrie ein Schwefelgehalt von max. 50 mg/kg fuer notwendig gehalten

Method of stripping plutonium from tributyl phosphate solution which contains dibutyl phosphate-plutonium stable complexes

International Nuclear Information System (INIS)

Ochsenfeld, W.; Schmieder, H.

1976-01-01

Fast breeder fuel elements which have been highly burnt-up are reprocessed by extracting uranium and plutonium into an organic solution containing tributyl phosphate. The tributyl phosphate degenerates at least partially into dibutyl phosphate and monobutyl phosphate, which form stable complexes with tetravalent plutonium in the organic solution. This tetravalent plutonium is released from its complexed state and stripped into aqueous phase by contacting the organic solution with an aqueous phase containing tetravalent uranium. 6 claims, 1 drawing figure

Experimental Studies on Plutonium Kinetics in Marine Biota

International Nuclear Information System (INIS)

Fowler, S.; Heyraud, M.; Beasley, T.M.

1976-01-01

Laboratory experiments were undertaken to measure plutonium flux through marine organisms and to clarify the pathways by which this important element is cycled in the marine environment. The use of a specially prepared isotope, plutonium-237, allowed measurements to be made with standard Nal(Tl) scintillation techniques. Mussels, shrimp and worms were allowed to accumulate plutonium-237 from sea water for up to 25 days. Accumulation by shrimp was relatively slow and the degree of uptake was strongly influenced by moulting. Cast moults contained large fractions of the shrimps ' plutonium content, indicating the high affinity of plutonium for surface areas. Only small amounts of the isotope in the moult are lost to water; hence, moulting is considered to be an important biological parameter in the biogeochemical cycling of plutonium. Mussels attained higher concentration factors than shrimp with most of the accumulated isotope (> 80%) located in the shell. Byssus threads often contained large fractions of the mussels' plutonium-237 content and reached concentration factors as high as 4100. Worms readily accumulated plutonium-237 in either the +4 or +6 state, reaching concentration factors of approximately 200, Retention studies indicated a relatively slow loss of plutonium-237 from all animals studied. In the case of mussels, a computed half-time for a large fraction of the animals plutonium content was of the order of 2 years. The more rapid loss from shrimp (Tb 1/2 = 1.5 months) was due principally to the large fraction of plutonium lost at moult. Food chain studies with shrimp indicated that tissue build-up via plutonium ingestion would be a slow process. Total excretion was not entirely a result of passing contaminated food through the gut; approximately 15% of the ingested plutonium was removed from the contaminated food and subsequently excreted by processes other than defaecation of labelled food. Ratios of four different plutonium isotopes used in

Experimental studies on plutonium kinetics in marine biota

International Nuclear Information System (INIS)

Fowler, S.; Heyraud, M.; Beasley, T.M.

1975-01-01

Laboratory experiments were undertaken to measure plutonium flux through marine organisms and to clarify the pathways by which this important element is cycled in the marine environment. The use of a specially prepared isotope, plutonium-237, allowed measurements to be made with standard NaI(Tl) scintillation techniques. Mussels, shrimp and worms were allowed to accumulate plutonium-237 from seawater for up to 25 days. Accumulation by shrimp was relatively slow and the degree of uptake was strongly influenced by moulting. Cast moults contained large fractions of the shrimps' plutonium content, indicating the high affinity of plutonium for surface areas. Only small amounts of the isotope in the moult are lost to water; hence, moulting is considered to be an important biological parameter in the biogeochemical cycling of plutonium. Mussels attained higher concentration factors than shrimp with most of the accumulated isotope (>80%) located in the shell. Byssus threads often contained large fractions of the mussels' plutonium-237 content and reached concentration factors as high as 4100. Worms readily accumulated plutonium-237 in either the +4 or +6 state, reaching concentration factors of approximately 200. Retention studies indicated a relatively slow loss of plutonium-237 from all animals studied. In the case of mussels, a computed half-time for a large fraction of the animals' plutonium content was of the order of 2 years. The more rapid loss from shrimp (Tbsub(1/2)=1.5 months) was due principally to the large fraction of plutonium lost at moult. Food chain studies with shrimp indicated that tissue build-up via plutonium ingestion would be a slow process. Total excretion was not entirely a result of passing contaminated food through the gut; approximately 15% of the ingested plutonium was removed from the contaminated food and subsequently excreted by processes other than defaecation of labelled food. Ratios of four different plutonium isotopes used in the

Specification analysis of plutonium fuels : a potentiometric method for the determination of plutonium

International Nuclear Information System (INIS)

Vaidyanathan, S.; Natarajan, P.R.

1977-01-01

A potentiometric method for the routine determination of plutonium in the specification analysis of plutonium fuels is described. Plutonium is oxidized to Pu(VI) with AgO and Pu(VI) is reduced with Fe(II) after the destruction of excess AgO with sulphamic acid. The excess Fe(II) is titrated potentiometrically against K 2 Cr 2 O 7 , the titration being carried out by adding a concentrated titrant solution from a weight burette and a suitably diluted solution from another weight burette near the end. The overall relative standard deviation obtained in 326 analyses of a working standard solution by eight experimenters is 0.14 percent. (author)

Von der Medienwirkungsbehauptung zur erziehungswissenschaftlichen Medienrezeptionsforschung. Vorschlag zur Analyse von Filmkommunikaten

Directory of Open Access Journals (Sweden)

Barbara Drinck

2001-04-01

Full Text Available Im Hinblick auf die Erforschung spezifischer Zusammenhänge von Medienkonsum und der Herausbildung von Einstellungen und Handlungen wird eine konstruktivistische Theorieorientierung plausibilisiert, indem zunächst auf den Stand der Medienwirkungsforschung eingegangen und vor dem Hintergrund einer begründeten Kritik des Wirkungsverständnisses auf die Notwendigkeit einer medienrezeptionswissenschaftlichen Forschungsalternative hingewiesen wird. Weiterhin wird der Stand der (erziehungswissenschaftlichen Medienrezeptionsforschung erörtert. Sodann werden Elemente einer konstruktivistischen Methodologie von Medienrezeptionsforschung beschrieben, die am Beispiel der Rezeption von Filmen konkretisiert werden. Dabei wird das Konzept des Kommunikates (S.J. Schmidt als Ausgangspunkt genommen, ein Vorschlag für eine Beschreibungssprache für (Film- Kommunikate entwickelt und eine Adaption des Ansatzes filmischer Narration zur Sprache gebracht.

Plutonium distribution in various components of natural organic matters and their role in plutonium migration in soils

Energy Technology Data Exchange (ETDEWEB)

Pavlotskaya, F.I.; Goryachenkova, T.A.

1987-09-01

The purpose of this work was to ascertain the links of plutonium with various components of the organic matter of different types of soils and their role in its migration in soils. The test objects were typical soils of forest and forest-steppe zones: sod-podzolic, gray forest, and leached chernozem contaminated with plutonium under laboratory conditions and stored in the air-dried state for three years, as also chernozem leached from an experimental site where agricultural plants were grown for a long time. The plutonium content in the fractions isolated from the contaminated soils was determined by its direct coprecipitation with microgram quantities of cerium hydroxide. The chemical yield of plutonium was determined by adding to a solution aliquot, equal to the analysis aliquot in volume, a known amount of plutonium and by its isolation under identical conditions. The ..gamma..-radiation of plutonium isolated on a nuclear filter with a pore size less than or equal to 15 ..mu..m was measured on a Protoka type gas flow counter.

Modification of the method of Figgie for determination of joint line shifting in total knee arthroplasty; Modifizierung der Messmethode nach Figgie zur Bestimmung der Gelenklinienverschiebung in der Knieendoprothetik

Energy Technology Data Exchange (ETDEWEB)

Classen, T.; Wegner, A.; Knoch, M. von [Universitaet Duisburg-Essen, Klinik fuer Orthopaedie, Essen (Germany)

2009-06-15

An important factor for a good result after total knee arthroplasty is the position of the patella in relation to the tibiofemoral joint line. The position of the patella itself is not influenced by arthroplasty, therefore any changes in the position of the tibiofemoral joint line are of special interest. The Figgie method to describe patella height delivers only absolute measurements, which makes it difficult to compare different radiographs. For this reason we developed a new JL/P quotient (JL: distance from the tibial plateau to the tibial tubercle, P: distance from the inferior pole of the patella to the tibial plateau) to enable better comparison. Furthermore, we modified the JL/P quotient and instead of taking the tibial plateau as the reference line, we constructed a tangent on the femoral condyle. With this modification, problems such as tibial inlays of different heights which have to be taken into account in the measurements, the slope of the tibial component or difficult assessment of the tibial joint surface in osteoarthritic knees do not arise. The JL/P quotient shows massive shift to cranialisation of the tibiofemoral joint line which does not correspond to reality. The modified method also shows cranialisation of the tibiofemoral joint line, but in a realistic way. Both methods show a minimal interobserver variability. The modified JL/P quotient seems to be a good method for determining the shift in the tibiofemoral joint line after total knee arthroplasty. (orig.) [German] Ein bedeutender Faktor fuer ein gutes postoperatives Ergebnis nach einer Knieendoprothesenimplantation ist die Stellung der Patella in Relation zur tibiofemoralen Gelenklinie. Da die Stellung der Patella durch den operativen Eingriff primaer nicht beeinflusst wird, liegt besonderes Augenmerk auf den Veraenderungen der Gelenklinie des Tibiofemoralgelenks. Die Messmethode zur Bestimmung der Patellahoehe nach Figgie liefert dafuer nur absolute Werte, was eine Vergleichbarkeit von

Electrochemistry of plutonium in molten halides

International Nuclear Information System (INIS)

McCurry, L.E.; Moy, G.M.M.; Bowersox, D.F.

1987-01-01

The electrochemistry of plutonium in molten halides is of technological importance as a method of purification of plutonium. Previous authors have reported that plutonium can be purified by electrorefining impure plutonium in various molten haldies. Work to eluciate the mechanism of the plutonium reduction in molten halides has been limited to a chronopotentiometric study in LiCl-KCl. Potentiometric studies have been carried out to determine the standard reduction potential for the plutonium (III) couple in various molten alkali metal halides. Initial cyclic voltammetric experiments were performed in molten KCL at 1100 K. A silver/silver chloride (10 mole %) in equimolar NaCl-KCl was used as a reference electrode. Working and counter electrodes were tungsten. The cell components and melt were contained in a quartz crucible. Background cyclic voltammograms of the KCl melt at the tungsten electrode showed no evidence of electroactive impurities in the melt. Plutonium was added to the melt as PuCl/sub 3/, which was prepared by chlorination of the oxide. At low concentrations of PuCl/sub 3/ in the melt (0.01-0.03 molar), no reduction wave due to the reduction of Pu(III) was observed in the voltammograms up to the potassium reduction limit of the melt. However on scan reversal after scanning into the potassium reduction limit a new oxidation wave was observed

The Plutonium Temperature Effect Experimental Program

Energy Technology Data Exchange (ETDEWEB)

Haeck, Wim; Leclaire, Nicolas; Letang, Eric [IRSN, Fontenay-aux-Roses (France); Girault, Emmanuel; Fouillaud, Patrick [CEA, VALDUC (France)

2008-07-01

Various theoretical studies have shown that highly diluted plutonium solutions could have a positive temperature effect but (up to now) no experimental program has confirmed this effect. The main goal of the French Plutonium Temperature Effect Experimental Program (or PU+ in short) is to effectively show that such a positive temperature effect exists for diluted plutonium solutions. The experiments were conducted in the 'Apparatus B' facility at the CEA Valduc research centre in France and involved several sub-critical approach type of experiments using plutonium nitrate solutions with concentrations of 14.3, 15 and 20 g/l at temperatures ranging from 20 to 40 deg. C. A total number of 14 phase I experiments (consisting of independent subcritical approaches) have been performed (5 at 20 g/l, 4 at 15 g/l and 5 at 14.3 g/l) between 2006 and 2007. The impact of the uncertainties on the solution acidity and the plutonium concentration makes it difficult to clearly demonstrate the positive temperature effect, requiring an additional phase II experiment (in which the use of the same plutonium solution was ensured) from 22 to 28 deg. C performed in July 2007. This experiment has shown the existence of a positive temperature effect approx +2 pcm/deg. C (from 22 to 28 deg. C for a plutonium concentration of 14.3 g/l). (authors)

The distribution of plutonium-241 in rodents

International Nuclear Information System (INIS)

Priest, N.D.

1977-01-01

Plutonium-241 citrate solution at pH 6.5 was injected intravenously or intraperitoneally into hamsters and rats at a dose of 50 MBq kg -1 (1.35 mCi kg -1 ). The animals were killed 1 day or 1 week later, and tissues were removed for autoradiography and radiochemical analysis. Plutonium-241 was distributed in rats in the same way as plutonium-239, and is a suitable isotope for high-resolution tissue-section autoradiography. Plutonium deposits in cells consisted of a nuclear and a cytoplasmic component. In the hamster kidney cells, the amount associated with the nucleus was about 55 per cent of the total cellular plutonium at 24 hours after injection. Six days later, it was only about 30 per cent. Plutonium deposits were also characterized in hepatocytes, in the interstitial cells of the testes, in the cells of ovarian follicles, in chondrocytes and in bone cells, including osteoblasts and osteocytes. In bone there appeared to be both an extracellular and intracellular deposit. No evidence was found of substantial incorporation of plutonium into the mineral phase of bone. (author)

Plutonium Speciation, Solubilization and Migration in Soils

International Nuclear Information System (INIS)

Neu, M.; Runde, W.

1999-01-01

This report summarizes research completed in the first half of a three-year project. As outlined in the authors' proposal they are focusing on (1) characterizing the plutonium at an actinide contaminated site, RFETS, including determining the origin, dispersion, and speciation of the plutonium, (2) studying environmentally important plutonium complexes, primarily hydroxides and carbonates, and (3) examining the interactions of plutonium species with manganese minerals. In the first year the authors focused on site based studies. This year they continue to characterize samples from the RFETS, study the formation and structural and spectroscopic features of environmentally relevant Pu species, and begin modeling the environmental behavior of plutonium

Vergleichende Einschätzung der diagnostischen Aussagekraft der Kenngrößen freies PSA, Alpha1-Antichymotrypsin-PSA und komplexiertes PSA in der Diagnostik des Prostatakarzinoms

OpenAIRE

Baumgart E; Deger S; Jung K; Lein M; Loening SA; Schnorr D

2001-01-01

Ziel der Studie war die vergleichende Einschätzung der diagnostischen Aussagekraft von Gesamt-PSA (tPSA), freiem PSA (fPSA), alpha1-Antichymotrypsin-PSA (ACT-PSA) und komplexiertem PSA (cPSA) sowie der entsprechenden Quotienten zur Differenzierung zwischen einem Prostatakarzinom (PCa) und einer Benignen Prostatahyperplasie (BPH). Die Bestimmung erfolgte bei insgesamt 324 Männern (PCa: n = 144; BPH: n = 89; Kontrollen: n = 91). Die tPSA- und cPSA-Konzentrationen wurden mit dem Bayer Immuno 1 S...

Recent trends of plutonium facilities and their control

Energy Technology Data Exchange (ETDEWEB)

Muto, T [Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works

1974-02-01

Much interest has been focussed on Pu recycle since the oil crisis because of an expected shortage of enriched uranium. Plutonium handling techniques and plutonium fuel fabricating facilities should be developed to meet the future demand of plutonium, but the radioactive property of plutonium to be reprocessed from spent fuel and recycled plutonium is remarkably different, and it has to be handled safely. Technical criteria for plutonium facilities are specified in the USAEC regulatory guides and other rules. Some of these criteria are location condition, quality of confinement, protection against accidents and so on. The control conditions for plutonium facilities are exposure control, criticality control, measurement control and new system of safeguard. These problems are under development to meet the future requirement for the safe handling of Pu material.

Plutonium Oxide Process Capability Work Plan

Energy Technology Data Exchange (ETDEWEB)

Meier, David E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Tingey, Joel M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2014-02-28

Pacific Northwest National Laboratory (PNNL) has been tasked to develop a Pilot-scale Plutonium-oxide Processing Unit (P3U) providing a flexible capability to produce 200g (Pu basis) samples of plutonium oxide using different chemical processes for use in identifying and validating nuclear forensics signatures associated with plutonium production. Materials produced can also be used as exercise and reference materials.

Weapons-grade plutonium dispositioning. Volume 1: Executive summary

International Nuclear Information System (INIS)

Parks, D.L.; Sauerbrun, T.J.

1993-06-01

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate dispositioning options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) assisted NAS in this evaluation by investigating the technical aspects of the dispositioning options and their capability for achieving plutonium annihilation levels greater than 90%. Additionally, the INEL investigated the feasibility of using plutonium fuels (without uranium) for disposal in existing light water reactors and provided a preconceptual analysis for a reactor specifically designed for destruction of weapons-grade plutonium. This four-volume report was prepared for NAS to document the findings of these studies. Volume 2 evaluates 12 plutonium dispositioning options. Volume 3 considers a concept for a low-temperature, low-pressure, low-power-density, low-coolant-flow-rate light water reactor that quickly destroys plutonium without using uranium or thorium. This reactor concept does not produce electricity and has no other mission than the destruction of plutonium. Volume 4 addresses neutronic performance, fabrication technology, and fuel performance and compatibility issues for zirconium-plutonium oxide fuels and aluminum-plutonium metallic fuels. This volumes gives summaries of Volumes 2--4

Long time contamination from plutonium

International Nuclear Information System (INIS)

Fueloep, M.; Patzeltova, N.; Ragan, P.; Matel, L.

1995-01-01

Plutonium isotopes in the organism of the patient (who had participated in the liquidation works after the Chernobyl accident; for three month he had stayed in the epicenter, where he acted as a chauffeur driving a radioactive material to the place of destination) from urine were determined. For determination of the concentration of Pu-239, Pu-240 in urine a modified radiochemical method was used. After mineralization the sample was separated as an anion-nitrate complex with contact by the anion form of the resin in the column. The resin was washed by 8 M HNO 3 , the 8 M HCl with 0.3 M HNO 3 for removing the other radionuclides. The solution 0.36 M HCl with 0.01 M HF was used for the elution of plutonium. Using the lanthanum fluoride technique the sample was filtrated through a membrane filter. The plutonium was detected in the dry sample. The Pu-239 tracer was used for the evaluation of the plutonium separation efficiency. The alpha spectrometric measurements were carried out with a large area silicon detector. The samples were measured and evaluated in the energy region 4.98-5.18 MeV. The detection limit of alpha spectrometry measurements has been 0.01 Bq dm -3 . The concentration of plutonium in the 24-hour urine was determined three times in the quarter year intervals. The results are: 54 mBq, 63.2 mBq, 53 mBq, with average 56,7 mBq. From the results of the analyses of plutonium depositions calculated according to ICRP 54 the intake of this radionuclide for the patient was 56.7 kBq. To estimate a committed effective dose (50 years) from the intake of plutonium was used a conversion factor 6.8.10 -5 Sv.Bq -1 (class W). So the expressed committed effective dose received from the plutonium intake is 3.8 Sv. This number is relatively high and all the effective dose will be higher, because the patient was exposed to the other radionuclides too. For example the determination of the rate radionuclides Am-241/Pu-239,Pu-240 was 32-36 % in the fallout after the Chernobyl

Plutonium gastrointestinal absorption by adults baboons

International Nuclear Information System (INIS)

Lataillade, G.; Madic, C.; Willemot, J.M.; Germain, P.; Colle, C.; Metivier, H.

1991-01-01

Gastrointestinal absorption of plutonium was investigated in baboons after ingestion of plutonium solution (oxidation states III; IV; V; VI), and plutonium incorporated in soya bean and winkles. We studied the effects of oxidation state and ingested mass for masses ranging from 0.35 μg to 51.6 x 10 +3 μg (4 x 10 -2 to 7776 μg of plutonium per kg of body weight). No clear increase in plutonium retention was shown for concentrations of plutonium smaller than 1 μg/kg. From 1 μg/kg to 1 mg/kg no effects of mass or oxidation state was observed and the mean fractional retention value was 10 -4 . For ingested masses higher than 1 mg/kg the fractional retention values respectively increased for Pu(V) and Pu(III) to (0.9 + 0.2) x 10 -2 and (7.4 + 4.1) x 10 -4 of the ingested mass. This increase might be due to the weak hydrolysis of these oxidation states which would increase gastrointestinal absorption by decrease of hydroxide formation. The fraction of plutonium retained after ingestion of soya bean was (3.0 + 0.5) x 10 -4 about 3 fold higher than the value for 238 Pu nitrate solution. No clear increase in plutonium retention was shown after ingestion of winkles containing 238 Pu. In conclusion, except for high masses of ingested Pu, the retention of which could reach 1% of the ingested dose, our results show that the gastrointestinal transfer factor of 10 -4 proposed by ICRP for gastrointestinal absorption of soluble form of Pu is acceptable, but 10 -3 would provide better safety margin [fr

Disposing of the world's excess plutonium

International Nuclear Information System (INIS)

McCormick, J.M.; Bullen, D.B.

1998-01-01

The authors undertake three key objectives in addressing the issue of plutonium disposition at the end of the Cold War. First, the authors estimate the total global inventory of plutonium both from weapons dismantlement and civil nuclear power reactors. Second, they review past and current policy toward handling this metal by the US, Russia, and other key countries. Third, they evaluate the feasibility of several options (but especially the vitrification and mixed oxide fuel options announced by the Clinton administration) for disposing of the increasing amounts of plutonium available today. To undertake this analysis, the authors consider both the political and scientific problems confronting policymakers in dealing with this global plutonium issue. Interview data with political and technical officials in Washington and at the International Atomic Energy Agency in Vienna, Austria, and empirical inventory data on plutonium from a variety of sources form the basis of their analysis

Neues über das Tertiär von Java und die mesozoischen Schichten von West-Borneo

NARCIS (Netherlands)

Martin, K.

1888-01-01

Die Monographie, welche unter dem Titel Die Fossilien von Java herausgegeben wird ¹), ist so weit fortgeschritten, dass sich aus den in ihr beschriebenen Gastropoden bereits eine Anzahl von Schlussfolgerungen ableiten lässt, welche für die in Bearbeitung begriffene, geologische Karte von Java von

Selecting a plutonium vitrification process

Energy Technology Data Exchange (ETDEWEB)

Jouan, A. [Centre d`Etudes de la Vallee du Rhone, Bagnols sur Ceze (France)

1996-05-01

Vitrification of plutonium is one means of mitigating its potential danger. This option is technically feasible, even if it is not the solution advocated in France. Two situations are possible, depending on whether or not the glass matrix also contains fission products; concentrations of up to 15% should be achievable for plutonium alone, whereas the upper limit is 3% in the presence of fission products. The French continuous vitrification process appears to be particularly suitable for plutonium vitrification: its capacity is compatible with the required throughout, and the compact dimensions of the process equipment prevent a criticality hazard. Preprocessing of plutonium metal, to convert it to PuO{sub 2} or to a nitric acid solution, may prove advantageous or even necessary depending on whether a dry or wet process is adopted. The process may involve a single step (vitrification of Pu or PuO{sub 2} mixed with glass frit) or may include a prior calcination step - notably if the plutonium is to be incorporated into a fission product glass. It is important to weigh the advantages and drawbacks of all the possible options in terms of feasibility, safety and cost-effectiveness.

Plutonium Disposition Now exclamation point

International Nuclear Information System (INIS)

Buckner, M.R.

1995-01-01

A means for use of existing processing facilities and reactors for plutonium disposition is described which requires a minimum capital investment and allows rapid implementation. The scenario includes interim storage and processing under IAEA control, and fabrication into MOX fuel in existing or planned facilities in Europe for use in operating reactors in the two home countries. Conceptual studies indicate that existing Westinghouse four-loop designs can safety dispose of 0.94 MT of plutonium per calendar year. Thus, it would be possible to consume the expected US excess stockpile of about 50 MT in two to three units of this type, and it is highly likely that a comparable amount of the FSU excess plutonium could be deposed of in a few VVER-1000's. The only major capital project for this mode of plutonium disposition would be the weapons-grade plutonium processing which could be done in a dedicated international facility or using existing facilities in the US and FSU under IAEA control. This option offers the potential for quick implementation at a very low cost to the governments of the two countries

Plutonium in depleted uranium penetrators

International Nuclear Information System (INIS)

McLaughlin, J.P.; Leon-Vintro, L.; Smith, K.; Mitchell, P.I.; Zunic, Z.S.

