Caracterização e manejo de resíduos gerados nos laboratórios do Instituto de Biologia da Universidade do Estado do Rio de Janeiro, IBRAG, UERJ.

O crescimento da população mundial, aumento da industrialização e consumo de bens e serviços, tem aumentado significativamente a geração de resíduos que vem causando impactos negativos na saúde humana e ambiental. Neste contexto, se destaca a geração de produtos perigosos, tais como, os resíduos de serviços de saúde- RSS. Por apresentarem riscos à saúde da população e do meio ambiente, recomendações, normas e legislações surgiram para orientar a melhor maneira o manejo e disposição final destes resíduos. No Brasil, as resoluções NBR 306/04 e CONAMA 358/05 dão diretrizes para a elaboração de um Plano de Gerenciamento de Resíduos de Serviços de Saúde-PGRSS. Os laboratórios de pesquisa e ensino, como geradores de RSS, precisam se adequar à legislação, porém existem poucos estudos e a legislação não aborda especificamente os resíduos destes laboratórios. Os laboratórios e unidades da UERJ, geradores de RSS, não possuem PGRSS. Na UERJ, somente dois estudos levantaram os resíduos gerados em laboratórios, entretanto os dados levantados para o Instituto de Biologia são incompletos. Este estudo buscou avaliar o manejo dos resíduos biológico, químico, radioativo e perfurocortante nos laboratórios do Instituto de Biologia. Os dados foram coletados pelas informações dadas pelos professores, funcionários ou alunos dos laboratórios e por observação direta. Os dados de manejo foram analisados de acordo com a RDC 306/04 Anvisa, da Resolução CONAMA 358/05 e das fichas de segurança dos produtos químicos. Foram estudados 83% dos laboratórios do Instituto de Biologia. Destes, 43% geram resíduos químicos. Dos laboratórios caracterizados, 19 laboratórios geram somente resíduo químico. No pavilhão Américo Piquet estão localizados 63% dos laboratórios geradores de resíduos biológicos, químicos, perfurocortantes ou radioativos. Do total de resíduos gerados nos laboratórios, cerca de 80% foi de resíduo biológico, 15% de resíduo químico e 5% de resíduo perfurocortante. O manejo dos resíduos nos laboratórios é realizado de maneira confusa, geralmente os erros estão na segregação, identificação e acondicionamento. De maneira geral, as informações sobre o manejo utilizado para os resíduos são incompletas, desconhecidas ou imprecisas. As ações incorretas do manejo de resíduos são características para cada tipo de resíduo; no resíduo biológico, freqüentemente, encontraram-se resíduos comuns. O resíduo químico é geralmente descartado sem tratamento prévio na rede de esgoto. O resíduo radioativo não possui identificação e acompanhamento do decaimento, para posterior descarte. No resíduo perfurocortante encontrou-se, freqüentemente, resíduo biológico e químico misturados. Para o sucesso de um futuro Plano de Gerenciamento de Resíduos, a capacitação dos profissionais é muito importante. A Instituição deve investir na consolidação desse trabalho, considerando que ela não pode se furtar de adotar uma postura pró-ativa com relação aos problemas ambientais, sejam eles dirigentes da instituição, ou profissionais que ali atuam. Espera-se que essa pesquisa possa auxiliar neste sentido.

主从式核废料处理机器人研究

为解决在核废料清理的问题,结合了机器人和吊车的特点,提出了一种新型的主从式处理机器人,并介绍了机构和控制方法。

地下水流动数值模拟的并行计算方法研究

Numerical modeling of groundwater is very important for understanding groundwater flow and solving hydrogeological problem. Today, groundwater studies require massive model cells and high calculation accuracy, which are beyond single-CPU computer’s capabilities. With the development of high performance parallel computing technologies, application of parallel computing method on numerical modeling of groundwater flow becomes necessary and important. Using parallel computing can improve the ability to resolve various hydro-geological and environmental problems. In this study, parallel computing method on two main types of modern parallel computer architecture, shared memory parallel systems and distributed shared memory parallel systems, are discussed. OpenMP and MPI (PETSc) are both used to parallelize the most widely used groundwater simulator, MODFLOW. Two parallel solvers, P-PCG and P-MODFLOW, were developed for MODFLOW. The parallelized MODFLOW was used to simulate regional groundwater flow in Beishan, Gansu Province, which is a potential high-level radioactive waste geological disposal area in China. 1. The OpenMP programming paradigm was used to parallelize the PCG (preconditioned conjugate-gradient method) solver, which is one of the main solver for MODFLOW. The parallel PCG solver, P-PCG, is verified using an 8-processor computer. Both the impact of compilers and different model domain sizes were considered in the numerical experiments. The largest test model has 1000 columns, 1000 rows and 1000 layers. Based on the timing results, execution times using the P-PCG solver are typically about 1.40 to 5.31 times faster than those using the serial one. In addition, the simulation results are the exact same as the original PCG solver, because the majority of serial codes were not changed. It is worth noting that this parallelizing approach reduces cost in terms of software maintenance because only a single source PCG solver code needs to be maintained in the MODFLOW source tree. 2. P-MODFLOW, a domain decomposition–based model implemented in a parallel computing environment is developed, which allows efficient simulation of a regional-scale groundwater flow. The basic approach partitions a large model domain into any number of sub-domains. Parallel processors are used to solve the model equations within each sub-domain. The use of domain decomposition method to achieve the MODFLOW program distributed shared memory parallel computing system will process the application of MODFLOW be extended to the fleet of the most popular systems, so that a large-scale simulation could take full advantage of hundreds or even thousands parallel processors. P-MODFLOW has a good parallel performance, with the maximum speedup of 18.32 (14 processors). Super linear speedups have been achieved in the parallel tests, indicating the efficiency and scalability of the code. Parallel program design, load balancing and full use of the PETSc were considered to achieve a highly efficient parallel program. 3. The characterization of regional ground water flow system is very important for high-level radioactive waste geological disposal. The Beishan area, located in northwestern Gansu Province, China, is selected as a potential site for disposal repository. The area includes about 80000 km2 and has complicated hydrogeological conditions, which greatly increase the computational effort of regional ground water flow models. In order to reduce computing time, parallel computing scheme was applied to regional ground water flow modeling. Models with over 10 million cells were used to simulate how the faults and different recharge conditions impact regional ground water flow pattern. The results of this study provide regional ground water flow information for the site characterization of the potential high-level radioactive waste disposal.

Impacts of shale gas wastewater disposal on water quality in western Pennsylvania.

The safe disposal of liquid wastes associated with oil and gas production in the United States is a major challenge given their large volumes and typically high levels of contaminants. In Pennsylvania, oil and gas wastewater is sometimes treated at brine treatment facilities and discharged to local streams. This study examined the water quality and isotopic compositions of discharged effluents, surface waters, and stream sediments associated with a treatment facility site in western Pennsylvania. The elevated levels of chloride and bromide, combined with the strontium, radium, oxygen, and hydrogen isotopic compositions of the effluents reflect the composition of Marcellus Shale produced waters. The discharge of the effluent from the treatment facility increased downstream concentrations of chloride and bromide above background levels. Barium and radium were substantially (>90%) reduced in the treated effluents compared to concentrations in Marcellus Shale produced waters. Nonetheless, (226)Ra levels in stream sediments (544-8759 Bq/kg) at the point of discharge were ~200 times greater than upstream and background sediments (22-44 Bq/kg) and above radioactive waste disposal threshold regulations, posing potential environmental risks of radium bioaccumulation in localized areas of shale gas wastewater disposal.