2002-01-01

Depleted Uranium (DU) penetrators used in the recent Balkan conflicts have been found to be contaminated with trace amounts of transuranic materials such as plutonium. This contamination is usually a consequence of DU fabrication being carried out in facilities also using uranium recycled from spent military and civilian nuclear reactor fuel. Specific activities of 239+240 Plutonium generally in the range 1 to 12 Bq/kg have been found to be present in DU penetrators recovered from the attack sites of the 1999 NATO bombardment of Kosovo. A DU penetrator recovered from a May 1999 attack site at Bratoselce in southern Serbia and analysed by University College Dublin was found to contain 43.7 +/- 1.9 Bq/kg of 239+240 Plutonium. This analysis is described. An account is also given of the general population radiation dose implications arising from both the DU itself and from the presence of plutonium in the penetrators. According to current dosimetric models, in all scenarios considered likely ,the dose from the plutonium is estimated to be much smaller than that due to the uranium isotopes present in the penetrators. (author)

Decontaminaion of metals containing plutonium and americium

International Nuclear Information System (INIS)

Seitz, M.G.; Gerding, T.J.; Steindler, M.J.

1979-06-01

Melt-slagging (melt-refining) techniques were evaluated as a decontamination and consolidation step for metals contaminated with oxides of plutonium and americium. Experiments were performed in which mild steel, stainless steel, and nickel contaminated with oxides of plutonium and americium were melted in the presence of silicate slags of various compositions. The metal products were low in contamination, with the plutonium and americium strongly fractionated to the slags. Partition coefficients (plutonium in slag/plutonium in steel) of 7 x 10 6 were measured with boro-silicate slag and of 3 x 10 6 with calcium, magnesium silicate slag. Decontamination of metals containing as much as 14,000 ppM plutonium appears to be as efficient as for metals with plutonium levels of 400 ppM. Staged extraction, that is, a remelting of processed metal with clean slag, results in further decontamination of the metal. The second extraction is effective with either resistance-furnace melting or electric-arc melting. Slag adhering to the metal ingots and in defects within the ingots is in the important contributors to plutonium retained in processed metals. If these sources of plutonium are controlled, the melt-refining process can be used on a large scale to convert highly contaminated metals to homogeneous and compact forms with very low concentrations of plutonium and americium. A conceptual design of a melt-refining process to decontaminate plutonium- and americium-contaminated metals is described. The process includes single-stage refining of contaminated metals to produce a metal product which would have less than 10 nCi/g of TRU-element contamination. Two plant sizes were considered. The smaller conceptual plant processes 77 kg of metal per 8-h period and may be portable.The larger one processes 140 kg of metal per 8-h period, is stationary, and may be near te maximum size that is practical for a metal decontamination process

Assay of low-level plutonium effluents

International Nuclear Information System (INIS)

Hsue, S.T.; Hsue, F.; Bowersox, D.F.

1981-01-01

In the plutonium recovery section at the Los Alamos National Laboratory, an effluent solution is generated that contains low plutonium concentration and relatively high americium concentration. Nondestructive assay of this solution is demonstrated by measuring the passive L x-rays following alpha decay. Preliminary results indicate that an average deviation of 30% between L x-ray and alpha counting can be achieved for plutonium concentrations above 10 mg/L and Am/Pu ratios of up to 3; for plutonium concentrations less than 10 mg/L, the average deviation is 40%. The sensitivity of the L x-ray assay is approx. 1 mg Pu/L

Light water breeder reactor using a uranium-plutonium cycle

International Nuclear Information System (INIS)

Radkowsky, A.; Chen, R.

1990-01-01

This patent describes a light water receptor (LWR) for breeding fissile material using a uranium-plutonium cycle. It comprises: a prebreeder section having plutonium fuel containing a Pu-241 component, the prebreeder section being operable to produce enriched plutonium having an increased Pu-241 component; and a breeder section for receiving the enriched plutonium from the prebreeder section, the breeder section being operable for breeding fissile material from the enriched plutonium fuel. This patent describes a method of operating a light water nuclear reactor (LWR) for breeding fissile material using a uranium-plutonium cycle. It comprises: operating the prebreeder to produce enriched plutonium fuel having an increased Pu-241 component; fueling a breeder section with the enriched plutonium fuel to breed the fissile material

Evaluation of the water hazard potential of solid wastes. Pt. 1. Experimental results; Untersuchung von Abfaellen mit biologischen Testverfahren zur Bewertung der Wassergefaehrdung. T. 1. Experimentelle Ergebnisse

Energy Technology Data Exchange (ETDEWEB)

Brackemann, H.; Hahn, J.; Vogel, U. [Umweltbundesamt, Berlin (Germany); Hagendorf, U. [Umweltbundesamt, Langen (Germany)

2000-07-01

Wastes from three different types of waste treatment facilities (slag from a municipal waste incineration plant, slag granules from a pilot plant combining carbonization and incineration, mechanical and biological treated wastes) were examined to determine their hazard potential to different waters sites. The process temperature is seen to be the main difference between the three treatment processes. The wastes were extracted with water according to the German standard DIN 38414 S 4 and additionally at a constant pH value of 4. The leachates were investigated in a battery of aquatic bioassays and characterised physically and chemically. Every leachate revealed in a toxic effect at least in one test. The toxicity of the leachates prepared at a pH of 4 was significantly higher than the toxicity of the leachates prepared by extraction with water without pH adjustment. The leachates of the slag granules showed the lowest toxicity. On the basis of these experimental results, a scheme to derive Water Hazard Classes of wastes, which is presented in part II of this publication, was developed. (orig.) [German] Zur Bestimmung der wassergefaehrdenden Eigenschaften wurden die Eluate von Abfaellen/Rueckstaenden aus drei verschiedenen Abfallbehandlungsanlagen untersucht (Schlacke aus einer Abfallverbrennungsanlage (Rostfeuerung), Schmelzgranulat aus einer Versuchsanlage mit kombinierter Verschwelung und Hochtemperaturverbrennung sowie biologisch-mechanisch behandelter Abfall). Ein wesentlicher Unterschied dieser drei Verfahren liegt in der Behandlungstemperatur. Die Rueckstaende wurden nach DIN 38414, Teil 4 sowie bei einem konstant eingestellten pH-Wert von 4 eluiert. Die Eluate wurden mit verschiedenen aquatischen Biotests untersucht sowie physikalisch-chemisch charakterisiert. Dabei zeigte sich, dass jedes untersuchte Eluat in mindestens einem Test eine toxische Wirkung aufwies; die Toxizitaet der bei saurem pH-Wert durchgefuehrten Elutionen war deutlich erhoeht. Die Eluate

The determination of plutonium isotopes in environmental samples

International Nuclear Information System (INIS)

Siripirom, Lopchai.

1983-01-01

The concentration of plutonium in environmental samples such as soil, water, and surface air in the middle part of Thailand were studied. The surface air were collected only at the fifth floor of the Office of Atomic Energy for Peace (OAEP). Plutonium-242 was used as a tracer. Soil and air samples were dissolved by pyrosulphate fusion, and plutonium was co-precipitated with barium sulfate. Then dissolved the precipitate in perchloric acid. Plutonium was extracted out by using solvent bis-(2-ethylhexyl) phosphoric acid (HDEHP). Plutonium in water samples were coprecipitated with iron (III) hydroxide and were dissolved in 8 M. nitric acid. Then the plutonium was separated out by using anion exchange resin, Dowex 1x4. After the solvent extraction or the anion exchange, plutonium was coprecipitated with cerous hydroxide. The activities of plutonium were measured by a surface barrier detector for about 24 hours. Lower limit of detection for 1,440 minutes is 0.012 pCi. These studies showed that only plutonium-239, 240 was observed. The range of activities of plutonium-239, 240 in soil were 0.002-0.157 pCi/g (dry), in water were 0.1-81 f Ci/l, and in air were 7-330 a Ci/m 3 . However, the plutonium concentrations in these studies are far below the maximum permissible concentration (MPC) recommended by International Commission on Radiological Protection (ICRP) for general population which is equal to 3x10 8 f Ci/l of water and 5x10 6 a Ci/m 3 of air

Plutonium contaminated materials research programme

International Nuclear Information System (INIS)

Higson, S.G.

1986-01-01

The paper is a progress report for 1985 from the Plutonium Contaminated Materials Working Party (PCMWP). The PCMWP co-ordinates research and development on a national basis in the areas of management, treatment and immobilisation of plutonium contaminated materials, for the purpose of waste management. The progress report contains a review of the development work carried out in eight areas, including: reduction of arisings, plutonium measurement, sorting and packaging, washing of shredded combustible PCM, decommissioning and non-combustible PCM treatment, PCM immobilisation, treatment of alpha bearing liquid wastes, and engineering objectives. (UK)

Nuclear legacy. Democracy in a plutonium economy

International Nuclear Information System (INIS)

Barnaby, F.

1997-01-01

There have already been a few hundred known incidents of nuclear smuggling, mostly of small quantities not close to weapons grade material - but one gram of plutonium is more than sufficient to cause significant harm and to pose a substantial threat. The potential for further thefts is growing as the world produces ever more quantities of plutonium, not only from the dismantling of nuclear weapons but also from the separation out of plutonium from spent uranium nuclear reactor fuel elements. Trying to prevent the theft of gram quantities of plutonium would require levels of protection and surveillance unacceptably high in a democratic society. It is unlikely, therefore, that democracy could survive in a plutonium economy

Diffusion in the uranium - plutonium system and self-diffusion of plutonium in epsilon phase

International Nuclear Information System (INIS)

Dupuy, M.

1967-07-01

A survey of uranium-plutonium phase diagram leads to confirm anglo-saxon results about the plutonium solubility in α uranium (15 per cent at 565 C) and the uranium one in ζ phase (74 per cent at 565 C). Interdiffusion coefficients, for concentration lower than 15 per cent had been determined in a temperature range from 410 C to 640 C. They vary between 0.2 and 6 10 12 cm 2 s -1 , and the activation energy between 13 and 20 kcal/mole. Grain boundary, diffusion of plutonium in a uranium had been pointed out by micrography, X-ray microanalysis and α autoradiography. Self-diffusion of plutonium in ε phase (bcc) obeys Arrhenius law: D = 2. 10 -2 exp -(18500)/RT. But this activation energy does not follow empirical laws generally accepted for other metals. It has analogies with 'anomalous' bcc metals (βZr, βTi, βHf, U γ ). (author) [fr

Atomic energy policy of Japan, especially plutonium utilization policy

International Nuclear Information System (INIS)

Moriguchi, Y.

1993-01-01

The necessity of plutonium use in Japan is discussed. Basic policy regarding plutonium use and future plutonium utilization programme is described including such an aspect as management of plutonium from dismantled nuclear weapons

Solubility of plutonium dioxide aerosols, in vitro

International Nuclear Information System (INIS)

Newton, G.J.; Kanapilly, G.M.

1976-01-01

Solubility of plutonium aerosols is an important parameter in establishing risk estimates for industrial workers who might accidentally inhale these materials and in evaluating environmental health impacts associated with Pu. In vitro solubility of industrial plutonium aerosols in a simulated lung fluid is compared to similar studies with ultrafine aerosols from laser ignition of delta phase plutonium metal and laboratory-produced spherical particles of 238 PuO 2 and 239 PuO 2 . Although relatively insoluble, industrial plutonium-mixed oxide aerosols were much more soluble than laboratory-produced plutonium dioxide particles. Chain agglomerate aerosols from laser ignition of metallic Pu indicated in vitro dissolution half-times of 10 and 50 days for activity median aerodynamic diameter (AMAD) of 0.7 and 2.3 μm, respectively. Plutonium-containing mixed oxide aerosols indicated dissolution half-times of 40 to 500 days for particles formed by industrial powder comminution and blending. Centerless grinding of fuel pellets yielded plutonium-containing aerosols with dissolution half-times of 1200 to 8000 days. All mixed oxide particles were in the size range 1.0 μm to 2.5 μm AMAD

Ultra-small plutonium oxide nanocrystals: an innovative material in plutonium science.

Science.gov (United States)

Hudry, Damien; Apostolidis, Christos; Walter, Olaf; Janssen, Arne; Manara, Dario; Griveau, Jean-Christophe; Colineau, Eric; Vitova, Tonya; Prüssmann, Tim; Wang, Di; Kübel, Christian; Meyer, Daniel

2014-08-11

Apart from its technological importance, plutonium (Pu) is also one of the most intriguing elements because of its non-conventional physical properties and fascinating chemistry. Those fundamental aspects are particularly interesting when dealing with the challenging study of plutonium-based nanomaterials. Here we show that ultra-small (3.2±0.9 nm) and highly crystalline plutonium oxide (PuO2 ) nanocrystals (NCs) can be synthesized by the thermal decomposition of plutonyl nitrate ([PuO2 (NO3 )2 ]⋅3 H2 O) in a highly coordinating organic medium. This is the first example reporting on the preparation of significant quantities (several tens of milligrams) of PuO2 NCs, in a controllable and reproducible manner. The structure and magnetic properties of PuO2 NCs have been characterized by a wide variety of techniques (powder X-ray diffraction (PXRD), X-ray absorption fine structure (XAFS), X-ray absorption near edge structure (XANES), TEM, IR, Raman, UV/Vis spectroscopies, and superconducting quantum interference device (SQUID) magnetometry). The current PuO2 NCs constitute an innovative material for the study of challenging problems as diverse as the transport behavior of plutonium in the environment or size and shape effects on the physics of transuranium elements. © 2014 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Current status of the plutonium hot particle problem

International Nuclear Information System (INIS)

Richmond, C.R.

1975-01-01

Information now available on the question of lung irradiation from particulate plutonium is reviewed. Careful consideration of the available data shows that particulate plutonium is not more hazardous than the same amount of plutonium distributed uniformly. The data also suggest that the potential hazard from plutonium increases as the dispersion throughout the lung becomes more uniform

Appraisal of BWR plutonium burners for energy centers

International Nuclear Information System (INIS)

Williamson, H.E.

1976-01-01

The design of BWR cores with plutonium loadings beyond the self-generation recycle (SGR) level is investigated with regard to their possible role as plutonium burners in a nuclear energy center. Alternative plutonium burner approaches are also examined including the substitution of thorium for uranium as fertile material in the BWR and the use of a high-temperature gas reactor (HTGR) as a plutonium burner. Effects on core design, fuel cycle facility requirements, economics, and actinide residues are considered. Differences in net fissile material consumption among the various plutonium-burning systems examined were small in comparison to uncertainties in HTGR, thorium cycle, and high plutonium-loaded LWR technology. Variation in the actinide content of high-level wastes is not likely to be a significant factor in determining the feasibility of alternate systems of plutonium utilization. It was found that after 10,000 years the toxicity of actinide high-level wastes from the plutonium-burning fuel cycles was less than would have existed if the processed natural ores had not been used for nuclear fuel. The implications of plutonium burning and possible future fuel cycle options on uranium resource conservation are examined in the framework of current ERDA estimates of minable uranium resources

Search for plutonium salt deposits in the plutonium extraction batteries of the Marcoule plant (1963)

International Nuclear Information System (INIS)

Bouzigues, H.; Reneaud, J.M.

1963-01-01

This report describes a method and a special apparatus making it possible to detach the insoluble plutonium salt deposits in the extraction chain of an irradiated fuel treatment plant. The process chosen allows the detection, in the extraction batteries or in the highly active chemical engineering equipment, of plutonium quantities of a few grains. After four years operation it has been impossible to detect measurable quantities of plutonium in any part of the extraction chain. The results have been confirmed by visual examinations carried out with a specially constructed endoscope. (authors) [fr

Tabulated Neutron Emission Rates for Plutonium Oxide

Energy Technology Data Exchange (ETDEWEB)

Shores, Erik Frederick [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-07-24

This work tabulates neutron emission rates for 80 plutonium oxide samples as reported in the literature. Plutonium-­238 and plutonium-­239 oxides are included and such emission rates are useful for scaling tallies from Monte Carlo simulations and estimating dose rates for health physics applications.

Model of plutonium dynamics in a deciduous forest ecosystem

International Nuclear Information System (INIS)

Garten, C.T. Jr.; Gardner, R.H.; Dahlman, R.C.

1980-01-01

A linear compartment model with donor-controlled flows between compartments was designed to describe and simulate the behavior of plutonium ( 239 240 Pu) in a contaminated forest ecosystem at Oak Ridge, TN. At steady states predicted by the model, less than 0.25% of the plutonium in the ecosystem resides in biota. Soil is the major repository of plutonium in the forest, and exchanges of plutonium between soil and litter or soil and tree roots were dominant transfers affecting the ecosystem distribution of plutonium. Variation in predicted steady-state amounts of plutonium in the forest, given variability in the model parameters, indicates that our ability to develop models of plutonium transport in ecosystems should improve with greater precision in data from natural environments and a better understanding of sources of variation in plutonium data

Measurements of plutonium in environmental samples

International Nuclear Information System (INIS)

D'Alberti, F.; Risposi, L.

1996-01-01

Within the activities connected with the start up of the PETRA Laboratory (Processo per l'Estrazione di Terre Rare ed Attinidi, i.e. process for extraction of rare earths and actinides), the Radiation Protection Unit of the J.R.C.-Ispra has carried out a well planned set of experimental measurements aimed at evaluating the zero point of the isotopes of plutonium in environmental samples by alfa spectrometry. After the International Moratorium in 1963, no release of plutonium has occurred in the environment apart from the burn up of SNAP 9A satellite in April 1964. Since then the plutonium concentration in air and in fallout samples has been continuously decreasing requiring, therefore, optimization of both instrumentation and experimental measurement procedures in order to obtain better sensibilities. In this work, the experimental methodology followed at the J.R.C.-Ispra for measurements of plutonium concentration in air, deposition and soil is described and the plutonium behaviour in these samples is reported and discussed starting from 1961

Measurements of plutonium in environmental samples

Energy Technology Data Exchange (ETDEWEB)

D' Alberti, F; Risposi, L [Instituto di Fisica Applicata, University of Milan, Milan (Italy)

1996-01-01

Within the activities connected with the start up of the PETRA Laboratory (Processo per l'Estrazione di Terre Rare ed Attinidi, i.e. process for extraction of rare earths and actinides), the Radiation Protection Unit of the J.R.C.-Ispra has carried out a well planned set of experimental measurements aimed at evaluating the zero point of the isotopes of plutonium in environmental samples by alfa spectrometry. After the International Moratorium in 1963, no release of plutonium has occurred in the environment apart from the burn up of SNAP 9A satellite in April 1964. Since then the plutonium concentration in air and in fallout samples has been continuously decreasing requiring, therefore, optimization of both instrumentation and experimental measurement procedures in order to obtain better sensibilities. In this work, the experimental methodology followed at the J.R.C.-Ispra for measurements of plutonium concentration in air, deposition and soil is described and the plutonium behaviour in these samples is reported and discussed starting from 1961.

Long time contamination from plutonium

Energy Technology Data Exchange (ETDEWEB)

Fueloep, M; Patzeltova, N; Ragan, P [Inst. of Preventive and Clinical Medicine, Bratislava (Slovakia); Matel, L [Comenius Univ., Bratislava (Slovakia). Department of Nuclear Chemistry

1996-12-31

Plutonium isotopes in the organism of the patient (who had participated in the liquidation works after the Chernobyl accident; for three month he had stayed in the epicenter, where he acted as a chauffeur driving a radioactive material to the place of destination) from urine were determined. For determination of the concentration of Pu-239, Pu-240 in urine a modified radiochemical method was used. After mineralization the sample was separated as an anion-nitrate complex with contact by the anion form of the resin in the column. The resin was washed by 8 M HNO{sub 3}, the 8 M HCl with 0.3 M HNO{sub 3} for removing the other radionuclides. The solution 0.36 M HCl with 0.01 M HF was used for the elution of plutonium. Using the lanthanum fluoride technique the sample was filtrated through a membrane filter. The plutonium was detected in the dry sample. The Pu-239 tracer was used for the evaluation of the plutonium separation efficiency. The alpha spectrometric measurements were carried out with a large area silicon detector. The samples were measured and evaluated in the energy region 4.98-5.18 MeV. The detection limit of alpha spectrometry measurements has been 0.01 Bq dm{sup -3}. The concentration of plutonium in the 24-hour urine was determined three times in the quarter year intervals. The results are: 54 mBq, 63.2 mBq, 53 mBq, with average 56,7 mBq. From the results of the analyses of plutonium depositions calculated according to ICRP 54 the intake of this radionuclide for the patient was 56.7 kBq. To estimate a committed effective dose (50 years) from the intake of plutonium was used a conversion factor 6.8.10{sup -5} Sv.Bq{sup -1} (class W). So the expressed committed effective dose received from the plutonium intake is 3.8 Sv. This number is relatively high and all the effective dose will be higher, because the patient was exposed to the other radionuclides too. (Abstract Truncated)

Plutonium recycle. In-core fuel management

International Nuclear Information System (INIS)

Vincent, F.; Berthet, A.; Le Bars, M.

1985-01-01

Plutonium recycle in France will concern a dozen of PWR 900 MWe controlled in gray mode till 1995. This paper presents the main characteristics of fuel management with plutonium recycle. The organization of management studies will be copied from this developed for classical management studies. Up these studies, a ''feasibility report'' aims at establishing at each stage of the fuel cycle, the impact of the utilization of fuel containing plutonium [fr

The plutonium-oxygen and uranium-plutonium-oxygen systems: A thermochemical assessment

International Nuclear Information System (INIS)

1967-01-01

The report of a panel of experts convened by the IAEA in Vienna in March 1964. It reviews the structural and thermodynamic data for the Pu-O and U-Pu-O systems and presents the conclusions of the panel. The report gives information on preparation, phase diagrams, thermodynamic and vaporization behaviour of plutonium oxides, uranium-plutonium oxides and PuO 2 -MeO x (Me=Be, Mg, Al, Si, W, Th, Eu, Zr, Ce) systems. 167 refs, 27 figs, 17 tabs

Qualitative chemical analysis of plutonium by Alpha spectroscopy

International Nuclear Information System (INIS)

Ramirez G, J Qumica.J.

1994-01-01

In this work the separation and purification of plutonium from irradiated uranium was done. The plutonium, produced by the irradiation of uranium in a nuclear reactor and the β decay of 239 Np, was stabilized to Pu +4 with sodium nitrite. Plutonium was separated from the fission products and uranium by ion exchange using the resin Ag 1 X 8. It was electrodeposited on stainless steel discs and the alpha radioactivity of plutonium was measured in a surface barrier detector. The results showed that plutonium was separated with a radiochemical purity higher than 99 %. (Author)

IMPROVED PROCESS OF PLUTONIUM CARRIER PRECIPITATION

Science.gov (United States)

Faris, B.F.

1959-06-30

This patent relates to an improvement in the bismuth phosphate process for separating and recovering plutonium from neutron irradiated uranium, resulting in improved decontamination even without the use of scavenging precipitates in the by-product precipitation step and subsequently more complete recovery of the plutonium in the product precipitation step. This improvement is achieved by addition of fluomolybdic acid, or a water soluble fluomolybdate, such as the ammonium, sodium, or potassium salt thereof, to the aqueous nitric acid solution containing tetravalent plutonium ions and contaminating fission products, so as to establish a fluomolybdate ion concentration of about 0.05 M. The solution is then treated to form the bismuth phosphate plutonium carrying precipitate.

International shipment of plutonium by air

International Nuclear Information System (INIS)

Mercado, J.E.; McGrogan, J.P.

1995-05-01

In support of the United States (US) Government's decision to place excess plutonium oxide at the US Department of Energy's (DOE) Hanford Site under International Atomic Energy Agency (IAEA) safeguards, the Department of State notified the Congress that a plutonium storage vault at the Plutonium Finishing Plant at the Hanford Site would be added to the eligible facilities list. As part of the preparations to transfer the plutonium oxide under IAEA safeguards, samples of the powder were taken from the inventory to be shipped to the IAEA headquarters in Vienna, Austria, for laboratory analysis. The analysis of these samples was of high priority, and the IAEA requested that the material be shipped by aircraft, the most expeditious method

Chemical Disposition of Plutonium in Hanford Site Tank Wastes

Energy Technology Data Exchange (ETDEWEB)

Delegard, Calvin H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jones, Susan A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-05-07

This report examines the chemical disposition of plutonium (Pu) in Hanford Site tank wastes, by itself and in its observed and potential interactions with the neutron absorbers aluminum (Al), cadmium (Cd), chromium (Cr), iron (Fe), manganese (Mn), nickel (Ni), and sodium (Na). Consideration also is given to the interactions of plutonium with uranium (U). No consideration of the disposition of uranium itself as an element with fissile isotopes is considered except tangentially with respect to its interaction as an absorber for plutonium. The report begins with a brief review of Hanford Site plutonium processes, examining the various means used to recover plutonium from irradiated fuel and from scrap, and also examines the intermediate processing of plutonium to prepare useful chemical forms. The paper provides an overview of Hanford tank defined-waste–type compositions and some calculations of the ratios of plutonium to absorber elements in these waste types and in individual waste analyses. These assessments are based on Hanford tank waste inventory data derived from separately published, expert assessments of tank disposal records, process flowsheets, and chemical/radiochemical analyses. This work also investigates the distribution and expected speciation of plutonium in tank waste solution and solid phases. For the solid phases, both pure plutonium compounds and plutonium interactions with absorber elements are considered. These assessments of plutonium chemistry are based largely on analyses of idealized or simulated tank waste or strongly alkaline systems. The very limited information available on plutonium behavior, disposition, and speciation in genuine tank waste also is discussed. The assessments show that plutonium coprecipitates strongly with chromium, iron, manganese and uranium absorbers. Plutonium’s chemical interactions with aluminum, nickel, and sodium are minimal to non-existent. Credit for neutronic interaction of plutonium with these absorbers

Plutonium safety training course

International Nuclear Information System (INIS)

Moe, H.J.

1976-03-01

This course seeks to achieve two objectives: to provide initial safety training for people just beginning work with plutonium, and to serve as a review and reference source for those already engaged in such work. Numerous references have been included to provide information sources for those wishing to pursue certain topics more fully. The first part of the course content deals with the general safety approach used in dealing with hazardous materials. Following is a discussion of the four properties of plutonium that lead to potential hazards: radioactivity, toxicity, nuclear properties, and spontaneous ignition. Next, the various hazards arising from these properties are treated. The relative hazards of both internal and external radiation sources are discussed, as well as the specific hazards when plutonium is the source. Similarly, the general hazards involved in a criticality, fire, or explosion are treated. Comments are made concerning the specific hazards when plutonium is involved. A brief summary comparison between the hazards of the transplutonium nuclides relative to 239 Pu follows. The final portion deals with control procedures with respect to contamination, internal and external exposure, nuclear safety, and fire protection. The philosophy and approach to emergency planning are also discussed

Determination of the mass and width of the W-boson using the semileptonic decay channel with the OPAL detector at LEP

CERN Document Server

Vollmer, Cornelius Fritz

2004-01-01

Diese Arbeit ist eine Weiterentwicklung der beim OPAL-Experiment verwendeten Faltungsmethode zur Bestimmung der Masse des geladenen Eichbosons der schwachen Wechselwirkung. Die Methode wurde ausgeweitet auf eine gleichzeitige Bestimmung der Masse Mw und der Zerfallsbreite Gw des W-Boson genannten Eichbosons. Analysiert wurden dazu Daten, die mit dem OPAL-Experiment in den Jahren 1997 bis 2000 aufgezeichnet wurden. Von den möglichen Zerfällen der erzeugten W-Bosonpaare werden nur semileptonische betrachtet, bei denen ein W-Boson hadronisch in ein Quark-Antiquark-Paar zerfällt und das andere in ein geladenes Lepton und ein Neutrino. In der Faltungsmethode werden die aus der Detektorauflösung resultierenden Fehler der einzelnen Ereignisse berücksichtigt. Dazu wird eine Funktion P(m) für jedes Ereignis ermittelt, welche die Wahrscheinlichkeit angibt, daß die produzierten W-Bosonen eine mittlere Masse m haben. Diese sogenannte Ereigniswahrscheinlichkeitsdichte wird mit einer Physikfunktion PF(m;Mw,Gw) gefal...

Disposal of Surplus Weapons Grade Plutonium

International Nuclear Information System (INIS)

Alsaed, H.; Gottlieb, P.

2000-01-01

The Office of Fissile Materials Disposition is responsible for disposing of inventories of surplus US weapons-usable plutonium and highly enriched uranium as well as providing, technical support for, and ultimate implementation of, efforts to obtain reciprocal disposition of surplus Russian plutonium. On January 4, 2000, the Department of Energy issued a Record of Decision to dispose of up to 50 metric tons of surplus weapons-grade plutonium using two methods. Up to 17 metric tons of surplus plutonium will be immobilized in a ceramic form, placed in cans and embedded in large canisters containing high-level vitrified waste for ultimate disposal in a geologic repository. Approximately 33 metric tons of surplus plutonium will be used to fabricate MOX fuel (mixed oxide fuel, having less than 5% plutonium-239 as the primary fissile material in a uranium-235 carrier matrix). The MOX fuel will be used to produce electricity in existing domestic commercial nuclear reactors. This paper reports the major waste-package-related, long-term disposal impacts of the two waste forms that would be used to accomplish this mission. Particular emphasis is placed on the possibility of criticality. These results are taken from a summary report published earlier this year

Pulmonary carcinogenesis from plutonium-containing particles

International Nuclear Information System (INIS)

Thomas, R.G.; Smith, D.M.; Anderson, E.C.

1980-01-01

Induction of lung tumors by various types of radiation is of paramount concern to the nuclear industry. The data presented were obtained by exposing the pulmonary system of Syrian hamsters to particles of zirconium oxide containing various amounts of either plutonium-238 or -239 as the alpha radiation source. These particles were injected intravenously and lodged permanently in the capillary bed of the lung. When less than 20% of the lung tissue was irradiated, simulating the ''hot particle'' mode, tumors were not evident with lung burdens up to 500 nCi plutonium. More diffuse irradiation significantly increased the tumor incidence, with lung burdens of 50 to 150 nCi. When plutonium-laden microspheres were administered intratracheally, tumor production was considerably increased and the addition of 3 mg of iron oxide intratracheally further increased the incidence. Using the zirconium oxide matrix for the carrier of plutonium in aerosol particles produced tumor incidences of up to 50% in Syrian hamsters exposed by inhalation. Initial pulmonary (alveolar) burdens reached 100 nCi of plutonium. Similar inhalation studies using plutonium dioxide alone (no matrix) failed to produce any increase in lung tumorigenesis. The results are discussed in terms of possible mechanisms necessary for lung carcinogenesis. (H.K.)

Verification station for Sandia/Rockwell Plutonium Protection system

International Nuclear Information System (INIS)

Nicholson, N.; Hastings, R.D.; Henry, C.N.; Millegan, D.R.

1979-04-01

A verification station has been designed to confirm the presence of plutonium within a container module. These container modules [about 13 cm (5 in.) in diameter and 23 cm (9 in.) high] hold sealed food-pack cans containing either plutonium oxide or metal and were designed by Sandia Laboratories to provide security and continuous surveillance and safety. After the plutonium is placed in the container module, it is closed with a solder seal. The verification station discussed here is used to confirm the presence of plutonium in the container module before it is placed in a carousel-type storage array inside the plutonium storage vault. This measurement represents the only technique that uses nuclear detectors in the plutonium protection system

Modified titrimetric determination of plutonium using photometric end-point detection

International Nuclear Information System (INIS)

Baughman, W.J.; Dahlby, J.W.

1980-04-01

A method used at LASL for the accurate and precise assay of plutonium metal was modified for the measurement of plutonium in plutonium oxides, nitrate solutions, and in other samples containing large quantities of plutonium in oxidized states higher than +3. In this modified method, the plutonium oxide or other sample is dissolved using the sealed-reflux dissolution method or other appropriate methods. Weighed aliquots, containing approximately 100 mg of plutonium, of the dissolved sample or plutonium nitrate solution are fumed to dryness with an HC1O 4 -H 2 SO 4 mixture. The dried residue is dissolved in dilute H 2 SO 4 , and the plutonium is reduced to plutonium (III) with zinc metal. The excess zinc metal is dissolved with HCl, and the solution is passed through a lead reductor column to ensure complete reduction of the plutonium to plutonium (III). The solution, with added ferroin indicator, is then titrated immediately with standardized ceric solution to a photometric end point. For the analysis of plutonium metal solutions, plutonium oxides, and nitrate solutions, the relative standard deviation are 0.06, 0.08, and 0.14%, respectively. Of the elements most likely to be found with the plutonium, only iron, neptunium, and uranium interfere. Small amounts of uranium and iron, which titrate quantitatively in the method, are determined by separate analytical methods, and suitable corrections are applied to the plutonium value. 4 tables, 4 figures

The economics of plutonium recycle

International Nuclear Information System (INIS)

James, R.A.

1977-11-01

The individual cost components and the total fuel cycle costs for natural uranium and uranium-plutonium mixed oxide fuel cycles for CANDU-PHW reactors are discussed. A calculation is performed to establish the economic conditions under which plutonium recycle would be economically attractive. (auth)

Nondestructive assay of plutonium residue in horizontal storage tanks

International Nuclear Information System (INIS)

Marsh, S.F.

1985-01-01

Aqueous plutonium recovery and purification processes often involve the temporary storage of plutonium solutions in holding tanks. Because plutonium is known to precipitate from aqueous solutions under certain conditions, there is a continuing need to assay emptied tanks for plutonium residue. A portable gamma spectrometer system, specifically designed for this purpose, provides rapid assay of such plutonium residues in horizontal storage tanks. A means is thus available for the nondestructive analysis of these tanks on a regular schedule to ensure that significant deposits of plutonium are not allowed to accumulate. 5 figs

Plutonium uniqueness

International Nuclear Information System (INIS)

Silver, G.L.

1984-01-01

A standard is suggested against which the putative uniqueness of plutonium may be tested. It is common folklore that plutonium is unique among the chemical elements because its four common oxidation states can coexist in the same solution. Whether this putative uniqueness appears only during transit to equilibrium, or only at equilibrium, or all of the time, is not generally made clear. But while the folklore may contain some truth, it cannot be put to test until some measure of 'uniqueness' is agreed upon so that quantitative comparisons are possible. One way of measuring uniqueness is as the magnitude of the product of the mole fractions of the element at equilibrium. A 'coexistence index' is defined and discussed. (author)

Determination of plutonium in soils by mass spectrometry

International Nuclear Information System (INIS)

Storms, H.A.; Carlson, D.C.; Hunter, F.F.

1974-01-01

A procedure is described in which mass spectrometry is utilized for the determination of plutonium in soils. Using this procedure we have measured plutonium isotopic compositions at concentrations as low as 2 x 10 -14 grams Pu per gram soil. A thermal ionization source with canoe-shaped rhenium filament, is utilized in the mass spectrometer. The plutonium, when loaded onto the filament, is contained in a single Dowex-1 resin bead which is about 350 micrometers in diameter. Concentrating the plutonium within this single bead is a key step in the procedure and produces a relatively clean plutonium fraction. The resin bead also serves as an effective diffusion barrier such that the plutonium is prevented from being removed with the lower boiling impurities. The Pu remains in the bead until the temperature is sufficiently high for efficient production of Pu + ions. Plutonium ionization efficiencies as high as 2.5 percent have been measured

Surplus plutonium disposition draft environmental impact statement. Volume 2

International Nuclear Information System (INIS)

1998-07-01

On May 22, 1997, DOE published a Notice of Intent (NOI) in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS). DOE's disposition strategy allows for both the immobilization of surplus plutonium and its use as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of the immobilized plutonium and MOX fuel (as spent nuclear fuel) in a geologic repository. The Surplus Plutonium Disposition Environmental Impact Statement analyzes alternatives that would use the immobilization approach (for some of the surplus plutonium) and the MOX fuel approach (for some of the surplus plutonium); alternatives that would immobilize all of the surplus plutonium; and the No Action Alternative. The alternatives include three disposition facilities that would be designed so that they could collectively accomplish disposition of up to 50 metric tons (55 tons) of surplus plutonium over their operating lives: (1) the pit disassembly and conversion facility would disassemble pits (a weapons component) and convert the recovered plutonium, as well as plutonium metal from other sources, into plutonium dioxide suitable for disposition; (2) the immobilization facility would include a collocated capability for converting nonpit plutonium materials into plutonium dioxide suitable for immobilization and would be located at either Hanford or SRS. DOE has identified SRS as the preferred site for an immobilization facility; (3) the MOX fuel fabrication facility would fabricate plutonium dioxide into MOX fuel. Volume 2 contains the appendices to the report and describe the following: Federal Register notices; contractor nondisclosure statement; adjunct melter

Addressing mixed waste in plutonium processing

International Nuclear Information System (INIS)

Christensen, D.C.; Sohn, C.L.; Reid, R.A.

1991-01-01

The overall goal is the minimization of all waste generated in actinide processing facilities. Current emphasis is directed toward reducing and managing mixed waste in plutonium processing facilities. More specifically, the focus is on prioritizing plutonium processing technologies for development that will address major problems in mixed waste management. A five step methodological approach to identify, analyze, solve, and initiate corrective action for mixed waste problems in plutonium processing facilities has been developed

Magnetic separation as a plutonium residue enrichment process

International Nuclear Information System (INIS)

Avens, L.R.; Gallegos, U.F.; McFarlan, J.T.

1990-01-01

Several plutonium contaminated residues have been subjected to Open Gradient Magnetic Separation (OGMS) on an experimental scale. OGMS experiments on graphite and bomb reduction residues resulted in a plutonium rich fraction and a plutonium lean fraction. Values for the bulk quantity rejected to the lean fraction varied between about 20% to 85% of the feed bulk. The plutonium content of the lean fraction can be reduced from about 2% in the feed to the 0.1% to 0.5% range dependent on the portion of the feed rejected to this lean fraction. These values are low enough in plutonium to meet economic discard limits and be considered for direct discard. Magnetic separation of pyrochemical salts gave less favorable results. While a fraction very rich in plutonium could be obtained, the lean fraction plutonium content was too high for direct discard. This may still have chemical processing applications. OGMS experiments at low magnetic field strength on incinerator ash did give two fractions but the plutonium content of each fraction was essentially identical. Thus, no chemical processing advantage was identified for magnetic separation of this residue. 6 refs., 1 fig., 9 tabs

Spectrographic analysis of plutonium (1960); L'analyse spectrographique du plutonium (1960)

Energy Technology Data Exchange (ETDEWEB)

Artaud, J; Chaput, M; Robichet, J [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1960-07-01

Various possibilities for the spectrographic determination of impurities in plutonium are considered. The application of the 'copper spark' method, of sparking on graphite and of fractional distillation in the arc are described and discussed in some detail (apparatus, accessories, results obtained). (author) [French] On examine diverses possibilites pour le dosage spectrographique des impuretes dans le plutonium. On decrit et discute plus particulierement de l'application des methodes 'copper spark', de l'etincelage sur graphite et de la distillation fractionnee dans l'arc (montages, accessoires, resultats obtenus). (auteur)

Der Briefwechsel zwischen Alexander von Humboldt und Karl Ernst von Baer

Directory of Open Access Journals (Sweden)

Thomas Schmuck

2012-10-01

Full Text Available Zusammenfassung Der kurze, nicht vollständig erhaltene Briefwechsel zwischen Alexander von Humboldt und Karl Ernst von Baer behandelt sehr verschiedene Themen: Politik, Kriegsgefahr, den Wissenschaftsbetrieb, Auszeichnungen und Tagungen, Embryologie und Cholera. Gemeinsam mit Briefen und Reden ergibt sich dabei ein differenziertes Bild der Beurteilung der beiden Wissenschaftler durch den jeweils anderen. Während Baer sich als Bewunderer Humboldts erweist, erscheint umgekehrt Humboldts Einschätzung Baers als ambivalent. Abstract The short, not completely preserved correspondence between Alexander von Humboldt and Karl Ernst von Baer deals with a wide range of subjects: politics and the danger of war, academic activities, scientific awards and conferences, aspects of embryology and the cholera. Letters to third persons and speeches, together with the correspondence between Humboldt and Baer show a differentiated pattern of mutual appraisal: While Baer always remained an admirer of the elder naturalist, Humboldt’s estimation was characterized by ambivalence.

Monitoring of wastes containing plutonium. Necessity and method

International Nuclear Information System (INIS)

Sousselier, Y.; Pottier, P.

1979-01-01

Importance of problems set by wastes containing plutonium is rapidly growing. Plutonium is not a waste, recycling limits heavily the quantity of plutonium to be stored with wastes. Optimized waste management must take definitive storage and economical limits of plutonium recovery into account. Waste monitoring is a must for safety, economy and waste management. Methods used require reliability, simplicity, sensibility and accuracy particularly for threshold detection [fr

Plutonium in the ocean environment. Its distributions and behavior

International Nuclear Information System (INIS)

Hirose, Katsumi

2009-01-01

Marine environments have been extensively contaminated by plutonium as a result of global fallout due to atmospheric nuclear-weapons testing. Knowledge of the levels and behavior of plutonium in marine environments is necessary to assess the radiological and ecological effects of plutonium. Such analytical techniques as radiochemical analysis, α-spectrometry, and mass spectrometry have been developed to analyze the plutonium in seawater over the past five decades. Because of complex chemical properties (e.g. high reactivity to particles), plutonium in the ocean exhibits more complicated behavior than other long-lived anthropogenic radionuclides, such as 137 Cs. In the present study. In reviewed the research history of plutonium in the ocean, including spatial and temporal changes of plutonium levels and distributions, and its oceanographic behavior. (author)

Volltextserver für wissenschaftliche Dokumente aus der Psychologie : PsyDok

OpenAIRE

Herb, Ulrich

2006-01-01

Artikel über den Open Access Server PsyDok, das disciplinary Repository für die Psychologie Community. Besonderes Augenmerk wird auf die Einbindung des Servers in disziplinäre und interdisziplinäre Suchmaschinen, Nachweissysteme und Datenbanken gelegt. Der letzte Absatz widmet sich Tendenzen bei der Etablierung neuer Maße zur Bestimmung der Qualität elektronischer Dokumente. Wichtig: Die Seitenzählung der PDF weicht von der des Tagungsbandes ab, inhaltlich ist die PDF aber identisch mit der ...

Evaluation von Bildungssoftware im Spannungsfeld von Objektivität und praktischer Anwendung

Directory of Open Access Journals (Sweden)

Cornelia Biffi

2002-05-01

Full Text Available Das Angebot an Bildungs- bzw. Lernsoftware umfasst eine breite Palette von sehr unterschiedlichen Produkten. Eigentliche Unterrichtssoftware, die speziell für den Unterricht hergestellt und auf Lehrmittel und Curriculum abgestimmt ist, gibt es kaum. Im Projekt «Lernsoftware Evaluation» des Pestalozzianums Zürich ermitteln Lehrpersonen die Qualität von Bildungssoftware, indem sie diese im Unterricht einsetzen und anhand eines Kriterienrasters beurteilen. Eine Analyse der in der Evaluation generierten Daten belegt die Problematik des Anspruchs einer objektiven Qualitätsbeurteilung. Es werden die Probleme bei der Anwendung von Kriterienraster und Beurteilungsmodus aufgezeigt und ermittelt, worin die subjektiven Qualitätsmassstäbe der Evaluierenden begründet sind. Diese Ausführungen sind Teil eines Forschungsprojekts für die Weiterentwicklung einer theoretisch fundierten, aber dennoch praxisnahen Evaluation von Bildungssoftware.

Extraction and purification of plutonium by a tertiary amine; Extraction et purification du plutonium par une amine tertiaire

Energy Technology Data Exchange (ETDEWEB)

Trentinian, M de; Chesne, A [Commissariat a l' Energie Atomique, Fontenay aux Roses, Section de Chimie des Actimides (France).Centre d' Etudes Nucleaires; Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1960-07-01

Trilaurylamine diluted with a paraffinic solvent (dodecane) was studied as part of the research dealing with the separation and purification of plutonium. The physical properties (solubility of nitrates in the amine as a function of temperature) and the resistance to radiations of this substance were examined. The extraction characteristics of nitric solutions of plutonium, uranium and certain fission products are given as a function of the following factors: concentration of the various ions in solution, valency states. A method of plutonium purification based on these results is presented. (author) [French] La trilaurylamine diluee par un solvant paraffinique (dodecane) a ete etudiee dans le cadre des recherches concernant la separation et la purification du plutonium. Une etude des caracteres physiques (solubilite des nitrates dans l'amine en fonction de la temperature) s'ajoute a celle de la tenue aux radiations de ce corps. Les caracteristiques d'extraction de solutions nitriques de plutonium, uranium, et certains produits de fission, sont donnes en fonction des facteurs suivants: concentration des differents ions en solution, etats de valence. On presente une methode de purification du plutonium basee sur ces resultats. (auteur)

Evaluation of plutonium at Enewetak Atoll

International Nuclear Information System (INIS)

Wilson, D.W.; Ng, Y.C.; Robison, W.L.

1975-01-01

An extensive survey was carried out in 1972 to 1973 to assess the current radiological status of Enewetok Atoll. The radionuclides detected in the Atoll environment were studied for their potential contributions to the dose commitment of the returning population according to several pathways of exposure. Plutonium was detected in air and in the terrestrial and aquatic environment at concentrations that varied from background levels due to world-wide fallout to levels several orders-of-magnitude above. The dose commitments from plutonium via the terrestrial food chain and inhalation vary according to the postulated living pattern. The dosages via marine foods can be expected to be insensitive to living pattern and to exceed those via terrestrial foods. Plutonium would contribute nearly all of the dosage via inhalation, but this pathway ranks low in overall importance compared with the food-chain and external-dose pathways. Although the potential dose from plutonium via all pathways is low relative to that from 60 Co, 90 Sr and 137 Cs, plutonium will still remain in the Atoll environment after the other makor isotopes have decayed away. (author)

Long-term plutonium storage: Design concepts

International Nuclear Information System (INIS)

Wilkey, D.D.; Wood, W.T.; Guenther, C.D.

1994-01-01

An important part of the Department of Energy (DOE) Weapons Complex Reconfiguration (WCR) Program is the development of facilities for long-term storage of plutonium. The WCR design goals are to provide storage for metals, oxides, pits, and fuel-grade plutonium, including material being held as part of the Strategic Reserve and excess material. Major activities associated with plutonium storage are sorting the plutonium inventory, material handling and storage support, shipping and receiving, and surveillance of material in storage for both safety evaluations and safeguards and security. A variety of methods for plutonium storage have been used, both within the DOE weapons complex and by external organizations. This paper discusses the advantages and disadvantages of proposed storage concepts based upon functional criteria. The concepts discussed include floor wells, vertical and horizontal sleeves, warehouse storage on vertical racks, and modular storage units. Issues/factors considered in determining a preferred design include operational efficiency, maintenance and repair, environmental impact, radiation and criticality safety, safeguards and security, heat removal, waste minimization, international inspection requirements, and construction and operational costs

Technical considerations and policy requirements for plutonium management

International Nuclear Information System (INIS)

Christensen, D.C.; Dinehart, S.M.; Yarbro, S.L.

1995-01-01

The goals for plutonium management have changed dramatically over the past few years. Today, the challenge is focused on isolating plutonium from the environment and preparing it for permanent disposition. In parallel, the requirements for managing plutonium are rapidly changing. For example, there is a significant increase in public awareness on how facilities operate, increased attention to environmental safety and health (ES and H) concerns, greater interest in minimizing waste, more emphasis on protecting material from theft, providing materials for international inspection, and a resurgence of interest in using plutonium as an energy source. Of highest concern, in the immediate future, is protecting plutonium from theft or diversion, while the national policy on disposition is debated. These expanded requirements are causing a broadening of responsibilities within the Department of Energy (DOE) to include at least seven organizations. An unavoidable consequence is the divergence in approach and short-term goals for managing similar materials within each organization. The technology base does exist, properly, safely, and cost effectively to extract plutonium from excess weapons, residues, waste, and contaminated equipment and facilities, and to properly stabilize it. Extracting the plutonium enables it to be easily inventoried, packaged, and managed to minimize the risk of theft and diversion. Discarding excess plutonium does not sufficiently reduce the risk of diversion, and as a result, long-term containment of plutonium from the environment may not be able to be proven to the satisfaction of the public

On-line monitoring of low-level plutonium concentrations

International Nuclear Information System (INIS)

Hofstetter, K.J.; Huff, G.A.; Rebagay, T.V.

1979-10-01

An on-line monitor has been developed to assay plutonium in nitric acid solutions. The performance of the monitor has been assessed by a laboratory experimentation program using solutions with plutonium concentrations from 0.1 to 10 g/l. These conditions are typical of the plutonium solutions in an input stream to a plutonium-purification cycle in a reprocessing plant following uranium/plutonium partitioning. The monitoring system can be fully automated and shows great promise for detecting and quantifying plutonium in situ, thus minimizing the reliance on traditional sampling and laboratory-analysis techniques. The total concentration and isotopic abundance of plutonium are determined by measuring the absolute intensities of the low-energy gamma rays characteristics of 238 Pu, 239 Pu, and 240 Pu nuclides by direct gamma-ray spectroscopy and computer analysis of the spectral data. The addition of a monitoring system of this type to the input stream of a plutonium-purification cycle along with other suitable monitors on the waste streams and on the product stream provides the basis for a near real-time materials control and inventory system. Results of the laboratory-evaluation program employing plutonium in solutions with isotopic compositions typical of those involved in processing light water reactor fuels are presented. The detailed design of a monitoring cell and detection system is given. The precision and accuracy of the results relative to those measured by mass spectrometry and controlled potential coulometry are also summarized

Technical considerations and policy requirements for plutonium management

International Nuclear Information System (INIS)

Christensen, D.C.; Dinehart, S.M.; Yarbro, S.L.