The effect of aqueous diffusion on the fractionation of chlorine and bromine stable isotopes

Diffusive isotopic fractionation factors are important in order to understand natural processes and have practical application in radioactive waste storage and carbon dioxide sequestration. We determined the isotope fractionation factors and the effective diffusion coefficients of chloride and bromide ions during aqueous diffusion in polyacrylamide gel. Diffusion was determined as functions of temperature, time and concentration. The effect of temperature is relatively large on the diffusion coefficient (D) but only small on isotope fractionation. For chlorine, the ratio, D-35cl/D-37cl varied from 1.00128 +/- 0.00017 (1 sigma) at 2 degrees C to 1.00192 +/- 0.00015 at 80 degrees C. For bromine, D-79Br/D-81Br varied from 1.00098 +/- 0.00009 at 2 degrees C to 1.0064 +/- 0.00013 at 21 degrees C and 1.00078 +/- 0.00018 (1 sigma) at 80 degrees C. There were no significant effects on the isotope fractionation due to concentration. The lack of sensitivity of the diffusive isotope fractionation to anything at the most common temperatures (0 to 30 C) makes it particularly valuable for application to understanding processes in geological environments and an important natural tracer in order to understand fluid transport processes. (C) 2009 Elsevier Ltd. All rights reserved.

Aditivação de pastas geopoliméricas com tetraborato de sódio e látex não iônico para cimentação de Poços de Petróleo

The development of activities in the oil and gas sector has been promoting the search for materials more adequate to oilwell cementing operation. In the state of Rio Grande do Norte, the cement sheath integrity tend to fail during steam injection operation which is necessary to increase oil recovery in reservoir with heavy oil. Geopolymer is a material that can be used as alternative cement. It has been used in manufacturing of fireproof compounds, construction of structures and for controlling of toxic or radioactive waste. Latex is widely used in Portland cement slurries and its characteristic is the increase of compressive strength of cement slurries. Sodium Tetraborate is used in dental cement as a retarder. The addition of this additive aim to improve the geopolymeric slurries properties for oilwell cementing operation. The slurries studied are constituted of metakaolinite, potassium silicate, potassium hydroxide, non-ionic latex and sodium tetraborate. The properties evaluated were: viscosity, compressive strength, thickening time, density, fluid loss control, at ambient temperature (27 ºC) and at cement specification temperature. The tests were carried out in accordance to the practical recommendations of the norm API RP 10B. The slurries with sodium tetraborate did not change either their rheological properties or their mechanical properties or their density in relation the slurry with no additive. The increase of the concentration of sodium tetraborate increased the water loss at both temperatures studied. The best result obtained with the addition of sodium tetraborate was thickening time, which was tripled. The addition of latex in the slurries studied diminished their rheological properties and their density, however, at ambient temperature, it increased their compressive strength and it functioned as an accelerator. The increase of latex concentration increased the presence of water and then diminished the density of the slurries and increased the water loss. From the results obtained, it was concluded that sodium tetraborate and non-ionic latex are promising additives for geopolymer slurries to be used in oilwell cementing operation

The licensing of a laboratory for manipulating radionuclides in Brazil

Radionuclides take a major role in guidelines of environmental agencies/national organizations of countries worldwide. In Brazil, CNEN-Comissão Nacional de Energia Nuclear is responsible for managing all subjects related to nuclear energy in the country. Thus, laboratories employing radionuclides for the development of their activities must submit a Radioprotection Plan to CNEN in order to get an operation license. Such plan must indicate that the laboratory is exempt of risks to the people involved and designed to fit all related environmental aspects. This was the case of LABIDRO-Hydrochemical and Isotopes Laboratory that belongs to IGCE-Geosciences and Exact Sciences Institute from UNESP - the University of the State of São Paulo Júlio de Mesquita Filho, located at Rio Claro city, São Paulo State, Brazil. The total monthly activity of the radionuclides utilized during the laboratorial activities held at LABIDRO corresponds to 0.01 μCi. This paper describes all information provided by LABIDRO in order to get the CNEN license. The LABIDRO plan also showed the expected radioactive waste released when the experiments take place and CNEN decided that it fits the guidelines established by Brazilian legislation. Therefore, LABIDRO received its license for utilizing radionuclides, which is valid until September 2016. © 2013 WIT Press.