1996-01-01

The goals for plutonium management have changed dramatically over the past few years. Today, the challenge is focused on isolating plutonium from the environment and preparing it for permanent disposition. In parallel, the requirements for managing plutonium are rapidly changing. For example, there is a significant increase in public awareness on how facilities operate, increased attention to environmental safety and health (ES and H) concerns, greater interest in minimizing waste, more emphasis on protecting material from theft, providing materials for international inspection, and a resurgence of interest in using plutonium as an energy source. Of highest concern, in the immediate future, is protecting plutonium from theft or diversion, while the national policy on disposition is debated. These expanded requirements are causing a broadening of responsibilities within the Department of Energy (DOE) to include at least seven organizations. An unavoidable consequence is the divergence in approach and short-term goals for managing similar materials within each organization. The technology base does exist, properly, safely, and cost effectively to extract plutonium from excess weapons, residues, waste, and contaminated equipment and facilities, and to properly stabilize it. Extracting the plutonium enables it to be easily inventoried, packaged, and managed to minimize the risk of theft and diversion. Discarding excess plutonium does not sufficient reduce the risk of diversion, and as a result, long-term containment of plutonium from the environment may not be able to be proven to the satisfaction of the public

Plutonium again (smuggling and movements)

International Nuclear Information System (INIS)

Anon.

1994-01-01

A link is discounted between nuclear proliferation and the recently discovered smuggled plutonium from the former Soviet Union at Munich airport and other places in Germany. It is argued that governments wishing to obtain nuclear materials to develop a weapons programme would not arrange to have it smuggled in a suitcase. Instead, it is speculated that a link exists between the plutonium smuggling incidents and the desire to promote the production of mixed oxide (MOX) fuel. Such incidents, by further raising public anxiety, may be intended to turn public opinion in favour of MOX fuel production as a sensible way of getting rid of surplus plutonium. (UK)

Safe handling of plutonium: a panel report

Energy Technology Data Exchange (ETDEWEB)

1974-01-01

This guide results from a meeting of a Panel of Experts held by the International Atomic Energy Agency on 8 to 12 November 1971. It is directed to workers in research laboratories handling plutonium in gram amounts. Contents: aspects of the physical and chemical properties of plutonium; metabolic features of plutonium; facility design features for safe handling of plutonium (layout of facility, working zones, decontamination room, etc.); glove boxes; health surveillance (surveillance of environment and supervision of workers); emergencies; organization. Annexes: types of glove boxes; tables; mobile ..cap alpha.. air sampler; aerosol monitor; bio-assay limits of detection; examples of contamination control monitors.

Plutonium disposition via immobilization in ceramic or glass

Energy Technology Data Exchange (ETDEWEB)

Gray, L.W.; Kan, T.; Shaw, H.F.; Armantrout, A.

1997-03-05

The management of surplus weapons plutonium is an important and urgent task with profound environmental, national, and international security implications. In the aftermath of the Cold War, Presidential Policy Directive 13, and various analyses by renown scientific, technical, and international policy organizations have brought about a focused effort within the Department of Energy to identify and implement paths for the long term disposition of surplus weapons- usable plutonium. The central goal of this effort is to render surplus weapons plutonium as inaccessible and unattractive for reuse in nuclear weapons as the much larger and growing stock of plutonium contained in spent fuel from civilian reactors. One disposition option being considered for surplus plutonium is immobilization, in which the plutonium would be incorporated into a glass or ceramic material that would ultimately be entombed permanently in a geologic repository for high-level waste.

Preparation of plutonium hexafluoride. Recovery of plutonium from waste dross (1962)

International Nuclear Information System (INIS)

Gendre, R.

1962-01-01

The object of this work is to study the influence of various physical factors on the rate of fluorination of solid plutonium tetrafluoride by fluorine. In a horizontal oven with a circulation for pure fluorine at atmospheric pressure and 520 deg. C, at a fluorine rate of 9 litres/hour, it is possible to transform 3 g of tetrafluoride to hexafluoride with about 100 per cent transformation and a recovery yield of over 90 per cent, in 4 to 5 hours. The fluorination rate is a function of the temperature, of the fluorine flow-rate, of the crucible surface, of the depth of the tetrafluoride layer and of the reaction time. It does not depend on the diffusion of the fluorine into the solid but is determined by the reaction at the gas-solid interface and obeys the kinetic law (1 - T T ) 1/3 = kt + 1. The existence of intermediate fluorides, in particular Pu 4 F 17 , is confirmed by a break in the Arrhenius plot at about 370 deg. C, by differences in the fluorination rates inside the tetrafluoride layer, and by reversible colour changes. The transformation to hexafluoride occurs with a purification with respect of the foreign elements present in the initial plutonium. Recovery of plutonium from waste dross: The study is based on the transformation of occluded plutonium particles to gaseous hexafluoride which is then decomposed thermally to the tetrafluoride which can be reintroduced directly in the production circuit. Under the conditions considered this process is not applicable industrially. After milling, it is possible to separate the dross into enriched (75 per cent Pu in 2.6 per cent by weight of dross) and depleted portions. By prolonged fluorination (16 hours) of the various fractions it is possible to recover about 80 per cent of the plutonium. A treatment plant using fluidization, as described at the end of this study, should make it possible to substantially improve the yield. (author) [fr

Plutonium decontamination studies using Reverse Osmosis

International Nuclear Information System (INIS)

Plock, C.E.; Travis, T.N.

1980-01-01

Water in batches of 45 gallons each, from a creek crossing the Rocky Flats Plant, was transferred to the Reverse Osmosis (RO) laboratory for experimental testing. The testing involved using RO for plutonium decontamination. For each test, the water was spiked with plutonium, had its pH adjusted, and was then processed by RO. At a water recovery level of 87%, the plutonium decontamination factors ranged from near 100 to 1200, depending on the pH of the processed water

Uranium-plutonium fuel for fast reactors

International Nuclear Information System (INIS)

Antipov, S.A.; Astafiev, V.A.; Clouchenkov, A.E.; Gustchin, K.I.; Menshikova, T.S.

1996-01-01

Technology was established for fabrication of MOX fuel pellets from co-precipitated and mechanically blended mixed oxides. Both processes ensure the homogeneous structure of pellets readily dissolvable in nitric acid upon reprocessing. In order to increase the plutonium charge in a reactor-burner a process was tested for producing MOX fuel with higher content of plutonium and an inert diluent. It was shown that it is feasible to produce fuel having homogeneous structure and the content of plutonium up to 45% mass

Elaboration and characterisation of plutonium waste reference materials

International Nuclear Information System (INIS)

Perolat, J.P.

1990-01-01

The Analysis Methods Establishment Commission (CETAMA) has set up a program for the elaboration and characterisation of plutonium waste reference materials. The object of this program is to give laboratories the possibility to test and calibrate apparatus used in non-destructive methods for the analysis of plutonium waste. The different parameters of this program are presented: - characterisation of plutonium, - type and number of containers, - plutonium distribution inside the different containers, - description of the matrix

The extraction of plutonium with triethylene glycol dichloride

International Nuclear Information System (INIS)

Aikin, A.M.; Moss, M.; Bruce, T.

1951-03-01

The extraction of plutonium by triethylene glycol dichloride (trigly) has been investigated briefly. The effect of (1) the valence state of the plutonium, (2) the concentration of nitric acid, (3) the concentration of ammonium nitrate and (4) the conditioning of the trigly was measured. The solubility of plutonium IV in trigly was found to be 70 mgms/ml. Solutions of plutonium in trigly and in concentrated nitric acid solutions have been examined spectrophotometrically. (author)

The extraction of plutonium with triethylene glycol dichloride

Energy Technology Data Exchange (ETDEWEB)

Aikin, A M; Moss, M; Bruce, T

1951-03-15

The extraction of plutonium by triethylene glycol dichloride (trigly) has been investigated briefly. The effect of (1) the valence state of the plutonium, (2) the concentration of nitric acid, (3) the concentration of ammonium nitrate and (4) the conditioning of the trigly was measured. The solubility of plutonium IV in trigly was found to be 70 mgms/ml. Solutions of plutonium in trigly and in concentrated nitric acid solutions have been examined spectrophotometrically. (author)

Study of plutonium multi-recycle in high moderation LWR cores

International Nuclear Information System (INIS)

Iwata, Yutaka; Yamamoto, Toru; Ueji, Masao; Hibi, Koki; Aoyama, Motoo; Sakurada, Koichi

2000-01-01

Nuclear Power Engineering Corporation (NUPEC) has been studying advanced cores that are dedicated to enhance the plutonium consumption per recycling for effective use of plutonium. In this study, a fissile plutonium consumption rate is adopted as an index of the effective use of plutonium, which is defined as a ratio of consumption to loading of fissile plutonium in a core. High moderation core concepts have been studied in order to increase this index based on full MOX cores in the latest designs of LWRs in Japan that are the Advanced Boiling Water Reactor (ABWR) and the Advanced Pressurized Water Reactor (APWR). As a part of this study, core performance in the case of plutonium multi-recycling has been surveyed with these higher moderation cores aiming further effective use of plutonium. The design and analyses for equilibrium cores show that nuclear and thermal hydraulics parameters satisfy design criteria, and a fissile plutonium consumption rate increases up to 20% for ABWRs and 30% for APWRs even in plutonium multi-recycling condition. It was confirmed that the high moderation cores are feasible from a viewpoint of nuclear and thermal hydraulics, safety and plutonium consumption in the condition of plutonium multi-recycling. (author)

Standard practice for preparation and dissolution of plutonium materials for analysis

CERN Document Server

American Society for Testing and Materials. Philadelphia

2008-01-01

1.1 This practice is a compilation of dissolution techniques for plutonium materials that are applicable to the test methods used for characterizing these materials. Dissolution treatments for the major plutonium materials assayed for plutonium or analyzed for other components are listed. Aliquants of the dissolved samples are dispensed on a weight basis when one of the analyses must be highly reliable, such as plutonium assay; otherwise they are dispensed on a volume basis. 1.2 The treatments, in order of presentation, are as follows: Procedure Title Section Dissolution of Plutonium Metal with Hydrochloric Acid 9.1 Dissolution of Plutonium Metal with Sulfuric Acid 9.2 Dissolution of Plutonium Oxide and Uranium-Plutonium Mixed Oxide by the Sealed-Reflux Technique 9.3 Dissolution of Plutonium Oxide and Uranium-Plutonium Mixed Oxides by Sodium Bisulfate Fusion 9.4 Dissolution of Uranium-Plutonium Mixed Oxides and Low-Fired Plutonium Oxide in Beakers 9.5 1.3 The values stated in SI units are to be re...

Civil plutonium held in France in December 31, 2000

International Nuclear Information System (INIS)

2002-02-01

Spent fuels comprise about 1% of plutonium which is separated during the reprocessing and recycled to prepare the mixed uranium-plutonium fuel (MOX), which in turn is burnt in PWRs. Plutonium can be in a non-irradiated or separated form, or in an irradiated form when contained in the spent fuel. Each year, in accordance with the 1997 directives relative to the management of plutonium, France has to make a status of its civil plutonium stock and communicate it to the IAEA using a standard model form. This short document summarizes the French plutonium stocks at the end of 1999 and 2000. (J.S.)

Plutonium determination by isotope dilution

International Nuclear Information System (INIS)

Lucas, M.

1980-01-01

The principle is to add to a known amount of the analysed solution a known amount of a spike solution consisting of plutonium 242. The isotopic composition of the resulting mixture is then determined by surface ionization mass spectrometry, and the plutonium concentration in the solution is deduced, from this measurement. For irradiated fuels neutronic studies or for fissile materials balance measurements, requiring the knowledge of the ratio U/Pu or of concentration both uranium and plutonium, it is better to use the double spike isotope dilution method, with a spike solution of known 233 U- 242 Pu ratio. Using this method, the ratio of uranium to plutonium concentration in the irradiated fuel solution can be determined without any accurate measurement of the mixed amounts of sample and spike solutions. For fissile material balance measurements, the uranium concentration is determined by using single isotope dilution, and the plutonium concentration is deduced from the ratio Pu/U and U concentration. The main advantages of isotope dilution are its selectivity, accuracy and very high sensitivity. The recent improvements made to surface ionization mass spectrometers have considerably increased the precision of the measurements; a relative precision of about 0.2% to 0.3% is obtained currently, but it could be reduced to 0.1%, in the future, with a careful control of the experimental procedures. The detection limite is around 0.1 ppb [fr

[Friedrich Ludwig von Maydelli pildid Baltimaade ajaloost = Friedrich Ludwig von Maydells Baltische Geschichte in Bildern = Friedrich Ludwig von Maydell ́s Baltic history in images] / Ulrike Plath

Index Scriptorium Estoniae

Plath, Ulrike, 1972-

2014-01-01

Arvustus: Friedrich Ludwig von Maydelli pildid Baltimaade ajaloost = Friedrich Ludwig von Maydells Baltische Geschichte in Bildern = Friedrich Ludwig von Maydell ́s Baltic history in images. Eesti kunstimuuseum, Kadrioru kunstimuuseum. Tallinn 2013

Plutonium and americium separation from salts

International Nuclear Information System (INIS)

Hagan, P.G.; Miner, F.J.

1976-01-01

Salts or materials containing plutonium and americium are dissolved in hydrochloric acid, heated, and contacted with an alkali metal carbonate solution to precipitate plutonium and americium carbonates which are thereafter readily separable from the solution

Work at Aldermaston on plutonium binding with biological systems

International Nuclear Information System (INIS)

Popplewell, D.S.

1976-01-01

Over a number of years, the Chemistry Division of AWRE, Aldermaston, studied the nature of plutonium in various biological systems. The object of the work was to identify those natural products of the body which play a part in the transport and deposition of accidental intakes of plutonium. These results should be of value in formulating more effective therapeutic measures for plutonium removal from the body. The paper reviews the work at AWRE on the interaction of plutonium with serum and rat liver. Experiments on the uptake of plutonium into cell cultures are described. The aim of these experiments was to see whether a model system could be set up for testing the efficacy by which chelating agents could remove plutonium from within cells. A simple hypothesis is presented for the mode of transport of plutonium within animals. (author)

Distribution coefficient of plutonium between sediment and seawater

International Nuclear Information System (INIS)

Duursma, E.K.; Parsi, P.

1974-01-01

Using plutonium 237 as a tracer, a series of experiments were conducted to determine the distribution coefficient of plutonium onto sediments both under oxic and anoxic conditions, where the plutonium was added to seawater in three different valence states: III, IV and VI

HENC performance evaluation and plutonium calibration

International Nuclear Information System (INIS)

Menlove, H.O.; Baca, J.; Pecos, J.M.; Davidson, D.R.; McElroy, R.D.; Brochu, D.B.

1997-10-01

The authors have designed a high-efficiency neutron counter (HENC) to increase the plutonium content in 200-L waste drums. The counter uses totals neutron counting, coincidence counting, and multiplicity counting to determine the plutonium mass. The HENC was developed as part of a Cooperative Research and Development Agreement between the Department of Energy and Canberra Industries. This report presents the results of the detector modifications, the performance tests, the add-a-source calibration, and the plutonium calibration at Los Alamos National Laboratory (TA-35) in 1996

Plutonium determination by spectrophotometry of plutonium (VI): control of the nuclear fuel reprocessing plant

Energy Technology Data Exchange (ETDEWEB)

Grison, J [Compagnie Generale des Matieres Nucleaires (COGEMA), Centre de la Hague, 50 - Cherbourg (France)

1980-10-01

The plutonium (VI) spectrophotometric determination, after AgO oxidation in 3 M nitric acid medium, is used for the running-control of the nuclear fuel reprocessing plant at La Hague. Analytical device used in glove-box or shielded-cell is briefly described. This method is fast, sensitive, unfailing and gives simple effluents. It is applied by day and night shifts, during Light Water Reactor fuel reprocessing campaign, for 0.5 mg/l up to 20 g/l plutonium solutions. Reference solution measurements have a 0.8 to 1.4 % relative standard deviation; duplicate plutonium determinations give a 0.3% relative standard deviation for sample analysis. There is a discrepancy (- 0.3% to - 0.9%) between the spectrophotometric method results and the isotopic dilution analysis.

Plutonium determination by spectrophotometry of plutonium (VI): control of the nuclear fuel reprocessing plant

International Nuclear Information System (INIS)

Grison, J.

1980-01-01

The plutonium (VI) spectrophotometric determination, after AgO oxidation in 3 M nitric acid medium, is used for the running-control of the nuclear fuel reprocessing plant at La Hague. Analytical device used in glove-box or shielded-cell is briefly described. This method is fast, sensitive, unfailing and gives simple effluents. It is applied by day and night shifts, during Light Water Reactor fuel reprocessing campaign, for 0.5 mg/l up to 20 g/l plutonium solutions. Reference solution measurements have a 0.8 to 1.4 % relative standard deviation; duplicate plutonium determinations give a 0.3% relative standard deviation for sample analysis. There is a discrepancy (- 0.3% to - 0.9%) between the spectrophotometric method results and the isotopic dilution analysis [fr

Fifty years of plutonium exposure to the Manhattan Project plutonium workers: an update.

Science.gov (United States)

Voelz, G L; Lawrence, J N; Johnson, E R

1997-10-01

Twenty-six white male workers who did the original plutonium research and development work at Los Alamos have been examined periodically over the past 50 y to identify possible health effects from internal plutonium depositions. Their effective doses range from 0.1 to 7.2 Sv with a median value of 1.25 Sv. As of the end of 1994, 7 individuals have died compared with an expected 16 deaths based on mortality rates of U.S. white males in the general population. The standardized mortality ratio (SMR) is 0.43. When compared with 876 unexposed Los Alamos workers of the same period, the plutonium worker's mortality rate was also not elevated (SMR = 0.77). The 19 living persons have diseases and physical changes characteristic of a male population with a median age of 72 y (range = 69 to 86 y). Eight of the twenty-six workers have been diagnosed as having one or more cancers, which is within the expected range. The underlying cause of death in three of the seven deceased persons was from cancer, namely cancer of prostate, lung, and bone. Mortality from all cancers was not statistically elevated. The effective doses from plutonium to these individuals are compared with current radiation protection guidelines.

Automatisierung von HiL Tests

OpenAIRE

Asbach, Lennart; Ebrecht, Lars

2010-01-01

Automatisierung von HiL Tests. Darstellung und Bewertung einer praktischen Umsetzung. Das Poster zeigt die Motivation, die Durchführung, einen aktuellen Stand und einen Ausblick der Testautomatisierung im Bahnlabor RailSiTe. Als Beispiel dient der Konformitätstest von ETCS-Onboard Zugrechnern, um die Einführung von ETCS zu unterstützen.

Die Wirkung von Desacetylcefotaxin, einem Metaboliten von Cefotaxim, in vitro und auf die experimentelle Infektion mit Escherichia coli

OpenAIRE

Wirbelauer, J.; Hof, H.; Hacker, Jörg

2009-01-01

Die MHK-Werte von Desacetylcefotaxim gegen verschiedene, z. T. ampicillinresistente Stämme von Escherichia coH, die mit Hilfe einer Agardilutionsmethode erhoben wurden, waren höher als die von Cefotaxim und Ceftriaxon, jedoch niedriger als die von Cefoxitin. In einem Modell der systemischen Infektion der Maus mit einem plasmidtragenden, betalactamaseproduzierenden Stamm von E. coli führte die Therapie mit Desacetylcefotaxim zu einer starken Reduktion der Keime pro Leber. Im Vergleich zur Ther...

Plutonium recycle in PWR reactors (Brazilian Nuclear Program)

International Nuclear Information System (INIS)

Rubini, L.A.

1978-02-01

An evaluation is made of the material requirements of the nuclear fuel cycle with plutonium recycle. It starts from the calculation of a reference reactor and allows the evaluation of demand under two alternatives of nuclear fuel cycle for Pressurized Water Reactors (PWR): without plutonium recycle; and with plutonium recycle. Calculations of the reference reactor have been carried out with the CELL-CORE codes. For plutonium recycle, the concept of uranium and plutonium homogeneous mixture has been adopted, using self-produced plutonium at equilibrium, in order to get minimum neutronic perturbations in the reactor core. The refueling model studied in the reference reactor was the 'out-in' scheme with a constant number of changed fuel elements (approximately 1/3 of the core). Variations in the material requirements were studied considering changes in the installed nuclear capacity of PWR reactors, the capacity factor of these reactors, and the introduction of fast breeders. Recycling plutonium produced inside the system can reach economies of about 5%U 3 O 8 and 6% separative work units if recycle is assumed only after the 5th operation cycle of the thermal reactors. The cumulative amount of fissile plutonium obtained by the Brazilian Nuclear Program of PWR reactors by 1991 should be sufficient for a fast breeder with the same capacity as Angra 2. For the proposed fast breeder programs, the fissile plutonium produced by thermal reactors is sufficient to supply fast breeder initial necessities. Howewer, U 3 O 8 and SWU economy with recycle is not significant when the proposed fast breeder program is considered. (Author) [pt

Plutonium in a grassland ecosystem

International Nuclear Information System (INIS)

Little, C.A.

1976-01-01

This study was concerned with plutonium contamination of grassland at the U.S. Energy Research and Development Administration Rocky Flats plant northwest of Denver, Colorado. Of interest were: the definition of major plutonium-containing ecosystem compartments; the relative amounts in those compartments; how those values related to studies done in other geogrphical areas; whether or not the predominant isotopes, 238 Pu and 239 Pu, behaved differently; and what mechanisms might have allowed for the observed patterns of contamination. Samples of soil, litter, vegetation, arthropods, and small mammals were collected for plutonium analysis and mass determination from each of two macroplots. Small aliquots (5 g or less) were analyzed by a rapid liquid scintillation technique and by alpha spectrometry. Of the compartments sampled, greater than 99% of the total plutonium was contained in the soil. The concentrations of plutonium in soil were significantly inversely correlated with distance from the contamination source, depth of the sample, and particle size of the sieved soil samples. The soil data suggested that the distribution of contamination largely resulted from physical transport processes. A mechanism of agglomerated submicron plutonium oxide particles and larger (1-500 μm) host soil particles was proposed. Concentrations of Pu in litter and vegetation were inversely correlated to distance from the source and directly correlated to soil concentrations at the same location. Comparatively high concentration ratios of vegetation to soil suggested wind resuspension of contamination as an important transport mechanism. Arthropod and small mammal samples were highly skewed, kurtotic, and quite variable, having coefficients of variation (standard deviation/mean) as high as 600%. Bone Pu concentrations were lower than other tissues. Hide, GI, and lung were generally not higher in Pu than kidney, liver and muscle

Work surface for soluble plutonium

International Nuclear Information System (INIS)

Silver, G.L.

2005-01-01

A three-dimensional work surface for aqueous plutonium is illustrated. It is constructed by means of estimating work as a function of the ambient pH and redox potential in a plutonium solution. The surface is useful for illustrating the chemistry of disproportionation reactions. Work expressions are easier to use than work integrals. (author)

Oxidation-state maxima in plutonium chemistry

International Nuclear Information System (INIS)

Silver, G.L.

2013-01-01

Maxima in the fractions of the trivalent and hexavalent oxidation states of plutonium are inherent in the algebra of its disproportionation reactions. The maxima do not support overall disproportionation equations as satisfactory representations of aqueous plutonium. (author)

Plutonium recycling and the problem of nuclear proliferation

International Nuclear Information System (INIS)

Albright, D.; Feiveson, H.S.

1988-01-01

A typical 1-gigawatt light water reactor (LWR), the dominant commercial power reactor type today, operating at 70% capacity factor, generates approximately 250 kilograms of plutonium annually. This plutonium, which is produced in the reactor through neutron capture by uranium-238, is then discharged from the reactor along with the other constituents of the spent fuel. About 70% of the plutonium, or 175 kilograms, consists of fissile (odd-numbered) plutonium isotopes. As long as the plutonium discharged from the reactor is left intermixed with the highly radioactive fission products also contained in the spent fuel, it cannot readily be used for power or for weapons. However, upon chemical separation from the radioactive fission products and other components of the spent reactor fuel, the plutonium produced each year in a gigawatt reactor could be used, either in recycled fuel (to replace about 175 kilograms of U-235 in a power reactor) or to provide the fissile material for more than 25 nuclear warheads. Commercial separation of plutonium and the introduction of nuclear fuel cycles using recycled plutonium, which are now impending in several countries, force one to balance the probable increased risks of nuclear proliferation due to these activities against various economic and other motives that have been forwarded in their defense. The authors undertake an assessment of this balancing in this article

The use of plutonium rapides surregenerateurs aspects techniques et economiques

International Nuclear Information System (INIS)

Guillet, H.; Delayre, R.; Mougniot, J.C.; Ferrari, A.

1977-01-01

Nuclear energy production utilizing U 235 and U 238 inevitably results in the formation of plutonium. Some of this is directly used by the reactor in power production. Some reactors, e.g. the Candu type, burn most of their plutonium ''in situ''. However the surplus quantity of plutonium produced is increasing, and by 1990 the world stock of plutonium is predicted to be about 1000 tons (300 tons in Europe and 400 in the USA). This represents approximately 0.1 Q of potential power, where Q=10 21 joules. Proposals for dealing with this plutonium include its storage, either as irradiated fuel or as a refined substance (plutonium nitrate or oxide); its use in thermal reactors as a substitute for U 235 ; its use in fast breeder reactors which can act as consumers of plutonium as well as producers and which can therefore regulate the world's plutonium stocks. Leaving aside the question of storage, certain technical conditions must be fulfilled. It is essential that reprocessing plants should be operational and available in adequate numbers. An industry able to make use of plutonium should be developed with large capacity units. There seem to be no problems with plutonium use in reactors: conclusive experiments have proved the accuracy of calculations regarding plutonium recycling in thermal reactors and a number of fast breeders have proved the possibility of using plutonium in them. Experience acquired during the past ten years permits us to deal with the safety and safeguards problem of using plutonium. Many economic questions remain, however, including questions affecting the utilization of plutonium, such as the cost of regenerating irradiated fuel and of making fuel, and questions affecting the strategy of using plutonium in different ways, such as the price at which it should be sold. Also the cost of producing electricity using plutonium is not yet clear. It is unavoidable that plutonium will be used in nuclear power development. The technical and economic problems

Plutonium Finishing Plant safety evaluation report

International Nuclear Information System (INIS)

1995-01-01

The Plutonium Finishing Plant (PFP) previously known as the Plutonium Process and Storage Facility, or Z-Plant, was built and put into operation in 1949. Since 1949 PFP has been used for various processing missions, including plutonium purification, oxide production, metal production, parts fabrication, plutonium recovery, and the recovery of americium (Am-241). The PFP has also been used for receipt and large scale storage of plutonium scrap and product materials. The PFP Final Safety Analysis Report (FSAR) was prepared by WHC to document the hazards associated with the facility, present safety analyses of potential accident scenarios, and demonstrate the adequacy of safety class structures, systems, and components (SSCs) and operational safety requirements (OSRs) necessary to eliminate, control, or mitigate the identified hazards. Documented in this Safety Evaluation Report (SER) is DOE's independent review and evaluation of the PFP FSAR and the basis for approval of the PFP FSAR. The evaluation is presented in a format that parallels the format of the PFP FSAR. As an aid to the reactor, a list of acronyms has been included at the beginning of this report. The DOE review concluded that the risks associated with conducting plutonium handling, processing, and storage operations within PFP facilities, as described in the PFP FSAR, are acceptable, since the accident safety analyses associated with these activities meet the WHC risk acceptance guidelines and DOE safety goals in SEN-35-91

Recommendations for plutonium colloid size determination

International Nuclear Information System (INIS)

Kosiewicz, S.T.

1984-02-01

This report presents recommendations for plutonium colloid size determination and summarizes a literature review, discussions with other researchers, and comments from equipment manufacturers. Four techniques suitable for plutonium colloid size characterization are filtration and ultrafiltration, gel permeation chromatography, diffusion methods, and high-pressure liquid chromatography (conditionally). Our findings include the following: (1) Filtration and ultrafiltration should be the first methods used for plutonium colloid size determination because they can provide the most rapid results with the least complicated experimental arrangement. (2) After expertise has been obtained with filtering, gel permeation chromatography should be incorporated into the colloid size determination program. (3) Diffusion methods can be used next. (4) High-pressure liquid chromatography will be suitable after appropriate columns are available. A plutonium colloid size characterization program with filtration/ultrafiltration and gel permeation chromatography has been initiated

Analytic determination of plutonium in the environment

International Nuclear Information System (INIS)

Ballada, J.

1967-01-01

The work described in this report was undertaken with a view to determining the plutonium content in the fall-out from nuclear explosions. In the first part are described in turn the importance of the problems due to the plutonium, the physico-chemical properties of the radioelement and the biological dangers which it presents. A detailed and critical analysis is made of the radio-toxicological determination of the plutonium as reported in the literature prior to this report. The second part consists in the presentation of a judicious choice of techniques making it possible to determine plutonium in air, rain-water, soils and ash. After a detailed description of the measurement equipment and the operational techniques which have been developed, a justification of these techniques is given with particular reference to their sensitivity and specificity. After a brief conclusion concerning the preceding chapters, the results are presented. These are then discussed in the ease of each element in which the plutonium has been determined. This discussion is concluded by a consideration of the importance of the occurrence of fall-out plutonium on problems relating to public health. From a consideration of 200 analyses carried out, it is concluded that the contribution of plutonium to the exposure of populations is still very small compared to that of natural radiation and that due to such fission products as strontium 90. The report includes 63 literature references, 26 figures and 11 tables. (author) [fr

The uranium-plutonium breeder reactor fuel cycle

International Nuclear Information System (INIS)

Salmon, A.; Allardice, R.H.

1979-01-01

All power-producing systems have an associated fuel cycle covering the history of the fuel from its source to its eventual sink. Most, if not all, of the processes of extraction, preparation, generation, reprocessing, waste treatment and transportation are involved. With thermal nuclear reactors more than one fuel cycle is possible, however it is probable that the uranium-plutonium fuel cycle will become predominant; in this cycle the fuel is mined, usually enriched, fabricated, used and then reprocessed. The useful components of the fuel, the uranium and the plutonium, are then available for further use, the waste products are treated and disposed of safely. This particular thermal reactor fuel cycle is essential if the fast breeder reactor (FBR) using plutonium as its major fuel is to be used in a power-producing system, because it provides the necessary initial plutonium to get the system started. In this paper the authors only consider the FBR using plutonium as its major fuel, at present it is the type envisaged in all, current national plans for FBR power systems. The corresponding fuel cycle, the uranium-plutonium breeder reactor fuel cycle, is basically the same as the thermal reactor fuel cycle - the fuel is used and then reprocessed to separate the useful components from the waste products, the useful uranium and plutonium are used again and the waste disposed of safely. However the details of the cycle are significantly different from those of the thermal reactor cycle. (Auth.)

Plutonium peroxide precipitation: review and current research

International Nuclear Information System (INIS)

Hagan, P.G.; Miner, F.J.

1980-01-01

Increasing the HNO 3 concentration decreases the filtration time but increases the plutonium concentration in the filtrate. A compromise was therefore necessary. If a minimum plutonium concentration is required in the filtrate, the acidity could be lowered to 1.9M with an approximate doubling in the filtration time. The H 2 O 2 concentration has little effect on filtration time. However, the higher the H 2 O 2 concentration, the less plutonium lost to the filtrate. Concentrations higher than the 22 moles/mole Pu recommended (at least up to 30 molar which was the highest investigated) would be beneficial if reagent costs are not excessive and production capacity exists for destroying the excess H 2 O 2 in the filtrate. Although the effect is not large, filtration time is shorter and the plutonium concentration in the filtrate is lower if metallic impurities are present. The slowest rate of H 2 O 2 addition investigated gives a plutonium peroxide precipitate with the fastest filtration time. The rate of addition has very little effect on the plutonium concentration in the filtrate. The temperature has little effect on the filtration time. 14 0 C is recommended since decomposition of H 2 O 2 would be slower at 14 0 C than at 22 0 C (min. Pu content in the filtrate). The effect of digestion time on both the filtration time and the plutonium content in the filtrate is minor, so the shortest digestion time investigated is recommended

Fluorescent determination of neptunium in plutonium

International Nuclear Information System (INIS)

Alexandruk, V.M.; Babaev, A.S.; Dem'yanova, T.A.; Stepanov, A.V.

1991-01-01

This paper describes a new procedure for direct determination of Neptunium in Plutonium using laser induced time resolved fluorescence method. The procedure based on measurement of fluorescence intensity of Neptunium followed its concentration in effective layer of pellet of calcium fluoride. Detection limit of determination of Neptunium is 2 10 -12 g. At the level of Neptunium content in Plutonium more than 5 ppm relative standard deviation is equal 0.08-0.12. For carrying out of single measurement it is necessary neither more nor less 5 mkg Plutonium

Plutonium Immobilization Can Loading Conceptual Design

Energy Technology Data Exchange (ETDEWEB)

Kriikku, E.

1999-05-13

'The Plutonium Immobilization Facility will encapsulate plutonium in ceramic pucks and seal the pucks inside welded cans. Remote equipment will place these cans in magazines and the magazines in a Defense Waste Processing Facility (DWPF) canister. The DWPF will fill the canister with glass for permanent storage. This report discusses the Plutonium Immobilization can loading conceptual design and includes a process block diagram, process description, preliminary equipment specifications, and several can loading issues. This report identifies loading pucks into cans and backfilling cans with helium as the top priority can loading development areas.'

Plutonium Immobilization Can Loading Conceptual Design

International Nuclear Information System (INIS)

Kriikku, E.

1999-01-01

'The Plutonium Immobilization Facility will encapsulate plutonium in ceramic pucks and seal the pucks inside welded cans. Remote equipment will place these cans in magazines and the magazines in a Defense Waste Processing Facility (DWPF) canister. The DWPF will fill the canister with glass for permanent storage. This report discusses the Plutonium Immobilization can loading conceptual design and includes a process block diagram, process description, preliminary equipment specifications, and several can loading issues. This report identifies loading pucks into cans and backfilling cans with helium as the top priority can loading development areas.'

New developments in the air transport of plutonium

International Nuclear Information System (INIS)

Andersen, J.A.

1978-01-01

A new package for the air transport of plutonium has been developed in response to a United States Public Law which restricts the US air transport of plutonium except for small medical devices. This new package, called PAT-1 for plutonium air transportable package model 1, is the result of the NRC-sponsored PARC (plutonium accident resistant container) project at Sandia Laboratories, Albuquerque. The PAT-1 package is designed to meet or exceed new criteria specified in NUREG-0360. These include a severe test sequence of impact (greater than 250 KTS) on an unyielding target, crush, puncture, slash, a large JP-4 fire for 1 hour, followed by water immersion, with stringent acceptance standards on plutonium release, nuclear shielding, and nuclear criticality. The PAT-1 package design features a high energy absorption capability with high-level fire protection. It weighs approximately 227 kg (500 lb) when loaded with 2 kg PuO 2 , and can accommodate up to 25 watts thermal energy from the plutonium load

The calculation of annual limits of intake for plutonium-239 in man using a bone model which allows for plutonium burial and recycling

International Nuclear Information System (INIS)

Priest, N.D.; Hunt, B.W.

1979-01-01

Values of the annual limit intake (ALI) for plutonium-239 in man have been calculated using committed dose equivalent limits as recommended by ICRP in Publication 26. The calculations were made using a multicompartment bone model which allows for plutonium burial and recycling in the skeleton. In one skeletal compartment, the growing surfaces of cortical bone, it is assumed that plutonium deposits are retained and are not subject to resorption or recycling. In the trabecular bone compartment plutonium is taken to be resorbed with either subsequent redeposition onto bone surfaces or retention in the bone marrow. ALIs for plutonium-239 have been calculated assuming a range of rates of bone accretion (0 to 32 μm yr -1 ), different amounts of plutonium retained in the marrow (0 to 60%) and a 20%, 45% or 70% deposition of plutonium in the skeleton from the blood. The calculations made using this bone model suggest that 750 Bq (20 nCi) is an appropriate ALI for the inhalation of class W and class Y plutonium compounds and that 830 kBq and 5 MBq (23 μCi and 136 μCi) are the appropriate ALIs for the ingestion of soluble and insoluble forms of plutonium respectively. (author)

The calculation of annual limits of intake for plutonium-239 in man using a bone model which allows for plutonium burial and recycling.

Science.gov (United States)

Priest, N D; Hunt, B W

1979-05-01

Values of the annual limit of intake (ALI) for plutonium-239 in man have been calculated using committed dose equivalent limits as recommended by ICRP in Publication 26. The calculations were made using a multicompartment bone model which allows for plutonium burial and recycling in the skeleton. In one skeletal compartment, the growing surfaces of cortical bone, it is assumed that plutonium deposits are retained and are not subject to resorption or recycling. In the trabecular bone compartment plutonium is taken to be resorbed with either subsequent redeposition onto bone surfaces or retention in the bone marrow. ALIs for plutonium-239 have been calculated assuming a range of rates of bone accretion (0-32 micron yr-1), different amounts of plutonium retained in the marrow (0-60%) and a 20%, 45% or 70% deposition of plutonium in the skeleton from the blood. The calculations made using this bone model suggest that 750 Bq (20 nCi) is an appropriate ALI for the inhalation of class W and class Y plutonium compounds and that 830 kBq and 5 MBq (23 muCi and 136 muCi) are the appropriate ALIs for the ingestion of soluble and insoluble forms of plutonium respectively.

Eine Analyse des Zusammenhangs zwischen dem Konsum von Alkopops und dem Problemverhalten von Jugendlichen

OpenAIRE

Metzner, Cornelia Beate Isabel

2007-01-01

Zielsetzung: In dieser Arbeit wird untersucht, ob bei Jugendlichen ein Zusammenhang zwischen dem Konsum von Alkopops einerseits und dem sonstigen Alkoholtrinkverhalten, dem Konsum von Zigaretten und illegalen Drogen sowie weiteren Risikoverhaltensweisen andererseits besteht, ferner ob sich Unterschiede im Verhalten von Jungen und Mädchen ergeben. Theoretischer und empirischer Hintergrund: �Alkopops�, d. h. Mischgetränke diverser Hersteller aus Likör bzw. Schnaps und Limonade sowie wein- ...

Contamination of living environment and human organism with plutonium

International Nuclear Information System (INIS)

Benes, J.

1981-01-01

The applicability of 239 Pu in nuclear power is discussed. The radiotoxic properties of plutonium, its tissue distribution and the effects of internal and external contamination are described. The contamination of the atmosphere, water, and soil with plutonium isotopes is discussed. Dosimetry is described of plutonium in the living and working environments as is plutonium determination in the human organism. (H.S.)

Plutonium Chemistry in the UREX+ Separation Processes

Energy Technology Data Exchange (ETDEWEB)

ALena Paulenova; George F. Vandegrift, III; Kenneth R. Czerwinski

2009-10-01

The project "Plutonium Chemistry in the UREX+ Separation Processes” is led by Dr. Alena Paulenova of Oregon State University under collaboration with Dr. George Vandegrift of ANL and Dr. Ken Czerwinski of the University of Nevada at Las Vegas. The objective of the project is to examine the chemical speciation of plutonium in UREX+ (uranium/tributylphosphate) extraction processes for advanced fuel technology. Researchers will analyze the change in speciation using existing thermodynamics and kinetic computer codes to examine the speciation of plutonium in aqueous and organic phases. They will examine the different oxidation states of plutonium to find the relative distribution between the aqueous and organic phases under various conditions such as different concentrations of nitric acid, total nitrates, or actinide ions. They will also utilize techniques such as X-ray absorbance spectroscopy and small-angle neutron scattering for determining plutonium and uranium speciation in all separation stages. The project started in April 2005 and is scheduled for completion in March 2008.

Constitutional problems in the handling of plutonium

International Nuclear Information System (INIS)

Witt, S. de.

1989-01-01

Reprocessing and final storage involve two different systems of nuclear energy utilization: with or without the use of plutonium. There is a choice available between these two systems. The paper discusss the constitutional implications of this choice. The permission of the use of plutonium as nuclear fuel by the Atomic Energy Law is irreconcilable with the Basic Law, i.e. the Constitution. If the corresponding provisions of the Atomic Energy Law are repealed, then only the plutonium-related branch will be revoked and not the legal permission of nuclear energy as a whole. The fact is not ignored that the Atomic Energy law does not permit the construction and operation of a plant or the handling of plutonium if this were to violate a basic right. However, the plutonium-related branch of nculear energy utilization inevitably results in such basic right violations; hence the Atomic Energy law is unconstitutional in this respect. (orig./HSCH) [de

Assessment of PWR plutonium burners for nuclear energy centers

International Nuclear Information System (INIS)

Frankel, A.J.; Shapiro, N.L.

1976-06-01

The purpose of the study was to explore the performance and safety characteristics of PWR plutonium burners, to identify modifications to current PWR designs to enhance plutonium utilization, to study the problems of deploying plutonium burners at Nuclear Energy Centers, and to assess current industrial capability of the design and licensing of such reactors. A plutonium burner is defined to be a reactor which utilizes plutonium as the sole fissile addition to the natural or depleted uranium which comprises the greater part of the fuel mass. The results of the study and the design analyses performed during the development of C-E's System 80 plant indicate that the use of suitably designed plutonium burners at Nuclear Energy Centers is technically feasible

Biological behaviour of plutonium inhaled by baboons as plutonium n-tributylphosphate complex. Comparison with ICRP models

International Nuclear Information System (INIS)

Metivier, H.; Duserre, C.; Rateau, G.; Legendre, N.; Masse, R.; Piechowski, J.; Menoux, B.

1989-01-01

In order to devise a model capable of calculating committed doses for workers contaminated by inhalation of plutonium tributylphosphate complex during reprocessing, we investigated the biokinetics of plutonium in baboons after inhalation of this chemical form. The animals were killed 0.6, 3, 15, 30, 90 and 365 days post inhalation. Urine and faeces were collected daily. After killing, the main organs were collected for chemical analysis. In order to improve our knowledge of the behaviour of systemic plutonium, three baboons were given an intravenous injection of Pu-TBP and were respectively killed 2, 30 and 365 days post injection. We observed that Pu-TBP could be classified as a W compound, with a half-time for lung clearance of 150 days. Urinary Pu excretion was 3 times higher than was expected from Durbin's model, suggesting that Pu introduced as Pu-TBP, is extremely mobile, and that the complex formed with blood proteins differs from the one formed after inhalation of plutonium nitrate. (author)

Spectrophotometers for plutonium monitoring in HB-line

Energy Technology Data Exchange (ETDEWEB)

Lascola, R. J. [Savannah River Site (SRS), Aiken, SC (United States); O' Rourke, P. E. [Savannah River Site (SRS), Aiken, SC (United States); Kyser, E. A. [Savannah River Site (SRS), Aiken, SC (United States); Immel, D. M. [Savannah River Site (SRS), Aiken, SC (United States); Plummer, J. R. [Savannah River Site (SRS), Aiken, SC (United States); Evans, E. V. [Savannah River Site (SRS), Aiken, SC (United States)

2016-02-12

This report describes the equipment, control software, calibrations for total plutonium and plutonium oxidation state, and qualification studies for the instrument. It also provides a detailed description of the uncertainty analysis, which includes source terms associated with plutonium calibration standards, instrument drift, and inter-instrument variability. Also included are work instructions for instrument, flow cell, and optical fiber setup, work instructions for routine maintenance, and drawings and schematic diagrams.

Plutonium contaminated materials research programme. Progress Report for 1983/84 from the Plutonium Contaminated Materials Working Party

International Nuclear Information System (INIS)

Higson, S.G.

1984-01-01

Plutonium contaminated material (PCM) is a generic term applied to a wide variety of materials which have become contaminated by plutonium compounds, by virtue of their use inside the primary containment of fuel cycle plants, but which generally have low beta gamma content. The report falls under the headings: introduction; organisation and role of the PCMWP; management practices; 1983/84 progress report (a) reduction of arisings; (b) plutonium measurement; (c) treatment of solid PCM; (d) treatment of alpha bearing liquid wastes; (e) actinide chemistry; (f) engineering objectives. (U.K.)

The radiological hazard of plutonium isotopes and specific plutonium mixtures

International Nuclear Information System (INIS)

Heindel, G.; Clow, J.; Inkret, W.; Miller, G.

1995-11-01

The US Department of Energy defines the hazard categories of its nuclear facilities based upon the potential for accidents to have significant effects on specific populations and the environment. In this report, the authors consider the time dependence of hazard category 2 (significant on-site effects) for facilities with inventories of plutonium isotopes and specific weapons-grade and heat-source mixtures of plutonium isotopes. The authors also define relative hazard as the reciprocal of the hazard category 2 threshold value and determine its time dependence. The time dependence of both hazard category 2 thresholds and relative hazards are determined and plotted for 10,000 years to provide useful information for planning long-term storage or disposal facilities

Cultural differences in human-computer interaction towards culturally adaptive human-machine interaction

CERN Document Server

Heimgärtner, Rüdiger

2012-01-01

Es wird eine Methode zur Bestimmung von quantitativ klassifizierenden kulturellen Variablen der Mensch-Maschine-Interaktion (MMI) präsentiert und in einem Werkzeug für die interkulturelle Interaktionsanalyse umgesetzt. Rüdiger Heimgärtner zeigt, dass MMI anhand der kulturell geprägten Interaktionsmuster des Benutzers automatisch an dessen kulturellen Hintergrund angepasst werden kann. Empfehlungen für das Design interkultureller Benutzungsschnittstellen sowie für die Architekturbildung kulturell-adaptiver Systeme runden die Arbeit ab. Der Arbeitsbericht der Dissertation ist in elektronischer F

Jeopardy alarm system - a building technology like any other technology?; Gefahrenmeldetechnik - eine Gebaeudetechnik wie jede andere?

Energy Technology Data Exchange (ETDEWEB)

Hegewald, B. [ZVEI, Fachkreis Ueberfall- und Einbruchmeldeanlagen, Frankfurt am Main (Germany)]|[Siemens AG, Muenchen

1995-12-31

In chapter 15 of the anthology about building control the jeopardy alarm system technology is described. The following aspects are discussed: importance of the safety, definition of jeopardy alarm systems, application of safety technique, instructions, guidelines and regulations, advantages of safety systems, integration or combination. (BWI) [Deutsch] Kapitel 15 des Sammelbandes ueber Buidling Control ist der Gefahrenmeldetechnik gewidmet. In diesem Zusammenhang wird auf folgende Themenbereiche eingegangen: Stellenwert der Sicherheit; Definition der Gefahrenmeldeanlagen; Einsatz der Sicherungstechnik; Vorschriften, Richtlinien und Bestimmung; Vorteile von Sicherungssystemen; Integration oder Kombination. (BWI)

Study of the reaction of uranium and plutonium with bone char

International Nuclear Information System (INIS)

Silver, G.L.; Koenst, J.W.

1977-01-01

A study of the reaction of plutonium with a commercial bone char indicates that this bone char has a high capacity for removing plutonium from aqueous wastes. The adsorption of plutonium by bone char is pH dependent, and for plutonium(IV) polymer appears to be maximized near pH 7.3 for plutonium concentrations typical of some waste streams. Adsorption is affected by dissolved salts, especially calcium and phosphate salts. Freundlich isotherms representing the adsorption of uranium and plutonium have been prepared. The low potential imposed upon aqueous solutions by commercial bone char is adequate for reduction of hexavalent plutonium to a lower plutonium oxidation state

SEPARATION OF URANIUM, PLUTONIUM, AND FISSION PRODUCTS

Science.gov (United States)

Spence, R.; Lister, M.W.

1958-12-16

Uranium and plutonium can be separated from neutron-lrradiated uranium by a process consisting of dissolvlng the lrradiated material in nitric acid, saturating the solution with a nitrate salt such as ammonium nitrate, rendering the solution substantially neutral with a base such as ammonia, adding a reducing agent such as hydroxylamine to change plutonium to the trivalent state, treating the solution with a substantially water immiscible organic solvent such as dibutoxy diethylether to selectively extract the uranium, maklng the residual aqueous solutlon acid with nitric acid, adding an oxidizing agent such as ammonlum bromate to oxidize the plutonium to the hexavalent state, and selectlvely extracting the plutonium by means of an immlscible solvent, such as dibutoxy dlethyletber.

Investigation of plutonium abundance and age analysis

Energy Technology Data Exchange (ETDEWEB)

Huailong, Wu; Jian, Gong; Fanhua, Hao [China Academy of Engineering Physics, Mianyang (China). Inst. of Nuclear Physics and Chemistry

2007-06-15

Based on spectra analysis software, all of the plutonium material peak counts are analyzed. Relatively efficiency calibration is done by the non-coupling peaks of {sup 239}Pu. By using the known isotopes half life and yield, the coupling peaks counts are allocated by non-coupling peaks, consequently the atom ratios of each isotope are gotten. The formula between atom ratio and abundance or age is deduced by plutonium material isotopes decay characteristic. And so the abundance and age of plutonium material is gotten. After some re- peat measurements for a plutonium equipment are completed, a comparison between our analysis results and PC-FRAM and the owner's reference results are done. (authors)

Plutonium in the arctic marine environment--a short review.

Science.gov (United States)

Skipperud, Lindis

2004-06-18

Anthropogenic plutonium has been introduced into the environment over the past 50 years as the result of the detonation of nuclear weapons and operational releases from the nuclear industry. In the Arctic environment, the main source of plutonium is from atmospheric weapons testing, which has resulted in a relatively uniform, underlying global distribution of plutonium. Previous studies of plutonium in the Kara Sea have shown that, at certain sites, other releases have given rise to enhanced local concentrations. Since different plutonium sources are characterised by distinctive plutonium-isotope ratios, evidence of a localised influence can be supported by clear perturbations in the plutonium-isotope ratio fingerprints as compared to the known ratio in global fallout. In Kara Sea sites, such perturbations have been observed as a result of underwater weapons tests at Chernaya Bay, dumped radioactive waste in Novaya Zemlya, and terrestrial runoff from the Ob and Yenisey Rivers. Measurement of the plutonium-isotope ratios offers both a means of identifying the origin of radionuclide contamination and the influence of the various nuclear installations on inputs to the Arctic, as well as a potential method for following the movement of water and sediment loads in the rivers.