Avaliação dos aspectos dosimétricos no tratamento de câncer de tireóide com Iodo-131

The 131I (radioactive iodine) is one of the most used radionuclides in nuclear medicine for diagnosis and treatment. The present study evaluates the dosimetric aspects related to radioiodine therapy after thyroidectomy in patients with thyroid cancer. The samples were studied with 50 patients undergoing treatment, by assessing the exposures of workers (nursing assistants, staff hygiene, medical and physical), the general public (accompanying and family members) and on the environment. To evaluate the workers, was made a survey of the environmental conditions of the room radioiodine and routines adopted by them during the treatment period. Estimating the dose equivalent per month for each employee, we observed that the maximum levels obtained for nursing assistants, the team of hygiene, medical and physicians were considered low in relation to the extent permitted by law. In order to assess the public, some situations have been suggested for the calculation of equivalent doses in which it was possible to verify the fundamental importance of isolating the patient in the 2 days first. Regarding the environment, the radioactive waste generated by patient had volume of 1.0 m3 and activity estimated at 0.91 mCi, taking a decay time for eliminating them about 75 days to reach the allowable value of 2 μCi / kg system of collecting garbage. Therefore, all radioactive waste removed from the patient's room should be sent to the warehouse for temporary storage of radioactive waste, located away from normal work areas

Fragmentation of extracellular DNA by long-term exposure to radiation from uranium in aquatic environments

Persistent harmful scenarios associated with disposal of radioactive waste, high-background radiation areas and severe nuclear accidents are of great concern regarding consequences to both human health and the environment. Of particular concern is the extracellular DNA in aquatic environments contaminated by radiological substances. Strand breaks induced by radiation promote decrease in the transformation efficiency for extracellular DNA. The focus of this study is the quantification of DNA damage following long-term exposure (over one year) to low doses of natural uranium (an alpha particle emitter) to simulate natural conditions, since nothing is known about alpha radiation induced damage to extracellular DNA. A high-resolution Atomic Force Microscope was used to evaluate DNA fragments. Double-stranded plasmid pBS as a model for extracellular DNA was exposed to different amounts of natural uranium. It was demonstrated that low concentrations of U in water (50 to 150 ppm) produce appreciable numbers of double strand breaks, scaling with the square of the average doses. The importance of these findings for environment monitoring of radiological pollution is addressed.

Spurenanalyse von Uran und Plutonium sowie Speziationsuntersuchungen an Plutonium mit massenspektrometrischen und kapillarelektrophoretischen Methoden

Die Elemente Uran und Plutonium besitzen seit Entdeckung der Kernspaltung und der technischen Nutzung der Kernenergie eine globale Bedeutung. So trägt Pu hauptsächlich zur Radiotoxizität von abgebrannten Brennelementen bei und erfordert im Falle einer Endlagerung in einer tiefen geologischen Formation einen sicheren Verschluss für bis zu einer Million Jahre. Das Wissen über die vorliegenden chemischen Spezies ist dabei entscheidend für das Verständnis der chemisch-physikalischen Wechselwirkungen im jeweiligen geochemischen System, insbesondere mit dem Wirtsgestein (hier Ton) und den allgegenwärtigen Huminstoffen (hier Fulvinsäure). Längerfristig sind so Vorhersagen über einen Transport des hochradioaktiven Abfalls nach Auslaugung und Austritt aus einem Endlager bis in die Biosphäre möglich. Gerade der Ultraspurenbereich, im Fernfeld eines Endlagers zu erwarten, ist dabei von besonderem Interesse. Darüber hinaus machen nuklearforensische Untersuchungen – in Hinblick auf illegal benutztes Nuklearmaterial, Schmuggel oder Nuklearterrorismus – zur Bestimmung der Herkunft, des Alters oder der Radiotoxizität isotopenselektive Nachweismethoden im Ultraspurenbereich notwendig. Im Rahmen dieser Arbeit wurden hierfür die Resonanzionisationsmassenspektrometrie (RIMS) zur isotopenselektiven Spuren- und Ultraspurenanalyse von U und Pu sowie die Kapillarelektrophorese (CE) gekoppelt an die induktiv gekoppelte Plasma (ICP)-Massenspektrometrie (CE-ICP-MS) zur Speziation von Pu eingesetzt. Für den isotopenselektiven Nachweis von Ultraspurenmengen von Uran mittels RIMS wurden vorbereitende Studien durchgeführt und mehrere zweifach resonante Anregungsleitern mit nicht-resonanter Ionisation untersucht. Eine Effizienz von ca. 10^-10 bei einer Nachweisgrenze von 10^12 Atomen U-238 konnte erzielt werden. In Zusammenarbeit mit dem Institut für Radiochemie, TU München, wurde mittels RIMS die Isotopenzusammensetzung von Plutonium, abgetrennt aus einem panzerbrechenden Urangeschoss aus dem Kosovokonflikt, bestimmt und dieses als Waffenplutonium mit einem Gehalt von 15 pg Pu-239/g Uran identifiziert. Rückschlüsse über Herkunft und Alter des Plutoniums konnten daraus gewonnen werden. Für Studien zur Umweltüberwachung von Plutonium in Rheinland-Pfalz wurden Grund-, Oberflächen- und Klärwasserproben mittels RIMS untersucht. Oberhalb der Nachweisgrenze von ca. 10^7 Atomen Pu-239/500 mL konnte kein signifikanter Gehalt bestimmt werden. Zusätzlich wurden Klärschlammproben untersucht, wobei in einer Probe 5,1*10^7 Atome Pu-239/g gemessen wurde, was auf eine Anreicherung von Pu im Klärschlamm aus großen Wasservolumina hindeuten könnte. Speziationsuntersuchungen von Plutonium in Kontakt mit Fulvinsäure und dem Tonmineral Kaolinit wurden in Hinblick auf die Wechselwirkungen im Umfeld eines nuklearen Endlagers durchgeführt. Die Redoxkinetik von Pu(VI) in Kontakt mit Gorleben-Fulvinsäure zeigt eine mit steigendem pH zunehmend schnellere und vollständige Reduktion und ein vergleichbares Verhalten zur Huminsäure. Für ein Plutoniumgemisch aus allen vier umweltrelevanten Oxidationsstufen in Kontakt mit Gorleben-Fulvinsäure konnte nach ca. 1 Monat Kontaktzeit eine fasst vollständige Reduktion zum tri- und tetravalenten Pu beobachtet werden. Sorptionsuntersuchungen der stabilsten Oxidationsstufe, Pu(IV), in Kontakt mit Kaolinit bei pH = 0 bis 13 im Konzentrationsbereich 10^-7 bis 10^-9 mol/L verdeutlichen das ausgeprägte Sorptionsverhalten von Pu(IV) (ca. 60% bis 90% Sorption) im umweltrelevanten pH-Bereich bei einem Einsetzen der Sorption bei pH = 0 bis 2. Im Rahmen des "Colloid and Radionuclide Retardation" (CRR) Experiments im Felslabor Grimsel, Schweizer Alpen, wurde in Zusammenarbeit mit dem Institut für Nukleare Entsorgung, Karlsruhe, die kolloidgetragene Migration von Pu(IV) in einem Grundwasserstrom durch Scherzonen im Granitgestein unter umweltrelevanten Bedingungen untersucht. Bei Zugabe von im Grundwasser stabilen Bentonitkolloiden – Bentonit wird als ein geeignetes Verschlussmaterial für nukleare Abfälle erforscht – konnte ein erhöhter Transport des Pu(IV) beobachtet werden, der durch Sorption des Pu an die mobilen Kolloide hervorgerufen wird. Zur Speziation von Plutonium im Ultraspurenbereich wurde im Rahmen dieser Arbeit an der Entwicklung der Kopplung der CE mit der sehr sensitiven RIMS gearbeitet. Das Prinzip der offline-Kopplung basiert auf dem Sammeln der zu unterschiedlichen Zeiten am Ende der Kapillare eluierten Oxidationsstufen in einzelnen Fraktionen. Aus jeder Fraktion wird ein eigenes Filament hergestellt und mit RIMS auf seinen Plutoniumgehalt untersucht. Eine erste Validierung der Methode konnte durch Bestimmung der Oxidationsstufenzusammensetzung eines bekannten Gemischs erfolgreich für einen Gehalt von ca. 6*10^9 Atome Pu-239 durchgeführt werden. Dies stellt einen möglichen Zugang zu dem erwarteten Konzentrationsbereich im Fernfeld eines Endlagers dar.