Titanisierung von Implantatoberflächen

Science.gov (United States)

Zimmermann, Hanngörg; Heinlein, Markus; Guldner, Norbert W.

Titan gilt seit Jahrzehnten als einer der wichtigsten Implantatwerkstoffe in der Medizin. Neben den guten mechanischen Eigenschaften (Leichtigkeit, hohe Festigkeit etc.), besitzen Titanimplantate vor allem eine hervorragende Körperverträglichkeit, so dass die Implantate optimal in den humanen Organismus integriert werden [1]. Ist jedoch aufgrund der Anforderungen an das Implantat eine hohe Flexibilität und/ oder Elastizität gefragt, so scheidet der Werkstoff Titan aufgrund seiner spröden und unflexiblen Materialeigenschaften aus. Die Folge ist der Einsatz von Implantatmaterialien, sowohl künstlichen als auch biologischen Ursprungs, welche nicht selten eine unzureichende Biokompatibilität aufweisen und somit zu Fremdköper- und immunologischen Reaktionen und Einkapselung des Implantates führen können. Die Erhöhung der Körperverträglichkeit, eine Adaption an das biologische Umfeld und eine hohe Biokompatibilität sind demzufolge die wichtigsten Eigenschaften bei der bedarfsgerechten Herstellung von Implantaten und Implantatoberflächen. Zur Gestaltung von innovativen, biokompatiblen Oberflächen stehen unterschiedliche technische Lösungsansätze zur Verfügung. Zum einen besteht die Möglichkeit, geeignete Oberflächeneigenschaften aus dem Grundmaterial selbst zu optimieren. Dies geschieht unter anderem durch Modifikation der Werkstoffoberflächen in Form von Texturierungen und Oberflächenrauhigkeiten. Zum anderen können die Oberflächeneigenschaften unabhängig von denen des Trägermaterials gestaltet werden. Durch Funktionalisierung der Oberflächen mit geeigneten Beschichtungen oder der Zugabe von Medikamenten (Drug Eluting) werden die Kunststoffimplantate dahingehend verändert, dass eine Steigerung der Körperakzeptanz erreicht wird. Die Titanbeschichtung von Implantatoberflächen kombiniert die positiven Materialeigenschaften von Titan und Polymer.

Radiation damage and annealing in plutonium tetrafluoride

Science.gov (United States)

McCoy, Kaylyn; Casella, Amanda; Sinkov, Sergey; Sweet, Lucas; McNamara, Bruce; Delegard, Calvin; Jevremovic, Tatjana

2017-12-01

A sample of plutonium tetrafluoride that was separated prior to 1966 at the Hanford Site in Washington State was analyzed at the Pacific Northwest National Laboratory (PNNL) in 2015 and 2016. The plutonium tetrafluoride, as received, was an unusual color and considering the age of the plutonium, there were questions about the condition of the material. These questions had to be answered in order to determine the suitability of the material for future use or long-term storage. Therefore, thermogravimetric/differential thermal analysis and X-ray diffraction evaluations were conducted to determine the plutonium's crystal structure, oxide content, and moisture content; these analyses reported that the plutonium was predominately amorphous and tetrafluoride, with an oxide content near ten percent. Freshly fluorinated plutonium tetrafluoride is known to be monoclinic. During the initial thermogravimetric/differential thermal analyses, it was discovered that an exothermic event occurred within the material near 414 °C. X-ray diffraction analyses were conducted on the annealed tetrafluoride. The X-ray diffraction analyses indicated that some degree of recrystallization occurred in conjunction with the 414 °C event. The following commentary describes the series of thermogravimetric/differential thermal and X-ray diffraction analyses that were conducted as part of this investigation at PNNL.

Radiation damage and annealing in plutonium tetrafluoride

International Nuclear Information System (INIS)

McCoy, Kaylyn; Casella, Amanda; Sinkov, Sergey

2017-01-01

A sample of plutonium tetrafluoride that was separated prior to 1966 at the Hanford Site in Washington State was analyzed at the Pacific Northwest National Laboratory (PNNL) in 2015 and 2016. The plutonium tetrafluoride, as received, was an unusual color and considering the age of the plutonium, there were questions about the condition of the material. These questions had to be answered in order to determine the suitability of the material for future use or long-term storage. Therefore, thermogravimetric/differential thermal analysis and X-ray diffraction evaluations were conducted to determine the plutonium's crystal structure, oxide content, and moisture content; these analyses reported that the plutonium was predominately amorphous and tetrafluoride, with an oxide content near ten percent. Freshly fluorinated plutonium tetrafluoride is known to be monoclinic. And during the initial thermogravimetric/differential thermal analyses, it was discovered that an exothermic event occurred within the material near 414 °C. X-ray diffraction analyses were conducted on the annealed tetrafluoride. The X-ray diffraction analyses indicated that some degree of recrystallization occurred in conjunction with the 414 °C event. This commentary describes the series of thermogravimetric/differential thermal and X-ray diffraction analyses that were conducted as part of this investigation at PNNL.

Reclamation of plutonium from pyrochemical processing residues

International Nuclear Information System (INIS)

Gray, L.W.; Gray, J.H.; Holcomb, H.P.; Chostner, D.F.

1987-04-01

Savannah River Laboratory (SRL), Savannah River Plant (SRP), and Rocky Flats Plant (RFP) have jointly developed a process to recover plutonium from molten salt extraction residues. These NaCl, KCL, and MgCl 2 residues, which are generated in the pyrochemical extraction of 241 Am from aged plutonium metal, contain up to 25 wt % dissolved plutonium and up to 2 wt % americium. The overall objective was to develop a process to convert these residues to a pure plutonium metal product and discardable waste. To meet this objective a combination of pyrochemical and aqueous unit operations was used. The first step was to scrub the salt residue with a molten metal (aluminum and magnesium) to form a heterogeneous ''scrub alloy'' containing nominally 25 wt % plutonium. This unit operation, performed at RFP, effectively separated the actinides from the bulk of the chloride salts. After packaging in aluminum cans, the ''scrub alloy'' was then dissolved in a nitric acid - hydrofluoric acid - mercuric nitrate solution at SRP. Residual chloride was separated from the dissolver solution by precipitation with Hg 2 (NO 3 ) 2 followed by centrifuging. Plutonium was then separated from the aluminum, americium and magnesium using the Purex solvent extraction system. The 241 Am was diverted to the waste tank farm, but could be recovered if desired

Plutonium in coniferous forests

International Nuclear Information System (INIS)

Rantavaara, A.; Kostiainen, E.

2002-01-01

Our aim was to study the uptake of plutonium by trees, undervegetation and some wild foods. The ratio of 238 Pu/ 239,240 Pu in soil samples was determined for comparisons of the fallout origin. In twelve years the Chernobyl derived plutonium has not reached the mineral soil. This refers to a very slow downward migration in podsolic soil. The study confirmed also the low Pu uptake by vegetation and an insignificant contribution to human doses through wild foods. (au)

The first metallurgical tests on plutonium

International Nuclear Information System (INIS)

Grison, E.; Abramson, R.; Anselin, F.; Monti, H.

1958-01-01

Metallic plutonium was first prepared in France in January 1956, as soon as we had access to quantities of the order of several grams of plutonium, which had been extracted from the rods of the pile EL2 at Saclay. Since up to the present this reactor, of thermal power 2 000 kW, has been our only source of plutonium, we have so far only worked on experimental quantities sufficient for the basic tests but not for tests on a scale of possible applications. It is this work, carried out during this phase of preliminary research, which is described below. With the starting up of the plutonium extraction plant at Marcoule, where the reactor G1 has been operating at power for more than a year, we shall go on next to a another order of magnitude which will allow the manufacture and experimentation of prototype fuel elements. (author) [fr

Plutonium and U-233 mines

International Nuclear Information System (INIS)

Milgram, M.S.

1983-08-01

A comparison is made among second generation reactor systems fuelled primarily with fissile plutonium and/or U-233 in uranium or thorium. This material is obtained from irradiated fuel from first generation CANDU reactors fuelled by natural or enriched uranium and thorium. Except for plutonium-thorium reactors, second generation reactors demand similar amounts of reprocessing throughput, but the most efficient plutonium burning systems require a large prior allocation of uranium. Second generation reactors fuelled by U-233 make more efficient use of resources and lead to more flexible fuelling strategies, but require development of first generation once-through thorium cycles and early demonstration of the commercial viability of thorium fuel reprocessing. No early implementation of reprocessing technology is required for these cycles

Investigation on the attribute detection of plutonium oxide

International Nuclear Information System (INIS)

Liu Suping; Hao Fanhua; Gong Jian; Wu Huailong; Hu Guangchun; Hu Yongbo

2006-01-01

A long-term detection of the 871 keV gamma-ray emitted from two PuO 2 samples (100 g recovered powder and 8 g pure powder) has been conduced with a high resolution HPGe spectrometer in a lead-shielded chamber. An on-site detection of the 871 keV gamma-ray emitted from 200 g recovered PuO 2 powder has also been performed. Although the 871 keV peak can be observed in all 3 samples, other characteristic gamma-rays related to the existence of oxygen are not seen. The 871 keV peak is absent in spectra acquired from metal plutonium samples, which can answer whether the plutonium material in a sealed container is metal plutonium or plutonium oxide, i.e. the 871 keV gamma-ray can be an evidence for the absence of metal plutonium. The 871 keV peak is strong in the spectrum of 200 g recovered PuO 2 sample. A software of plutonium abundance and age analysis developed by ourselves can identify the 871 keV peak from a spectrum of 10 min. If the system is appropriately improved, it can be used to detect attribute of plutonium oxide through identifying 871 keV gamma-ray peak. (authors)

Determination of cartilage thickness in the ankle joint. MRT (1,5 T) comparative anatomical study; Bestimmung der Knorpeldicke am oberen Sprunggelenk. Eine MRT(1,5 T)-anatomische Vergleichsstudie

Energy Technology Data Exchange (ETDEWEB)

Trattnig, S. [Universitaetsklinik fuer Radiodiagnostik, Wien (Austria). Klinische Einrichtung Magnet Resonanz und Abt. fuer Osteoradiologie]|[Ludwig Boltzmann Inst. fuer Radiologische Tumordiagnostik, Wien (Austria); Breitenseher, M.J. [Universitaetsklinik fuer Radiodiagnostik, Wien (Austria). Klinische Einrichtung Magnet Resonanz und Abt. fuer Osteoradiologie]|[Ludwig Boltzmann Inst. fuer Radiologische Tumordiagnostik, Wien (Austria); Huber, M. [Pathologisch-Bakteriologisches Inst. Baumgartner Hoehe, Wien (Austria); Zettl, R. [Orthopaedisches Krankenhaus Gersthof, Wien (Austria); Rottmann, B. [Universitaetsklinik fuer Radiodiagnostik, Wien (Austria). Klinische Einrichtung Magnet Resonanz und Abt. fuer Osteoradiologie]|[Ludwig Boltzmann Inst. fuer Radiologische Tumordiagnostik, Wien (Austria); Haller, J. [Hanuschkrankenhaus, Wien (Austria). Radiologische Abt.; Imhof, H. [Universitaetsklinik fuer Radiodiagnostik, Wien (Austria). Klinische Einrichtung Magnet Resonanz und Abt. fuer Osteoradiologie]|[Ludwig Boltzmann Inst. fuer Radiologische Tumordiagnostik, Wien (Austria)

1997-04-01

Purpose: The aim of this study was to evaluate the accuracy of MRI in the measurement of cartilage thickness of the ankle joint in comparison to pathologic and histologic specimens. Patients and methods: The ankle joints of four fresh cadaver feet were imaged on a 1.5 T MR-unit in the coronal plane. Standard T{sub 1}-weighted spin echo (SE) and a T{sub 1}-weighted 3D-GE (FLASH-3D) sequence with fat saturation were applied. Following MR imaging, the talus was explanted and cut parallel to the MR images for macroscopic evaluation and histologic specimens were prepared. MRI measurements of the cartilage thickness of the talus were carried out in two ways: Without and with consideration of a transition zone of intermediate signal intensity between hyperintense cartilage and hypointense cortical bone. The data were compared with the anatomic specimens as the gold standard expressing the difference as a percentage value. On histologic specimens thickness of deep calcified cartilage layer was measured. Results: Measurements without the transition zone showed a mean underestimation of talus cartilage thickness of 46.8% (41.3-52.1) for T{sub 1}-SE and 47.5% (43.1-52.1) for fat saturated FLASH-3D images. Considering the transition zone the mean values were 25.0% (23.1-26.2) and 14.1% (6.7-21.5). The histologic specimens showed a three-fold increase of thickness of deep calcified cartilage layer. Conclusions: Measurements of the cartilage layer of the ankle joint on MR images are only accurate if the transition zone (calcified cartilage layer) is considered and the optimal pulse sequence (FLASH-3D-fat-sat) is applied. (orig.) [Deutsch] Ziel: Die Frage, ob die MRT die Dicke des Knorpels exakt bestimmen kann, wird kontrovers diskutiert. Ziel der Studie war die Bestimmung der Knorpeldicke am oberen Sprunggelenk mit der MRT im Vergleich zum anatomischen Praeparat. Material und Methode: Sprunggelenke von 4 Leichen wurden auf einem 1,5 Tesla MR-Geraet mittels T{sub 1}-betonter Spin

Physics of plutonium recycling

International Nuclear Information System (INIS)

2003-01-01

The commercial recycling of plutonium as PuO 2 /UO 2 mixed-oxide (MOX) fuel is an established practice in pressurised water reactors (PWRs) in several countries, the main motivation being the consumption of plutonium arising from spent fuel reprocessing. Although the same motivating factors apply in the case of boiling water reactors (BWRs), they have lagged behind PWRs for various reasons, and MOX utilisation in BWRs has been implemented in only a few reactors to date. One of the reasons is that the nuclear design of BWR MOX assemblies (or bundles) is more complex than that of PWR assemblies. Recognizing the need and the timeliness to address this issue at the international level, the OECD/NEA Working Party on the Physics of Plutonium Fuels and Innovative Fuel Cycles (WPPR) conducted a physics code benchmark test for a BWR assembly. This volume reports on the benchmark results and conclusions that can be drawn from it. (authors)

Plutonium in the environment

International Nuclear Information System (INIS)

Kudo, A.

2001-01-01

The first volume of the new series, Radioactivity in the Environment, focuses on the environmental occurrence, the speciation, the behaviour, the fate, the applications and the health consequences of that much-feared and much-publicised element, plutonium. Featuring a collection of selected, peer-reviewed, up-to-date papers by leading researchers in the field, this work provides a state-of-the-art description of plutonium in the environment. This title helps to explain where present frontiers are drawn in our continuing efforts to understand the science of environmental plutonium and will help to place widespread concerns into perspective. As a whole this new book series on environmental radioactivity addresses, at academic research level, the key aspects of this socially important and complex interdisciplinary subject. Presented objectively and with the ultimate authority gained from the many contributions by the world's leading experts, the negative and positive consequences of having a radioactive world around us will be documented and given perspective. refs

Recovery of plutonium from pyrolysis and incineration residues

International Nuclear Information System (INIS)

Isaacs, J.W.; McDonald, L.A.; Roberts, W.G.; Sutcliffe, P.W.; Wilkins, J.D.

1981-01-01

The effect of ashes prepared from typical plutonium-handling, glove box, combustible wastes on the dissolution of PuO 2 is described. Synthetic ashes have been prepared by doping inactively-prepared ashes with various plutonium-containing compounds, followed by heating at temperatures in the range 550-1200 0 C. The resulting ashes have been leach-tested in order to provide information on the relationship between leachability, the nature of the ashes, the type of plutonium contamination and temperature of thermal treatment. Optimum temperatures for the recovery of plutonium and for the production of inert ''slag'' -type residues have been identified. A furnace for producing model incinerator ashes and pyrolysis chars under carefully controlled conditions is described. Preliminary results on the leaching of these plutonium-active ashes and chars are discussed. (author)

Continuous precipitation process of plutonium salts

International Nuclear Information System (INIS)

Richard, P.

1967-03-01

This work concerns the continuous precipitation process of plutonium oxalate. Investigations about the solubility of different valence states in nitric-oxalic and in nitric-sulfuric-oxalic medium lead to select the precipitation process of tetravalent plutonium oxalate. Settling velocity and granulometry of tetravalent oxalate plutonium have been studied with variation of several precipitation parameters such as: temperature, acidity, excess of oxalic acid and aging time. Then are given test results of some laboratory continuous apparatus. Conditions of operation with adopted tubular apparatus are defined in conclusion. A flow-sheet is given for a process at industrial scale. (author) [fr

Nondestructive analysis of plutonium contaminated soil

International Nuclear Information System (INIS)

Smith, H.E.; Taylor, L.H.

1977-01-01

Plutonium contaminated soil is currently being removed from a covered liquid waste disposal trench near the Pu Processing facility on the Hanford Project. This soil with the plutonium is being mined using remote techniques and equipment. The mined soil is being packaged for placement into retrievable storage, pending possible recovery. To meet the requirements of criticality safety and materials accountability, a nondestructive analysis program has been developed to determine the quantity of plutonium in each packing-storage container. This paper describes the total measurement program: equipment systems, calibration techniques, matrix assumption, instrument control program and a review of laboratory operating experience

Computerized plutonium laboratory-stack monitoring system

International Nuclear Information System (INIS)

Stafford, R.G.; DeVore, R.K.

1977-01-01

The Los Alamos Scientific Laboratory has recently designed and constructed a Plutonium Research and Development Facility to meet design criteria imposed by the United States Energy Research and Development Administration. A primary objective of the design criteria is to assure environmental protection and to reliably monitor plutonium effluent via the ventilation exhaust systems. A state-of-the-art facility exhaust air monitoring system is described which establishes near ideal conditions for evaluating plutonium activity in the stack effluent. Total and static pressure sensing manifolds are incorporated to measure average velocity and integrated total discharge air volume. These data are logged at a computer which receives instrument data through a multiplex scanning system. A multipoint isokinetic sampling assembly with associated instrumentation is described. Continuous air monitors have been designed to sample from the isokinetic sampling assembly and transmit both instantaneous and integrated stack effluent concentration data to the computer and various cathode ray tube displays. The continuous air monitors also serve as room air monitors in the plutonium facility with the primary objective of timely evacuation of personnel if an above tolerance airborne plutonium concentration is detected. Several continuous air monitors are incorporated in the ventilation system to assist in identification of release problem areas

Effect of compositional variation in plutonium on process shielding design

Energy Technology Data Exchange (ETDEWEB)

Brown, T.H.

1997-11-01

Radiation dose rate from plutonium with high {sup 239}Pu content varies with initial nuclidic content, radioactive decay time, and impurity elemental content. The two idealized states of old plutonium and clean plutonium, whose initial compositions are given, provide approximate upper and lower bounds on dose rate variation. Whole-body dose rates were calculated for the two composition states, using unshielded and shielded plutonium spheres of varying density. The dose rates from these variable density spheres are similar to those from expanded plutonium configurations encountered during processing. The dose location of 40 cm from the sphere center is representative of operator standoff for direct handling of plutonium inside a glove box. The results have shielding implications for glove boxes with only structurally inherent shielding, especially for processing of old plutonium in an expanded configuration. Further reduction in total dose rate by using lead to reduce photon dose rate is shown for two density cases representing compact and expanded plutonium configurations.

Effect of compositional variation in plutonium on process shielding design

International Nuclear Information System (INIS)

Brown, T.H.

1997-11-01

Radiation dose rate from plutonium with high 239 Pu content varies with initial nuclidic content, radioactive decay time, and impurity elemental content. The two idealized states of old plutonium and clean plutonium, whose initial compositions are given, provide approximate upper and lower bounds on dose rate variation. Whole-body dose rates were calculated for the two composition states, using unshielded and shielded plutonium spheres of varying density. The dose rates from these variable density spheres are similar to those from expanded plutonium configurations encountered during processing. The dose location of 40 cm from the sphere center is representative of operator standoff for direct handling of plutonium inside a glove box. The results have shielding implications for glove boxes with only structurally inherent shielding, especially for processing of old plutonium in an expanded configuration. Further reduction in total dose rate by using lead to reduce photon dose rate is shown for two density cases representing compact and expanded plutonium configurations

Laser diagnosis and plasma technology: fundamentals for reduction of emissions and fuel consumption in DI internal combustion engines. Spray/wall-interaction under diesel engine conditions. Final report; Laserdiagnostische und plasmatechnologische Grundlagen zur Verminderung von Emissionen und Kraftstoffverbrauch von DI-Verbrennungsmotoren. Spray/Wand-Wechselwirkung bei der motorischen Einspritzung. Abschlussbericht

Energy Technology Data Exchange (ETDEWEB)

Renz, U.; Meingast, U.

2001-02-01

Kraftstoffsprays auf eine Wand sind unter motorischen Bedingungen in einer Einspritzkammer mit erweiterten laseroptischen Verfahren experimentell untersucht worden. Dabei wurden eine Mikroskop-Visualierungstechnik zur Strahlcharakterisierung, ein angepasstes Phasen-Doppler-Anemometer (PDA) zur Bestimmung von Groesse und Geschwindigkeit der Tropfen, eine auf Fluoreszenz der Fluessigkeit (LIF) basierende Filmdickenmesstechnik und Oberflaechenthermoelemente zur Bestimmung des Wandwaermestroms eingesetzt. Die numerische Vorhersage des Einspritzvorgangs mit einem um aus der Literatur uebernommenen Spray/Wandmodellen und einem Waermeuebergangsmodell erweiterten Stroemungsberechnungsprogramm (CFD) zeigt zwar qualitativ gute Uebereinstimmung, muss aber weiter verbessert werden. Die meist unter atmosphaerischen Bedingungen ermittelten Kennzahlgesetze koennen nicht ohne Einschraenkung auf den Hochdruck- und Hochtemperaturbereich uebertragen werden. Hier ergibt sich fuer die Zukunft weiterer Forschungsbedarf. Mit den experimentellem Ergebnissen ist eine umfassende Grundlage geschaffen worden, die die Validierung des Zusammenspiels dieser Modelle ermoeglicht. Der Einsatzbereich Messtechniken konnte an die Bedingungen angepasst werden. (orig.)

Safe disposal of surplus plutonium

Science.gov (United States)

Gong, W. L.; Naz, S.; Lutze, W.; Busch, R.; Prinja, A.; Stoll, W.

2001-06-01

About 150 tons of weapons grade and weapons usable plutonium (metal, oxide, and in residues) have been declared surplus in the USA and Russia. Both countries plan to convert the metal and oxide into mixed oxide fuel for nuclear power reactors. Russia has not yet decided what to do with the residues. The US will convert residues into a ceramic, which will then be over-poured with highly radioactive borosilicate glass. The radioactive glass is meant to provide a deterrent to recovery of plutonium, as required by a US standard. Here we show a waste form for plutonium residues, zirconia/boron carbide (ZrO 2/B 4C), with an unprecedented combination of properties: a single, radiation-resistant, and chemically durable phase contains the residues; billion-year-old natural analogs are available; and criticality safety is given under all conceivable disposal conditions. ZrO 2/B 4C can be disposed of directly, without further processing, making it attractive to all countries facing the task of plutonium disposal. The US standard for protection against recovery can be met by disposal of the waste form together with used reactor fuel.

Management of Russian military plutonium

International Nuclear Information System (INIS)

Zaleski, C.P.

1996-01-01

The objective of this paper is to propose and discuss a solution which enables storing as quickly as possible all weapons-grade plutonium from Russian military program in a way which would prevent diversion. Two main conditions apply to this solution. First, it should be achieved in a manner acceptable to Russian government, notably by preserving plutonium for possible future energy production, and second, the economics of the total system should be good enough to ensure no charge or limited charge for the storage of plutonium. A proposal is made to store plutonium in a specially designed fast reactor or specially designed reactor core. This solution could be favorable in comparison to other solutions applying the above mentioned goal and conditions. Additionally the proposed solution would have the following side advantages: utilizing available personnel and installations of the Russian nuclear complex; providing possible basis for decommissioning of older and less safe Russian reactors; giving experience of construction and operation of a series of sodium-cooled fast reactors. The major problem however is the need for large capital investment with the risk of getting no adequate return on investment due to difficult political and economic situation in Russia

Economic analysis of self-generated plutonium recycling in light water reactor

International Nuclear Information System (INIS)

Deguchi, Morimoto; Hirabayashi, Fumio; Yumoto, Ryozo

1978-01-01

This paper describes on the economics of plutonium recycle to light water reactors (LWRs). In the situation that plutonium market does not exist, it is realistic for utilities to recycle the self-generated plutonium to their own reactors. The economic incentive to recycle self-generated plutonium, plutonium fuel fabrication penalty, and the dependence of fuel cycle cost on fuel cycle cost parameters are considered. In recycling self-generated plutonium, two alternatives for fuel element design are feasible. Those are the all-plutonium design and the island design. In the present analysis, the all-plutonium design was chosen for PWRs. The calculation of reactivity variation along with burnup for both uranium fuel and plutonium fuel was done with LASER-PNC code. Plutonium inventory and other nuclear data were calculated with CHAIN code. It is expected that equilibrium composition is reached after 5 or 6 times of recycling. For the calculation of fuel cycle cost, MITCOST code was used. The recent increase in the prices of uranium ore, enrichment and reprocessing services was taken into account. The fuel cycle cost of plutonium recycle is lower than that of uranium fuel cycle within a certain limit of plutonium fabrication penalty. It is shown that the fabrication penalty of about 1250 dollar/kgHM for each plutonium successive recycle reduces the cost difference to zero. The change in other cost components affects break-even fabrication penalty, in which the fuel cycle cost of plutonium recycle is equal to that of uranium cycle. (Kato, T.)

Physics of plutonium recycling: volume V. Plutonium recycling in fast reactors

International Nuclear Information System (INIS)

1996-01-01

As part of a programme proposed by the OECD/NEA Working Party on Physics of Plutonium Recycling (WPPR) to evaluate different scenarios for the use of plutonium, fast reactor physics benchmarks were developed. In this report, the multi-recycle performance of the metal-fuelled benchmark is evaluated. Benchmark results assess the reactor performance and toxicity behaviour in a closed nuclear fuel cycle for a parametric variation of the conversion ratio between 0.5 and 1.0. Results indicate that a fast burner reactor closed fuel cycle can be utilised to significantly reduce the radiotoxicity originating in the LWR cycle which would otherwise be destined for burial. (Author). tabs., figs., refs

Decontamination of Battelle-Columbus' Plutonium Facility. Final report

International Nuclear Information System (INIS)

Rudolph, A.; Kirsch, G.; Toy, H.L.

1984-01-01

The Plutonium Laboratory, owned and operated by Battelle Memorial Institute's Columbus Division, was located in Battelle's Nuclear Sciences area near West Jefferson, Ohio, approximately 17 miles west of Columbus, Ohio. Originally built in 1960 for plutonium research and processing, the Plutonium Laboratory was enlarged in 1964 and again in 1967. With the termination of the Advanced Fuel Program in March, 1977, the decision was made to decommission the Plutonium Laboratory and to decontaminate the building for unrestricted use. Decontamination procedures began in January, 1978. All items which had come into contact with radioactivity from the plutonium operations were cleaned or disposed of through prescribed channels, maintaining procedures to ensure that D and D operations would pose no risk to the public, the environment, or the workers. The entire program was conducted under the cognizance of DOE's Chicago Operations Office. The building which housed the Plutonium Laboratory has now been decontaminated to levels allowing it to house ordinary laboratory and office operations. A ''Finding of No Significant Impact'' (FNSI) was issued in May, 1980

New developments in the air transport of plutonium

International Nuclear Information System (INIS)

Andersen, J.A.

1978-01-01

A new package for the air transport of plutonium has been developed in response to a United States Public Law which restricts the U.S. air transport of plutonium except for small medical devices. This new package, called PAT-1 for plutonium air transportable package model 1, is the result of the NRC-sponsored (NRC=U.S. Nuclear Regulatory Commission.) PARC (plutonium accident resistant container) project at Sandia Laboratories, Albuquerque. The PAT-1 package is designed to meet or exceed new criteria specified in NUREG-0360. These inclued a severe test sequence of impact (>250 knots) on an unyielding target, crush, puncture, slash, a large JP-4 fire for 1 hour, followed by water immersion, with stringent acceptance standards on plutonium release, nuclear shielding, and nuclear criticality. The PAT-1 package design features a high energy absorption capability with high-level fire protection. It weighs approximately 227 kg (500 lb) when loaded with 2 kg PuO 2 , and can accommodate up to 25 watts thermal energy from the plutonium load

Waste minimization at a plutonium processing facility

International Nuclear Information System (INIS)

Pillay, K.K.S.

1995-01-01

As part of Los Alamos National Laboratory's (LANL) mission to reduce the nuclear danger throughout the world, the plutonium processing facility at LANL maintains expertise and skills in nuclear weapons technologies as well as leadership in all peaceful applications of plutonium technologies, including fuel fabrication for terrestrial and space reactors and heat sources and thermoelectric generators for space missions. Another near-term challenge resulted from two safety assessments performed by the Defense Nuclear Facilities Safety Board and the U.S. Department of Energy during the past two years. These assessments have necessitated the processing and stabilization of plutonium contained in tons of residues so that they can be stored safely for an indefinite period. This report describes waste streams and approaches to waste reduction of plutonium management

Plutonium Chemistry in the UREX Separation Processes

International Nuclear Information System (INIS)

Paulenova, Alena; Vandegrift, George F. III; Czerwinski, Kenneth R.

2009-01-01

The objective of the project is to examine the chemical speciation of plutonium in UREX+ (uranium/tributylphosphate) extraction processes for advanced fuel technology. Researchers will analyze the change in speciation using existing thermodynamics and kinetic computer codes to examine the speciation of plutonium in aqueous and organic phases. They will examine the different oxidation states of plutonium to find the relative distribution between the aqueous and organic phases under various conditions such as different concentrations of nitric acid, total nitrates, or actinide ions. They will also utilize techniques such as X-ray absorbance spectroscopy and small-angle neutron scattering for determining plutonium and uranium speciation in all separation stages. The project started in April 2005 and is scheduled for completion in March 2008.

Fuel cycles using adulterated plutonium

International Nuclear Information System (INIS)

Brooksbank, R.E.; Bigelow, J.E.; Campbell, D.O.; Kitts, F.G.; Lindauer, R.B.

1978-01-01

Adjustments in the U-Pu fuel cycle necessitated by decisions made to improve the nonproliferation objectives of the US are examined. The uranium-based fuel cycle, using bred plutonium to provide the fissile enrichment, is the fuel system with the highest degree of commercial development at the present time. However, because purified plutonium can be used in weapons, this fuel cycle is potentially vulnerable to diversion of that plutonium. It does appear that there are technologically sound ways in which the plutonium might be adulterated by admixture with 238 U and/or radioisotopes, and maintained in that state throughout the fuel cycle, so that the likelihood of a successful diversion is small. Adulteration of the plutonium in this manner would have relatively little effect on the operations of existing or planned reactors. Studies now in progress should show within a year or two whether the less expensive coprocessing scheme would provide adequate protection (coupled perhaps with elaborate conventional safeguards procedures) or if the more expensive spiked fuel cycle is needed as in the proposed civex pocess. If the latter is the case, it will be further necessary to determine the optimum spiking level, which could vary as much as a factor of a billion. A very basic question hangs on these determinations: What is to be the nature of the recycle fuel fabrication facilities. If the hot, fully remote fuel fabrication is required, then a great deal of further development work will be required to make the full cycle fully commercial

Determination of uranium and plutonium by sequential potentiometric titration

International Nuclear Information System (INIS)

Kato, Yoshiharu; Takahashi, Masao

1976-01-01

The determination of uranium and plutonium in mixed oxide fuels has been developed by sequential potentiometric titration. A weighed sample of uranium and plutonium oxides is dissolved in a mixture of nitric and hydrofluoric acids and the solution is fumed with sulfuric acid. After the reduction of uranium and plutonium to uranium(IV) and plutonium(III) by chromium(II) sulfate, 5 ml of buffer solution (KCl-HCl, pH 1.0) is added to the solution. Then the solution is diluted to 30 ml with water and the pH of the solution is adjusted to 1.0 -- 1.5 with 1 M sodium hydroxide. The solution is stirred until the oxidation of the excess of chromium(II) by air is completed. After the removal of dissolved oxygen by bubbling nitrogen through the solution for 10 minutes, uranium (IV) is titrated with 0.1 N cerium(IV) sulfate. Then, plutonium is titrated by 0.02 N cerium(IV) sulfate. When a mixture of uranium and plutonium is titrated with 0.1 N potassium dichromate potentiometrically, the potential change at the end point of plutonium is very small and the end point of uranium is also unclear when 0.1 N potassium permanganate is used as a titrant. In the present method, nitrate, fluoride and copper(II) interfere with the determination of plutonium and uranium. Iron interferes quantitatively with the determination of plutonium but not of uranium. Results obtained in applying the proposed method to 50 mg of mixtures of plutonium and uranium ((7.5 -- 50))% Pu were accurate to within 0.15 mg of each element. (auth.)

Remote handling in the Plutonium Immobilization Project: Plutonium conversion and first stage immobilization

International Nuclear Information System (INIS)

Brault, J.R.

2000-01-01

Since the break up of the Soviet Union at the end of the Cold War, the United States and Russia have been negotiating ways to reduce their nuclear stockpiles. Economics is one of the reasons behind this, but another important reason is safeguarding these materials from unstable organizations and countries. With the downsizing of the nuclear stockpiles, large quantities of plutonium are being declared excess and must be safely disposed of. The Savannah River Site (SRS) has been selected as the site where the immobilization facility will be located. Conceptual design and process development commenced in 1998. SRS will immobilize excess plutonium in a ceramic waste form and encapsulate it in vitrified high level waste in the Defense Waste Processing Facility (DWPF) canister. These canisters will then be interred in the national repository at Yucca Mountain, New Mexico. The facility is divided into three distinct operating areas: Plutonium Conversion, First Stage Immobilization, and Second Stage Immobilization. This paper will discuss the first two operations

Safe handling of plutonium in research laboratories

International Nuclear Information System (INIS)

1976-01-01

The training film illustrates the main basic requirements for the safe handling of small amounts of plutonium. The film is intended not only for people setting up plutonium research laboratories but also for all those who work in existing plutonium research laboratories. It was awarded the first prize in the category ''Protection of Workers'' at the international film festival organized by the 4th World Congress of the International Radiation Protection Association (IRPA) in Paris in April 1977

Safe handling of plutonium in research laboratories

Energy Technology Data Exchange (ETDEWEB)

NONE

1977-12-31

The training film illustrates the main basic requirements for the safe handling of small amounts of plutonium. The film is intended not only for people setting up plutonium research laboratories but also for all those who work in existing plutonium research laboratories. It was awarded the first prize in the category ``Protection of Workers`` at the international film festival organized by the 4th World Congress of the International Radiation Protection Association (IRPA) in Paris in April 1977

Inhaled plutonium oxide in dogs

International Nuclear Information System (INIS)

Anon.

1981-01-01

This project is concerned with long-term experiments to determine the life-span dose-effect relationships of inhaled 239 PuO 2 and 238 PuO 2 in beagles. The data will be used to estimate the health effects of inhaled transuranics. The tissue distribution of plutonium, radiation effects in the lung and hematologic changes in plutonium-exposed beagles with lung tumors were evaluated

Reduction of uranium and plutonium oxides by aluminum. Application to the recycling of plutonium; Reduction des oxydes d'uranium et de plutonium par l'aluminium application au recyclage du plutonium

Energy Technology Data Exchange (ETDEWEB)

Gallay, J [Commissariat a l' Energie Atomique, Valduc (France). Centre d' Etudes

1968-07-01

A process for treating plutonium oxide calcined at high temperatures (1000 to 2000 deg. C) with a view to recovering the metal consists in the reduction of this oxide dissolved in a mixture of aluminium, sodium and calcium fluorides by aluminium at about 1180 deg. C. The first part of the report presents the results of reduction tests carried out on the uranium oxides UO{sub 2} and U{sub 3}O{sub 8}; these are in agreement with the thermodynamic calculations of the exchange reaction at equilibrium. The second part describes the application of this method to plutonium oxides. The Pu-Al alloy obtained (60 per cent Pu) is then recycled in an aqueous medium. (author) [French] Un procede de traitement de l'oxyde de plutonium calcine a haute temperature (1000 deg. C a 2000 deg. C), en vue de la recuperation du metal, consiste a reduire cet oxyde dissous dans un melange de fluorures d'aluminium, de sodium et de calcium, par l'aluminium vers 1180 deg. C. Une premiere partie du rapport presente les resultats des essais de reduction des oxydes d'uranium UO{sub 2} et U{sub 3}O{sub 8}, en accord avec les resultats du calcul thermodynamique de la reaction d'echange a l'equilibre. Une seconde partie rend compte de l'application de cette methode a l'oxyde de plutonium. L'alliage Pu-Al obtenu (60 pour cent Pu) est ensuite recycle par voie aqueuse. (auteur)

Surplus plutonium disposition draft environmental impact statement. Volume 1, Part A

International Nuclear Information System (INIS)

1998-07-01

On May 22, 1997, DOE published a Notice of Intent (NOI) in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS). DOE's disposition strategy allows for both the immobilization of surplus plutonium and its use as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of the immobilized plutonium and MOX fuel (as spent nuclear fuel) in a geologic repository. The Surplus Plutonium Disposition Environmental Impact Statement analyzes alternatives that would use the immobilization approach (for some of the surplus plutonium) and the MOX fuel approach (for some of the surplus plutonium); alternatives that would immobilize all of the surplus plutonium; and the No Action Alternative. The alternatives include three disposition facilities that would be designed so that they could collectively accomplish disposition of up to 50 metric tons (55 tons) of surplus plutonium over their operating lives: (1) the pit disassembly and conversion facility would disassemble pits (a weapons component) and convert the recovered plutonium, as well as plutonium metal from other sources, into plutonium dioxide suitable for disposition; (2) the immobilization facility would include a collocated capability for converting nonpit plutonium materials into plutonium dioxide suitable for immobilization and would be located at either Hanford or SRS. DOE has identified SRS as the preferred site for an immobilization facility; (3) the MOX fuel fabrication facility would fabricate plutonium dioxide into MOX fuel. This volume includes background information; purpose of and need for the proposed action; alternatives for disposition of surplus weapons useable plutonium; and

Multiple recycling of plutonium in advanced PWRs

International Nuclear Information System (INIS)

Kloosterman, J.L.

1998-04-01

The influence of the moderator-to-fuel ratio in MOX fueled PWRs on the moderator void coefficient, the fuel temperature coefficient, the moderator temperature coefficient, the boron reactivity worth, the critical boron concentration, the mean neutron generation time and the effective delayed neutron fraction has been assessed. Increasing the moderator-to-fuel ratio to values larger than three, gives a moderator void coefficient sufficiently large to recycle the plutonium at least four times. Scenario studies show that four times recycling of plutonium in PWRs reduces the plutonium mass produced with a factor of three compared with a reference once-through reactor park, but that the americium and curium production triple. If the minor actinides and the remaining plutonium after four times recycling are disposed of, the reduction of the radiotoxicity reaches only a factor of two. This factor increases to five at the maximum when the plutonium is further recycled. Recycling of americium and curium is needed to further reduce the radiotoxicity of the spent fuel. 4 refs

Transuranic elements in nature - plutonium all around us

International Nuclear Information System (INIS)

Keller, C.; Baptista de Alleluia, I.

1979-01-01

At first the transuranic element plutonium was thought to be an artificial element which was formed during nuclear reactions. However, in the earth's crust traces of plutonium have also been found which has constantly been renewing itself ever since the birth of our solar system. But it is the quantities of artificially produced plutonium which make up the bulk of this element on our planet. Part of it has spread fairly equally over the whole of the earth. Plutonium can be proved to exist on every field an in every sample of air today. (orig.) [de

Safety aspects with regard to plutonium vitrification techniques

International Nuclear Information System (INIS)

Gray, L.W.; Kan, T.

1995-01-01

Substantial inventories of excess plutonium are expected to result from dismantling US and Russian nuclear weapons. Disposition of this material should be a high priority in both countries. Various disposition options are under consideration. One option is to vitrify the plutonium with the addition of 137 Cs or high-level waste to act as a deterrent to proliferation. The primary safety problem associated with vitrification of plutonium is to avoid criticality in form fabrication and in the final repository over geologic time. Recovery should be as difficult (costly) as the recovery of plutonium from spent fuel

Political influences in plutonium recycling

International Nuclear Information System (INIS)

Patak, H.N.

1982-01-01

The history of plutonium safeguards is one of political error and misunderstandings, as well as a lack of technical knowledge. Although there was widespread support for preventing the proliferation of nuclear explosives, with over 100 nations signing the Nonproliferation Treaty of 1969, India's 1974 nuclear test brought renewed political activity to prevent another such occurrence. Opposition has been directed only at how to pursue this goal, but the status of four major experiments aimed at minimizing weapons proliferation is one of failure, intensified by a weakening of the International Atomic Energy Agency (IAEA). If the link between plutonium power and weapons production can be broken through on-site reprocessing, the situation could improve. One course would be for the nuclear power industry to adopt its own system for safe guarding plutonium

Shielding calculational system for plutonium

International Nuclear Information System (INIS)

Zimmerman, M.G.; Thomsen, D.H.

1975-08-01

A computer calculational system has been developed and assembled specifically for calculating dose rates in AEC plutonium fabrication facilities. The system consists of two computer codes and all nuclear data necessary for calculation of neutron and gamma dose rates from plutonium. The codes include the multigroup version of the Battelle Monte Carlo code for solution of general neutron and gamma shielding problems and the PUSHLD code for solution of shielding problems where low energy gamma and x-rays are important. The nuclear data consists of built in neutron and gamma yields and spectra for various plutonium compounds, an automatic calculation of age effects and all cross-sections commonly used. Experimental correlations have been performed to verify portions of the calculational system. (23 tables, 7 figs, 16 refs) (U.S.)

Japan-U.S. cooperation in transport of plutonium

International Nuclear Information System (INIS)

Takeda, Yu

2012-01-01

Japan's effort to utilize plutonium for peaceful purpose since 1950s was caught in a cross fire after the end of the Cold War. Maritime transport of plutonium from France to Japan in 1993, for instance, was criticized by U.S. Congress, nonproliferation specialists and environmental activists. U.S. government, however, compiled with Japan-US Nuclear Cooperation Agreement and cooperated to ship plutonium. This paper focuses on why Washington was supportive for the sealift of plutonium despite of opposition against it. By solving the puzzle, this research will contribute to studies of Japan's plutonium policy and Japan-U.S. nuclear relations. Based on newspaper articles, memoirs and official documents, this paper examines backgrounds and features of controversy surrounding the transport. The analyses show the causes of U.S. cooperation to the transport, such as Japan's efforts toward nuclear nonproliferation. (author)

Optimal management of weapons plutonium through MOX recycling

International Nuclear Information System (INIS)

McMurphy, M.A.; Bastard, G. le

1995-01-01

Beyond the satisfaction of witnessing the end of the nuclear arms race, the availability of large quantities of plutonium from the dismantlement of nuclear weapons in Russia and the US can be perceived as a challenge and an opportunity. A challenge because poor management of this material would maintain a problematic situation in terms of proliferation; an opportunity because such plutonium represents a high value energy source that the civilian industry is capable of using efficiently, actually turning it from swords to plowshares. The object of this paper is to describe the main characteristics of the use of weapons plutonium in the civilian cycle to produce electricity through the use of mixed uranium-plutonium oxide (MOX), or moxification. A comparison with the main alternate solution--plutonium vitrification--is offered, in particular with regard to industrial availability, energy resource management, economy, environment and proliferation

Plutonium Disposition by Immobilization

International Nuclear Information System (INIS)

Gould, T.; DiSabatino, A.; Mitchell, M.

2000-01-01

The ultimate goal of the Department of Energy (DOE) Immobilization Project is to develop, construct, and operate facilities that will immobilize between 17 to 50 tonnes (MT) of U.S. surplus weapons-usable plutonium materials in waste forms that meet the ''spent fuel'' standard and are acceptable for disposal in a geologic repository. Using the ceramic can-in-canister technology selected for immobilization, surplus plutonium materials will be chemically combined into ceramic forms which will be encapsulated within large canisters of high level waste (HLW) glass. Deployment of the immobilization capability should occur by 2008 and be completed within 10 years. In support of this goal, the DOE Office of Fissile Materials Disposition (MD) is conducting development and testing (D and T) activities at four DOE laboratories under the technical leadership of Lawrence Livermore National Laboratory (LLNL). The Savannah River Site has been selected as the site for the planned Plutonium Immobilization Plant (PIP). The D and T effort, now in its third year, will establish the technical bases for the design, construction, and operation of the U. S. capability to immobilize surplus plutonium in a suitable and cost-effective manner. Based on the D and T effort and on the development of a conceptual design of the PIP, automation is expected to play a key role in the design and operation of the Immobilization Plant. Automation and remote handling are needed to achieve required dose reduction and to enhance operational efficiency

Complementary technologies for verification of excess plutonium

International Nuclear Information System (INIS)

Langner, D.G.; Nicholas, N.J.; Ensslin, N.; Fearey, B.L.; Mitchell, D.J.; Marlow, K.W.; Luke, S.J.; Gosnell, T.B.

1998-01-01

Three complementary measurement technologies have been identified as candidates for use in the verification of excess plutonium of weapons origin. These technologies: high-resolution gamma-ray spectroscopy, neutron multiplicity counting, and low-resolution gamma-ray spectroscopy, are mature, robust technologies. The high-resolution gamma-ray system, Pu-600, uses the 630--670 keV region of the emitted gamma-ray spectrum to determine the ratio of 240 Pu to 239 Pu. It is useful in verifying the presence of plutonium and the presence of weapons-grade plutonium. Neutron multiplicity counting is well suited for verifying that the plutonium is of a safeguardable quantity and is weapons-quality material, as opposed to residue or waste. In addition, multiplicity counting can independently verify the presence of plutonium by virtue of a measured neutron self-multiplication and can detect the presence of non-plutonium neutron sources. The low-resolution gamma-ray spectroscopic technique is a template method that can provide continuity of knowledge that an item that enters the a verification regime remains under the regime. In the initial verification of an item, multiple regions of the measured low-resolution spectrum form a unique, gamma-radiation-based template for the item that can be used for comparison in subsequent verifications. In this paper the authors discuss these technologies as they relate to the different attributes that could be used in a verification regime

Chemical species of plutonium in Hanford radioactive tank waste

International Nuclear Information System (INIS)

Barney, G.S.

1997-01-01

Large quantities of radioactive wastes have been generated at the Hanford Site over its operating life. The wastes with the highest activities are stored underground in 177 large (mostly one million gallon volume) concrete tanks with steel liners. The wastes contain processing chemicals, cladding chemicals, fission products, and actinides that were neutralized to a basic pH before addition to the tanks to prevent corrosion of the steel liners. Because the mission of the Hanford Site was to provide plutonium for defense purposes, the amount of plutonium lost to the wastes was relatively small. The best estimate of the amount of plutonium lost to all the waste tanks is about 500 kg. Given uncertainties in the measurements, some estimates are as high as 1,000 kg (Roetman et al. 1994). The wastes generally consist of (1) a sludge layer generated by precipitation of dissolved metals from aqueous wastes solutions during neutralization with sodium hydroxide, (2) a salt cake layer formed by crystallization of salts after evaporation of the supernate solution, and (3) an aqueous supernate solution that exists as a separate layer or as liquid contained in cavities between sludge or salt cake particles. The identity of chemical species of plutonium in these wastes will allow a better understanding of the behavior of the plutonium during storage in tanks, retrieval of the wastes, and processing of the wastes. Plutonium chemistry in the wastes is important to criticality and environmental concerns, and in processing the wastes for final disposal. Plutonium has been found to exist mainly in the sludge layers of the tanks along with other precipitated metal hydrous oxides. This is expected due to its low solubility in basic aqueous solutions. Tank supernate solutions do not contain high concentrations of plutonium even though some tanks contain high concentrations of complexing agents. The solutions also contain significant concentrations of hydroxide which competes with other

Neutronic design of a plutonium-thorium burner small nuclear reactor

International Nuclear Information System (INIS)

Hartanto, Donny

2010-02-01

A small nuclear reactor using thorium and plutonium fuel has been designed from the neutronic point of view. The thermal power of the reactor is 150 MWth and it is proposed to be used to supply electricity in an island in Indonesia. Thorium and plutonium fuel was chosen because in recent years the thorium fuel cycle is one of the promising ways to deal with the increasing number of plutonium stockpiles, either from the utilization of uranium fuel cycle or from nuclear weapon dismantling. A mixed fuel of thorium and plutonium will not generate the second generation of plutonium which will be a better way to incinerate the excess plutonium compared with the MOX fuel. Three kinds of plutonium grades which are the reactor grade (RG), weapon grade (WG), and spent fuel grade (SFG) plutonium, were evaluated as the thorium fuel mixture in the 17x17 Westinghouse PWR Fuel assembly. The evaluated parameters were the multiplication factor, plutonium depletion, fissile buildup, neutron spectrum, and temperature reactivity feedback. An optimization was also done to increase the plutonium depletion by changing the Moderator to Fuel Ratio (MFR). The computer codes TRITON (coupled NEWT and ORIGEN-S) in SCALE version 6 were used as the calculation tool for this assembly level. From the evaluation and optimization of the fuel assembly, the whole core was designed. The core was consisted of 2 types of thorium fuel with different plutonium grade and it followed the checkerboard loading pattern. A new concept of enriched burnable poison was also introduced to the core. The core life is 6.4 EFPY or 75 GWd/MTHM. It can burn up to 58% of its total mass of initial plutonium. VENTURE was used as the calculation tool for the core level

Potentiometric titration of plutonium

International Nuclear Information System (INIS)

Silver, G.L.