Study of the interactions of Neptunium with humic substances and the clay mineral montmorillonite by direct and non direct speciation methods

For the safety assessment of radioactive waste, the possibility of radionuclide migration has to be considered. Since Np (and also Th due to the long-lived 232-Th) will be responsible for the greatest amount of radioactivity one million years after discharge from the reactor, its (im)-mobilization in the geosphere is of great importance. Furthermore, the chemistry of Np(V) is quite similar (but not identical) to the chemistry of Pu(V). Three species of neptunium may be found in the near field of the waste disposal, but pentavalent neptunium is the most abundant species under a wide range of natural conditions. Within this work, the interaction of Np(V) with the clay mineral montmorillonite and melanodins (as model substances for humic acids) was studied. The sorption of neptunium onto gibbsite, a model clay for montmorillonite, was also investigated. The sorption of neptunium onto γ-alumina and montmorillonite was studied in a parallel doctoral work by S. Dierking. Neptunium is only found in ultra trace amounts in the environment. Therefore, sensitive and specific methods are needed for its determination. The sorption was determined by γ spectroscopy and LSC for the whole concentration range studied. In addition the combination of these techniques with ultrafiltration allowed the study of Np(V) complexation with melanoidins. Regrettably, the available speciation methods (e.g. CE-ICP-MS and EXAFS) are not capable to detect the environmentally relevant neptunium concentrations. Therefore, a combination of batch experiments and speciation analyses was performed. Further, the preparation of hybrid clay-based materials (HCM) montmorillonitemelanoidins for sorption studies was achieved. The formation of hybrid materials begins in the interlayers of the montmorillonite, and then the organic material spreads over the surface of the mineral. The sorption of Np onto HCM was studied at the environmentally relevant concentrations and the results obtained were compared with those predicted by the linear additive model by Samadfam. The sorption of neptunium onto gibbsite was studied in batch experiments and the sorption maximum determined at pH~8.5. The sorption isotherm pointed to the presence of strong and weak sorption sites in gibbsite. The Np speciation was studied by using EXAFS, which showed that the sorbed species was Np(V). The influence of M42 type melanodins on the sorption of Np(V) onto montmorillonite was also investigated at pH 7. The sorption of the melanoidins was affected by the order in which the components were added and by ionic strength. The sorption of Np was affected by ionic strength, pointing to outer sphere sorption, whereas the presence of increasing amounts of melanoidins had little influence on Np sorption.

Speziation von Neptunium bei der Migration in Tongestein

Die vorliegende Arbeit wurde im Rahmen eines Stipendiums des interdisziplinärenrnGraduiertenkollegs 826 „Spurenanalytik von Elementspezies: Methodenentwicklung und Anwendungen“, gefördert durch die Deutsche Forschungsgemeinschaft (DFG) und das Land Rheinland-Pfalz, angefertigt. Dabei sollten neue Erkenntnisse über die Wechselwirkung zwischen Neptunium und natürlichem Tongestein mit Hinblick auf die Endlagerung wärmeentwickelnder radioaktiver Abfälle in einem geologischen Tiefenlager gewonnen werden. Auf Grund seiner langen Halbwertszeit von mehr als zwei Millionen Jahren wird Np-237 einen signifikanten Anteil an der Radiotoxizität dieser Abfälle nach Lagerzeiten von mehr als 1000 Jahren haben. Np tritt in Lösung unter umweltrelevanten Bedingungen in den Oxidationsstufen +IV und +V auf. Auf Grund der guten Löslichkeit und daher höheren Mobilität ist Np(V) als die gefährlichere Spezies einzustufen. In den Migrationsstudien wurdernOpalinuston (OPA) aus Mont Terri, Schweiz, als natürliches Referenzmaterial verwendet. Der Fokus dieser Arbeit lag dabei auf der Speziation von Np an der Mineraloberfläche mittels synchrotronbasierter Röntgenabsorptionsspektroskopie (EXAFS/XANES).rnDie Wechselwirkung zwischen Np(V) und OPA wurde zunächst in Batch- und Diffusionsexperimenten in Abhängigkeit verschiedener experimenteller Parameter (u.a. pH, Temperatur, Hintergrundelektrolyt, Einfluss von Huminsäure, Konkurrenz mit U(VI), aerobe/anaerobe Bedingungen) untersucht. Die Untersuchung der Np-Speziation erfolgt zum einen an Pulverproben aus Batch-Experimenten unter aeroben und anaeroben Bedingungen, welche mittels EXAFS-Spektroskopie untersucht wurden. Zum anderen wurden ortsaufgelöste μ-XANES-Messungen an Np-Anreicherungen auf OPA-Dünnschliffen und in Diffusionsproben durchgeführt. Durch Kombination der Spektroskopie mit μ-Rötngenfluoreszenzmapping (XRF) und μ-Röntgenbeugung (XRD) konnten zudem Erkenntnisse über die Elementverteilung von Np und anderen im Opalinuston enthaltenen Elementen sowie über kristalline Mineralphasen im Umfeld von Bereichen erhöhter Np-Konzentration erhalten werden.rnSowohl Sorptionsexperimente als auch die spektroskopischen Untersuchungen zeigten eine teilweise Reduktion von Np(V) zu Np(IV) bei der Wechselwirkung mit OPA. Dabei konnte Pyrit als eine der redoxaktiven Phasen identifiziert werden. In diesem Zusammenhang ist die Bildung schwerlöslicher Np(IV)-Spezies mit Hinblick auf die Endlagerung positiv zu bewerten.

Radiative neutron capture cross section on 238U at the n_TOF CERN facility: a high precision measurement

The aim of this work is to provide a precise and accurate measurement of the 238U(n,gamma) reaction cross-section. This reaction is of fundamental importance for the design calculations of nuclear reactors, governing the behaviour of the reactor core. In particular, fast neutron reactors, which are experiencing a growing interest for their ability to burn radioactive waste, operate in the high energy region of the neutron spectrum. In this energy region inconsistencies between the existing measurements are present up to 15%, and the most recent evaluations disagree each other. In addition, the assessment of nuclear data uncertainty performed for innovative reactor systems shows that the uncertainty in the radiative capture cross-section of 238U should be further reduced to 1-3% in the energy region from 20 eV to 25 keV. To this purpose, addressed by the Nuclear Energy Agency as a priority nuclear data need, complementary experiments, one at the GELINA and two at the n_TOF facility, were scheduled within the ANDES project within the 7th Framework Project of the European Commission. The results of one of the 238U(n,gamma) measurement performed at the n_TOF CERN facility are presented in this work, carried out with a detection system constituted of two liquid scintillators. The very accurate cross section from this work is compared with the results obtained from the other measurement performed at the n_TOF facility, which exploit a different and complementary detection technique. The excellent agreement between the two data-sets points out that they can contribute to the reduction of the cross section uncertainty down to the required 1-3%.