1978-01-01

In the potentiometric titration of plutonium(III), it has been customary to take the equivalence point as the inflection point on a plot of potential vs. volume of titrant. It have not been, however, demonstrated, that the stoichiometric end point corresponds to the inflection point. Suggestions are made according to which these points may not correspond in the potentiometric titration of plutonium(III), as these titrations are ordinarily concluded in a period of time which is short compared to the time required for valence state rearrangement through disproportionation. (T.G.)

Accountability methods for plutonium and uranium: the NRC manuals

Energy Technology Data Exchange (ETDEWEB)

Gutmacher, R.G.; Stephens, F.B.

1977-09-28

Four manuals containing methods for the accountability of plutonium nitrate solutions, plutonium dioxide, uranium dioxide and mixed uranium-plutonium oxide have been prepared by us and issued by the U.S. Nuclear Regulatory Commission. A similar manual on methods for the accountability of uranium and plutonium in reprocessing plant dissolver solutions is now in preparation. In the present paper, we discuss the contents of the previously issued manuals and give a preview of the manual now being prepared.

Accountability methods for plutonium and uranium: the NRC manuals

International Nuclear Information System (INIS)

Gutmacher, R.G.; Stephens, F.B.

1977-01-01

Four manuals containing methods for the accountability of plutonium nitrate solutions, plutonium dioxide, uranium dioxide and mixed uranium-plutonium oxide have been prepared by us and issued by the U.S. Nuclear Regulatory Commission. A similar manual on methods for the accountability of uranium and plutonium in reprocessing plant dissolver solutions is now in preparation. In the present paper, we discuss the contents of the previously issued manuals and give a preview of the manual now being prepared

Concentration of plutonium in desert plants from contaminated area

International Nuclear Information System (INIS)

Xu Hui; Jin Yuren; Tian Mei; Li Weiping; Zeng Ke; Wang Yaoqin; Wang Yu

2012-01-01

The investigation of plutonium in desert plants from contaminated sites contributes to the evaluation of its pollution situation and to the survey of plutonium hyper accumulator. The concentration of 239 Pu in desert plants collected from a contaminated site was determined, and the influence factors were studied. The concentration of 239 Pu in plants was (1.8±4.9) Bq/kg in dry weight, and it means that the plants were contaminated, moreover, the resuspension results in dramatic plutonium pollution of plant surface. The concentration of plutonium in plants depends on species, live stages and the content of plutonium in the rhizosphere soil. The concentration of plutonium in herbage is higher than that in woody plant, and for the seven species of desert plants investigated, it decreases in the order of Hexinia polydichotoma, Phragmites australis, Halostashys caspica, Halogeton arachnoideus, Lycium ruthenicum, Tamarix hispida and Calligonum aphyllum. (authors)

Study of plutonium cycle in marine ecosystems

International Nuclear Information System (INIS)

Merino Pareja, J.; Sanchez Cabeza, J. A.; Molero Savall, J.; Masque Barri, P.

1998-01-01

The distribution, transport and accumulation mechanisms of transuranics (and other radionuclides) in the marine environment depend on the source term, biogeochemical cycles, transport with the water masses, sedimentation processes and transfer mechanisms in the trophic chain. The biogeochemical behaviour of plutonium, which has been the focus of our work, was studied using the following approaches: determination of the physico-chemical speciation of plutonium in marine waters, vertical flux in the water column, uptake by marine organisms (phytoplankton and zooplankton) and distribution in dements cores. A preliminary model of the accumulation and distribution of plutonium in the first levels of the marine food chain in the Irish Sea has also been formulated. All this information allowed us to obtain an integrated view of the behaviour of plutonium in the marine environment. (Author) 14 refs

Plutonium: real and false problems

International Nuclear Information System (INIS)

Bemden, E. van den

1981-01-01

This paper deals with technical and technological state of the possibilities of using plutonium as fuel in the thermal and fast reactors. It also describes the political blockage restraining its use and the reasons for it. The accent is put on some fundamental lacks of international coordination and on some problems of commercial policy, which impede, in a certain way, the industrial use of plutonium as a fuel. (author)

Plutonium (Pu)

International Nuclear Information System (INIS)

2002-01-01

This pedagogical document presents the properties and uses of plutonium: where does it come from, the history of its discovery, its uses and energy content, its recycling and reuse in MOX fuels, its half-life, toxicity and presence in the environment. (J.S.)

Nutzerorientiertes Management von materiellen und immateriellen Informationsobjekten

OpenAIRE

Hübsch, Chris

2001-01-01

Schaffung einer stabilen, erweiterbaren und skalierbaren Infrastruktur für die Bereitstellung von Diensten im Umfeld von Bibliotheken und ähnlichen wissensanbietenden Einrichtungen unter Verwendung von XML-RPC und Python.

International and institutional aspects of reprocessing and plutonium management

International Nuclear Information System (INIS)

1978-09-01

Various institutional alternatives applicable to reprocessing, plutonium management and recycle are considered, not as a definitive analysis but rather as a basis for identifying the institutional approaches and measures which the Working Group might wish to examine more thoroughly. Seven alternatives arrangements for reprocessing are presented. These range from suspending the operation of existing reprocessing plants through placing national facilities under safeguards to limiting reprocessing to a few large facilities subject to plutonium management, multinational or international control. Finally, the comprehensive alternative of an International Nuclear Fuel Authority with worldwide responsibility for reprocessing and plutonium management is considered. Plutonium management alternatives to complement the reprocessing options, are then outlined. These include national discretion on the separation and disposition of plutonium under safeguards, an agreed Code of Practice for plutonium management at national facilities and the international storage of plutonium. The advantages and disadvantages of the alternative are discussed tentatively. It is recognised that the alternatives are presented in a simplified form and that their elements can be combined or separated in many ways. Although strengthening the institutions relating to the peaceful uses of nuclear energy is imperative and can contribute to non-proliferation, such arrangements might open other proliferation risks through the spread of sensitive materials, facilities and technology. While there are risks with any fuel cycle, where plutonium in quantity is separated these risks are of a high order. Although these can be mitigated, they will have to be set against the energy and economic case for reprocessing and alternatives other than plutonium considered

Materials identification and surveillance project item evaluation: Items, impure plutonium oxide (ATL27960) and pure plutonium oxide (PEOR3258)

International Nuclear Information System (INIS)

Allen, T.; Appert, Q.; Davis, C.

1997-03-01

In this report, Los Alamos scientists characterize properties relevant to storage of an impure plutonium oxide (74 mass % plutonium) in accordance with the Department of Energy (DOE) standard DOE-STD-3013-96. This oxide is of interest because it is the first impure plutonium oxide sample to be evaluated and it is similar to other materials that must be stored. Methods used to characterize the oxide at certain points during calcination include surface-area analyses, mass loss-on-ignition (LOI) measurements, elemental analysis, moisture-adsorption measurements, and quantitative supercritical-CO 2 extraction of adsorbed water. Significant decreases in the LOI and surface area occurred as the oxide was calcined at progressively increasing temperatures. Studies indicate that supercritical-CO 2 extraction is an effective method for removing adsorbed water from oxides. We extracted the water from powdered oxides (high-purity ZrO 2 , pure PuO 2 , and impure plutonium oxide) using CO 2 at 3000 psi pressure and 75 degrees C, and we quantitatively determined it by using gravimetric and dew-point procedures. The effectiveness of the extraction method is demonstrated by good agreement between the amounts of water extracted from pure zirconium and plutonium dioxides and the mass changes obtained from LOI analyses. However, the amount of moisture (0.025 mass %) extracted from the impure plutonium oxide after it had been calcined at 950 degrees C and stored for a period of months is much less than the LOI value (0.97 mass %). These results imply that the impure plutonium oxide is free of adsorbed water after calcination at 950 degrees C, even though the sample does not satisfy the LOI requirement of <0.50 mass % for storage

Surplus plutonium disposition draft environmental impact statement. Volume 1, Part B

International Nuclear Information System (INIS)

1998-07-01

On May 22, 1997, DOE published a Notice of Intent (NOI) in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS). DOE's disposition strategy allows for both the immobilization of surplus plutonium and its use as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of the immobilized plutonium and MOX fuel (as spent nuclear fuel) in a geologic repository. The Surplus Plutonium Disposition Environmental Impact Statement analyzes alternatives that would use the immobilization approach (for some of the surplus plutonium) and the MOX fuel approach (for some of the surplus plutonium); alternatives that would immobilize all of the surplus plutonium; and the No Action Alternative. The alternatives include three disposition facilities that would be designed so that they could collectively accomplish disposition of up to 50 metric tons (55 tons) of surplus plutonium over their operating lives: (1) the pit disassembly and conversion facility would disassemble pits (a weapons component) and convert the recovered plutonium, as well as plutonium metal from other sources, into plutonium dioxide suitable for disposition; (2) the immobilization facility would include a collocated capability for converting nonpit plutonium materials into plutonium dioxide suitable for immobilization and would be located at either Hanford or SRS. DOE has identified SRS as the preferred site for an immobilization facility; (3) the MOX fuel fabrication facility would fabricate plutonium dioxide into MOX fuel. This volume has chapters on environmental consequences; environmental regulations, permits, and consultations; a glossary; list of preparers; distribution list

A rapid method of dosing plutonium in radioactive effluents; Methode de dosage rapide du plutonium dans les effluents radioactifs (1961)

Energy Technology Data Exchange (ETDEWEB)

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

1961-07-01

The plutonium is first separated by a lanthanum fluoride precipitation. The precipitated fluorides are dissolved in normal nitric acid solution in the presence of aluminium nitrate. The plutonium transformed to the tetravalent state is then extracted with thenoyltrifluoroacetone and returned to the aqueous phase with 10 N nitric acid. After evaporation on a watch glass the residue is calcined on a Meker burner and counted using a counting system fitted with a zinc sulphide scintillator. When necessary, the calcium is eliminated at the beginning of the dosage by a fluoride precipitation, the plutonium being oxidised to the valency IV. (authors) [French] Le plutonium est d'abord separe par entrainement au fluorure de lanthane. Le precipite des fluorures est remis en solution en milieu acide nitrique normal, en presence de nitrate d'aluminium. Le plutonium amene a la valence IV est alors extrait par la thenoyltrifluoroacetone et remis en phase aqueuse dans l'acide nitrique 10 N. Apres evaporation sur verre de montre, le residu est calcine sur bec Meker et compte sur un ensemble de comptage equipe d'un scintillateur au sulfure de zinc. Lorsque cela est necessaire, le calcium est elimine, au debut du dosage, par precipitation du fluorure, le plutonium etant oxyde a la valence VI. (auteurs)

Diffusion and Kirkendall effect in plutonium-zirconium system; Diffusion et effet Kirkendall dans le systeme plutonium-zirconium

Energy Technology Data Exchange (ETDEWEB)

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

1968-10-01

Results are reported for the chemical diffusion in {epsilon}{beta} phase (bcc) over the range 10 - 70 atomic per cent plutonium. Concentration-penetration curves, obtained by using electron microprobe, have been analysed by Hall and Matano methods. Chemical diffusion coefficients, measured from 650 to 900 deg. C., increase with plutonium concentration and follow the Arrhenius law. Activation energies range from 18000 up to 44000 cal/mole for plutonium concentrations from 60 to 20 atomic per cent plutonium. Kirkendall effect has been observed by the shift of inert markers located originally at the Zr-PuZr interface. Analysis of intrinsic diffusion coefficients variation, flux of the two species and lattice velocity has been carried out by the incremental couples technique by using Darken and Heumann equations. It was found that D{sub Pu} > D{sub Zr}; the ratio D{sub Pu}/D{sub Zr} increases from 1 to 6 over the range 15 - 60 atomic per cent Pu. Activation energies for intrinsic diffusion coefficients vary between 25 and 50 Kcal/mole. (author) [French] Nous donnons des resultats sur la diffusion chimique en phase {epsilon}{beta} (cc) de 10 a 70 pour cent atomique en plutonium. Les courbes concentration-penetration, obtenues par microanalyse X ont ete depouillees par les methodes de HALL et de MATANO. Les coefficients de diffusion chimique mesures de 650 deg. C a 900 deg. C., augmentent avec la concentration en plutonium et suivent la loi d'ARRHENIUS. Les energies d'activation passent de 18000 a 44000 calories par mole pour des concentrations de 60 a 20 pour cent atomique en plutonium. L'existence d'un effet KIRKENDALL a ete mis en evidence par le deplacement de fils inertes places initialement dans le plan de soudure. L'analyse de la variation des coefficients de diffusion intrinseques, des flux des deux especes et de la vitesse du reseau a ete faite par la technique des couples incrementaux en utilisant les equations de DARKEN et de HEUMANN. On trouve D{sub Pu} > D

Plutonium recovery from spent reactor fuel by uranium displacement

Science.gov (United States)

Ackerman, J.P.

1992-03-17

A process is described for separating uranium values and transuranic values from fission products containing rare earth values when the values are contained together in a molten chloride salt electrolyte. A molten chloride salt electrolyte with a first ratio of plutonium chloride to uranium chloride is contacted with both a solid cathode and an anode having values of uranium and fission products including plutonium. A voltage is applied across the anode and cathode electrolytically to transfer uranium and plutonium from the anode to the electrolyte while uranium values in the electrolyte electrolytically deposit as uranium metal on the solid cathode in an amount equal to the uranium and plutonium transferred from the anode causing the electrolyte to have a second ratio of plutonium chloride to uranium chloride. Then the solid cathode with the uranium metal deposited thereon is removed and molten cadmium having uranium dissolved therein is brought into contact with the electrolyte resulting in chemical transfer of plutonium values from the electrolyte to the molten cadmium and transfer of uranium values from the molten cadmium to the electrolyte until the first ratio of plutonium chloride to uranium chloride is reestablished.

The mysterious world of plutonium metallurgy: Past and future

International Nuclear Information System (INIS)

Hecker, S.S.; Hammel, E.F.

1998-01-01

The first atomic bomb detonated at the Trinity Site in New Mexico on July 16, 1945, used plutonium, a man-made element discovered < 5 yr earlier. The story of how Manhattan Project scientists and engineers tackled the mysteries of this element and fabricated it into the first atomic bomb is one of the most fascinating in the history of metallurgy and materials. The authors are currently trying to generate renewed interest in plutonium metallurgy because of the challenge posed by President Clinton, i.e., to keep the nuclear stockpile of weapons safe and reliable without nuclear testing. The stockpile stewardship challenge requires either a lifetime extension of the plutonium components or a remanufacture--neither of which can be verified by testing. In turn, this requires that one achieve a better fundamental understanding of plutonium. Of special interest is the effect of self-irradiation on the properties and on the long-term stability of plutonium and its alloys. Additional challenges arise from long-term concerns about disposing of plutonium and dealing with its environmental legacy. It is imperative to interest the next generation of students in these plutonium challenges

Plutonium recovery from spent reactor fuel by uranium displacement

International Nuclear Information System (INIS)

Ackerman, J.P.

1992-01-01

A process is described for separating uranium values and transuranic values from fission products containing rare earth values when the values are contained together in a molten chloride salt electrolyte. A molten chloride salt electrolyte with a first ratio of plutonium chloride to uranium chloride is contacted with both a solid cathode and an anode having values of uranium and fission products including plutonium. A voltage is applied across the anode and cathode electrolytically to transfer uranium and plutonium from the anode to the electrolyte while uranium values in the electrolyte electrolytically deposit as uranium metal on the solid cathode in an amount equal to the uranium and plutonium transferred from the anode causing the electrolyte to have a second ratio of plutonium chloride to uranium chloride. Then the solid cathode with the uranium metal deposited thereon is removed and molten cadmium having uranium dissolved therein is brought into contact with the electrolyte resulting in chemical transfer of plutonium values from the electrolyte to the molten cadmium and transfer of uranium values from the molten cadmium to the electrolyte until the first ratio of plutonium chloride to uranium chloride is reestablished

General consideration of effective plutonium utilization in future LWRs

International Nuclear Information System (INIS)

Ishikawa, Nobuyuki; Okubo, Tsutomu

2009-01-01

In this study, the potential of mixed oxide fueled light water reactors (MOX-LWRs), especially focusing on the high conversion type LWRs (HC-LWRs) such as FLWR are evaluated in terms of both economic aspect and effective use of plutonium. For economics consideration, relative economics positions of MOX-LWRs are clarified comparing the cost of electricity for uranium fueled LWRs (U-LWRs), MOX-LWRs and fast breeder reactors (FBRs) assuming future natural uranium price raise and variation of parameters such as construction cost and capacity factor. Also the economic superiority of MOX utilization against the uranium use is mentioned from the view point of plutonium credit concerning to the front-end fuel cycle cost. In terms of effective use of plutonium, comparative evaluations on plutonium mass balance in the cases of HC-LWR and high moderation type LWRs (HM-LWRs) taking into account plutonium quality (ratio of fissile to total plutonium) constraint in multiple recycling are performed as representative MOX utilization cases. Through this evaluation, the advantageous features of plutonium multiple recycling by HC-LWR are clarified. From all these results, merits of the introduction of HC-LWRs are discussed. (author)

Corrosion performance of several metals in plutonium nitrate solution

International Nuclear Information System (INIS)

Takeda, Seiichiro; Nagai, Takayuki; Yasu, Shozo; Koizumi, Tsutomu

1995-01-01

Corrosion behavior of several metals exposed in plutonium nitrate solution was studied. Plutonium nitrate solution with the plutonium concentration ranging from 0.01 to 300 g/l was used as a corrosive medium. Specimens tested were type 304 ULC (304 ULC) stainless steel, type 310 Nb (310 Nb) stainless steel, titanium (Ti), titanium-5% tantalum alloy (Ti-5Ta), and zirconium (Zr). Corrosion behavior of these metals in plutonium nitrate solution was evaluated through examining electrochemical characteristics and corrosion rates obtained by weight loss measurement. From the results of the corrosion tests, it was found that the corrosion rate of stainless steels i.e. 304 ULC and 310 Nb, increases by the presence of plutonium in nitric acid solution. The corrosion potential of the stainless steels shifted linearly towards the noble direction as the concentration of plutonium increases. It is thought that the shifts in corrosion potential of the stainless steels to the noble direction results an increase in anodic current and, hence, corrosion rate. Valve metals, i.e. Ti, Ti-5Ta and Zr, showed good corrosion resistance over the whole range of plutonium concentration examined here. (author)

Plutonium in the aquatic environment around the Rocky Flats facility

International Nuclear Information System (INIS)

Thompson, M.A.

1975-01-01

The Rocky Flats Plant of the United States Energy Research and Development Administration has been fabricating and chemically recovering plutonium for over 20 years. During that time, small amounts of plutonium have been released with liquid process and sanitary waste discharges. The liquid waste flows through a series of holding ponds from which it is discharged into a creek that is part of a municipal drinking water supply. The water flows for about 1.5 km between the last holding pond and the municipal drinking water reservoir. In addition, liquid wastes containing high levels of chemical contaminants and plutonium concentrations less than allowable drinking water standards have been discharged to large evaporation ponds. The fate of the plutonium in both the surface and subsurface aquatic environment has been extensively monitored and studied. It has been found that plutonium does not move very far or very rapidly through subsurface water. The majority of the plutonium released through surface water has been contained in the sediments of the plant holding ponds. Small amounts of plutonium have also been found in the sediments of the draining creek and in the sediments of the receiving reservoir. Higher than normal amounts of plutonium were released from the waste treatment plants during times when suspended solids were high. Various biological species have been examined and plutonium concentration factors determined. Considerably less than 1% of the 210 mCi of plutonium released has been detected in biological systems including man. After more than 20 years of large scale operations, no health or environmental hazard has been identified due to the release of small amounts of plutonium. (author)

Die Verteilung und Eigenschaften von Bodenformen in der Deutschen Bucht, eine Rekonstruktion der Karten von Ulrich (1973)

DEFF Research Database (Denmark)

Winter, Christian; Lefebvre, Alice; Benninghoff, Markus

2015-01-01

Entstehung, Gestalt und Dynamik von Bodenformen in vergleichsweise kleinen Untersuchungsgebieten ist die Arbeit von ULRICH (1973) über die Verteilung von Bodenformen in der Deutschen Bucht bis heute die einzige verfügbare zusammenhängende Darstellung für die deutsche Nordseeküste. Die analogen Karten und die...

Plutonium waste incineration using pyrohydrolysis

International Nuclear Information System (INIS)

Meyer, M.L.

1991-01-01

Waste generated by Savannah River Site (SRS) plutonium operations includes a contaminated organic waste stream. A conventional method for disposing of the organic waste stream and recovering the nuclear material is by incineration. When the organic material is burned, the plutonium remains in the incinerator ash. Plutonium recovery from incinerator ash is highly dependent on the maximum temperature to which the oxide is exposed. Recovery via acid leaching is reduced for a high fired ash (>800 degree C), while plutonium oxides fired at lower decomposition temperatures (400--800 degrees C) are more soluble at any given acid concentration. To determine the feasibility of using a lower temperature process, tests were conducted using an electrically heated, controlled-air incinerator. Nine nonradioactive, solid, waste materials were batch-fed and processed in a top-heated cylindrical furnace. Waste material processing was completed using a 19-liter batch over a nominal 8-hour cycle. A processing cycle consisted of 1 hour for heating, 4 hours for reacting, and 3 hours for chamber cooling. The water gas shift reaction was used to hydrolyze waste materials in an atmosphere of 336% steam and 4.4% oxygen. Throughput ranged from 0.14 to 0.27 kg/hr depending on the variability in the waste material composition and density

˝FLUMINENSIA˝ VON FRAN KURELAC

Directory of Open Access Journals (Sweden)

Leopoldina Veronika Banaš

1990-01-01

Full Text Available Das Buch "Fluminensia" (1862 von Fran Kurelac enthält die für die Schulfestlichkeiten geschriebenen Reden, Gelegenheitsgedichte - Ehrengedichte den bedeutenden und verdienstvollen Zeitgenossen gewidmet: dem Bischof von Senj und Modrus" Mirko Ožegović, Bartol Zmajic von Bakar, dem kroatischen Ban Josip Jelačić u.a. Danach folgen Aufrufe ("Proglasi" aus stürmischem 1848, gerichtet auf die Granzlandbewohner, Deutscher, ungarische Kroaten, Rumänen und Slawonier. Die Aufrufe wurden von Kurelac im Namen der Banalregierung beschrieben. Am Ende des Buches steht eine sprachwissenschaftliche Abhandlung über die ubstantivbiegung. Die für die Schulfestlichkeiten geschreibenen Reden sind wissenschaftliche Inhalte, essaystisch-didaktisch gestalltet, mit der Meldung über die Bedeutung der Wisenschaft, über die Bedeutung und Rolle der Sprache und des Buches für den Fortschritt des Volkes. Der Verfasser widmete dieses Buch seinen ehemaligen Schülern. "Fluminensia" nimmt eine wichtige Stelle in literarischer und sprachwissenschaftlicher Schöpfung auf dem Gebiet von Rijeka und Kroatien im 19. Jahrhundert ein.

Nukem's plutonium hitches a ride

International Nuclear Information System (INIS)

Anon.

1988-01-01

The European repercussions of a scandal involving the illegal movement of plutonium and cobalt 60 in canisters in which it was claimed there was only low-level radioactive waste, from West Germany to the reprocessing centre at Mol, Belgium are considered. Large bribes were paid to employees of the nuclear industry and government inspectors to allow this illicit transport to carry on over a number of years. It is not yet clear where the plutonium came from or where it was going. The suggestion that it may have been sold to Libya or Pakistan for nuclear weapons is very damaging to the nuclear safety argument. Even if the plutonium was being disposed of because it could not be accounted for, the safeguard procedures do not give confidence to the European public more aware of nuclear safety than ever. (UK)

Recent improvements in plutonium gamma-ray analysis using MGA

International Nuclear Information System (INIS)

Ruhter, W.D.; Gunnink, R.

1992-06-01

MGA is a gamma-ray spectrum analysis program for determining relative plutonium isotopic abundances. It can determine plutonium isotopic abundances better than 1% using a high-resolution, low-energy, planar germanium detector and measurement times ten minutes or less. We have modified MGA to allow determination of absolute plutonium isotopic abundances in solutions. With calibration of a detector using a known solution concentration in a well-defined sample geometry, plutonium solution concentrations can be determined. MGA can include analysis of a second spectrum of the high-energy spectrum to include determination of fission product abundances relative to total plutonium. For the high-energy gamma-ray measurements we have devised a new hardware configuration, so that both the low- and high-energy gamma-ray detectors are mounted in a single cryostat thereby reducing weight and volume of the detector systems. We describe the detector configuration, and the performance of the MGA program for determining plutonium concentrations in solutions and fission product abundances

How much plutonium does North Korea really have?