Speziation von Plutonium bei der Sorption und Diffusion in Opalinuston

Die vorliegende Arbeit wurde im Rahmen des BMWi-Verbundprojektes Wechselwirkung und Transport von Aktiniden im natürlichen Tongestein unter Berücksichtigung von Huminstoffen und Tonorganika – Wechselwirkung von Neptunium und Plutonium mit natürlichem Tongestein“ durchgeführt. Um die langfristige Sicherheit der nuklearen Endlager beurteilen zu können, muss eine mögliche Migration der radiotoxischen Abfälle in die Umwelt betrachtet werden. Wegen seiner langen Halbwertszeit (24000 a) leistet Pu-239 einen wesentlichen Beitrag zur Radiotoxizität abgebrannter Kernbrennstoffe in einem Endlager. Das redox-sensitive Pu tritt in Lösung unter umweltrelevanten Bedingungen in den Oxidationsstufen +III bis +VI auf und kann nebeneinander in bis zu vier Oxidationsstufen vorliegen. Tonsteinformationen werden als mögliches Wirtsgestein für Endlager hoch-radioaktiver Abfälle betrachtet. Deshalb sind ausführliche Informationen zur Mobilisierung und Immobilisierung des Pu durch/in das Grundwasser aus einem Endlager von besonderer Bedeutung. In dieser Arbeit wurden neue Erkenntnisse über die Wechselwirkung zwischen Pu und dem natürlichen Tongestein Opalinuston (OPA, Mont Terri, Schweiz) mit Hinblick auf die Endlagerung wärmeentwickelnder radioaktiver Abfälle in einem geologischen Tiefenlager gewonnen.rnDer Fokus der Arbeit lag dabei auf der Bestimmung der Speziation von Pu an der Mineraloberfläche nach Sorptions- und Diffusionsprozessen mittels verschiedener synchrotronbasierter Methoden (µ-XRF, µ-XANES/EXAFS, µ-XRD, XANES/EXAFS). rnDie Wechselwirkung zwischen Pu und OPA wurde zunächst in Batch- und Diffusionsexperimenten in Abhängigkeit verschiedener experimenteller Parameter (u.a. pH, Pu-Oxidationsstufe) untersucht. In Sorptionsexperimenten konnte gezeigt werden, dass einige Parameter (z.B. Temperatur, Huminsäure) einen deutlichen Einfluss auf die Sorption von Pu haben.rnDie Speziationsuntersuchungen wurden zum einen an Pulverproben aus Batchexperimenten und zum anderen an OPA-Dünnschliffen bzw. Diffusionsproben in Abhängigkeit verschiedener experimenteller Parameter durchgeführt. Die EXAFS-Messungen an der Pu LIII-Kante der Pulverproben ergaben, dass eine innersphäriche Sorption von Pu(IV) an Tongestein unabhängig von dem Ausgangsoxidationszustand des Plutoniums in Lösung stattgefunden hat. Durch die Kombination der ortsaufgelösten Methoden wurde erstmalig mittels μ-XRF die Verteilung von Pu und anderen in OPA enthaltenen Elementen bestimmt. µ-XANES-Spektren an Pu-Anreicherungen auf OPA-Dünnschliffen und in Diffusionsproben bestätigen, dass das weniger mobile Pu(IV) die dominierende Spezies nach den Sorptions- und Diffusionsprozessen ist. Darüber hinaus wurde zum ersten Mal ein Diffusionsprofil von Pu in OPA mittels µ-XRF gemessen. Die Speziationsuntersuchungen mittels μ-XANES zeigten, dass das eingesetzte Pu(V) entlang seines Diffusionspfades zunehmend zu Pu(IV) reduziert wird. Mit µ-XRD wurde Illit als dominierende Umgebung, in der Pu angereichert wurde, identifiziert und Siderit als eine redoxaktive Phase auftreten kann. Die Ergebnisse dieser Arbeit zeigen, dass die Sicherheit von OPA als Wirtsgestein eines Endlagers hoch-radioaktiver Abfälle positiv zu bewerten ist. rn