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

Iodide interaction with natural pyrite

29I is one of the major dose-determining nuclides in the safety analysis of deep storage of radioactive waste. Iodine forms anionic species that hardly sorb on the surfaces of common host-rock minerals. Recently, interest has arisen on the role of pyrite, an accessory mineral capable of binding anionic selenium. Whereas the interaction of selenium with pyrite is well documented, corresponding results on iodine sorption are still scarce and controversial. Pyrite is present in argicilleous rocks which are being considered in many countries as potential host rocks for a radioactive waste repository. The uptake of iodide (I−) on natural pyrite was investigated under nearly anoxic conditions (O2 < 5 ppm) over a wide concentration range (10−11–10−3 M total I−) using 125I as the radioactive tracer. Weak but measurable sorption was observed; distribution coefficients (R d) were less than 0.002 m3 kg−1 and decreased with increasing total iodide concentration. Iodide sorption was connected to the presence of oxidized clusters on the pyrite surface, which were presumably formed by reaction with limited amounts of dissolved oxygen. The results obtained indicated that pyrite cannot be considered as an effective scavenger of 129I under the geochemical conditions prevailing in underground radioactive waste geologic storage.

Diffusion-driven transport in clayrock formations

Clay mineral-rich sedimentary formations are currently under investigation to evaluate their potential use as host formations for installation of deep underground disposal facilities for radioactive waste (e.g. Boom Clay (BE), Opalinus Clay (CH), Callovo-Oxfordian argillite (FR)). The ultimate safety of the corresponding repository concepts depends largely on the capacity of the host formation to limit the flux towards the biosphere of radionuclides (RN) contained in the waste to acceptably low levels. Data for diffusion-driven transfer in these formations shows extreme differences in the measured or modelled behaviour for various radionuclides, e. g. between halogen RN (Cl-36, I-129) and actinides (U-238,U-235, Np-237, Th-232, etc.), which result from major differences between RN of the effects on transport of two phenomena: diffusion and sorption. This paper describes recent research aimed at improving understanding of these two phenomena, focusing on the results of studies carried out during the EC Funmig IP on clayrocks from the above three formations and from the Boda formation (HU). Project results regarding phenomena governing water, cation and anion distribution and mobility in the pore volumes influenced by the negatively-charged surfaces of clay minerals show a convergence of the modelling results for behaviour at the molecular scale and descriptions based on electrical double layer models. Transport models exist which couple ion distribution relative to the clay-solution interface and differentiated diffusive characteristics. These codes are able to reproduce the main trends in behaviour observed experimentally, e.g. D-e(anion) < D-e(HTO) < D-e(cation) and D-e(anion) variations as a function of ionic strength and material density. These trends are also well-explained by models of transport through ideal porous matrices made up of a charged surface material. Experimental validation of these models is good as regards monovalent alkaline cations, in progress for divalent electrostatically-interacting cations (e.g. Sr2+) and still relatively poor for 'strongly sorbing', high K-d cations. Funmig results have clarified understanding of how clayrock mineral composition, and the corresponding organisation of mineral grain assemblages and their associated porosity, can affect mobile solute (anions, HTO) diffusion at different scales (mm to geological formation). In particular, advances made in the capacity to map clayrock mineral grain-porosity organisation at high resolution provide additional elements for understanding diffusion anisotropy and for relating diffusion characteristics measured at different scales. On the other hand, the results of studies focusing on evaluating the potential effects of heterogeneity on mobile species diffusion at the formation scale tend to show that there is a minimal effect when compared to a homogeneous property model. Finally, the results of a natural tracer-based study carried out on the Opalinus Clay formation increase confidence in the use of diffusion parameters measured on laboratory scale samples for predicting diffusion over geological time-space scales. Much effort was placed on improving understanding of coupled sorption-diffusion phenomena for sorbing cations in clayrocks. Results regarding sorption equilibrium in dispersed and compacted materials for weakly to moderately sorbing cations (Sr2+, Cs+, Co2+) tend to show that the same sorption model probably holds in both systems. It was not possible to demonstrate this for highly sorbing elements such as Eu(III) because of the extremely long times needed to reach equilibrium conditions, but there does not seem to be any clear reason why such elements should not have similar behaviour. Diffusion experiments carried out with Sr2+, Cs+ and Eu(III) on all of the clayrocks gave mixed results and tend to show that coupled diffusion-sorption migration is much more complex than expected, leading generally to greater mobility than that predicted by coupling a batch-determined K-d and Ficks law based on the diffusion behaviour of HTO. If the K-d measured on equivalent dispersed systems holds as was shown to be the case for Sr, Cs (and probably Co) for Opalinus Clay, these results indicate that these cations have a D-e value higher than HTO (up to a factor of 10 for Cs+). Results are as yet very limited for very moderate to strongly sorbing species (e.g. Co(II), Eu(III), Cu(II)) because of their very slow transfer characteristics. (C) 2011 Elsevier Ltd. All rights reserved.

Experimental characterization of cement–bentonite interaction using core infiltration techniques and 4D computed tomography

Deep geological storage of radioactive waste foresees cementitious materials as reinforcement of tunnels and as backfill. Bentonite is proposed to enclose spent fuel drums, and as drift seals. The emplacement of cementitious material next to clay material generates an enormous chemical gradient in pore water composition that drives diffusive solute transport. Laboratory studies and reactive transport modeling predict significant mineral alteration at and near interfaces, mainly resulting in a decrease of porosity in bentonite. The goal of this project is to characterize and quantify the cement/bentonite skin effects spatially and temporally in laboratory experiments. A newly developed mobile X-ray transparent core infiltration device was used, which allows performing X-ray computed tomography (CT) periodically without interrupting a running experiment. A pre-saturated cylindrical MX-80 bentonite sample (1920 kg/m3 average wet density) is subjected to a confining pressure as a constant total pressure boundary condition. The infiltration of a hyperalkaline (pH 13.4), artificial OPC (ordinary Portland cement) pore water into the bentonite plug alters the mineral assemblage over time as an advancing reaction front. The related changes in X-ray attenuation values are related to changes in phase densities, porosity and local bulk density and are tracked over time periodically by non-destructive CT scans.

Transport of 234U in the Opalinus Clay on centimetre to decimetre scales

The Opalinus Clay formation in North Switzerland is a potential host rock for a deep underground radioactive waste repository. The distribution of U-238, U-234 and Th-230 was studied in rock samples of the Opalinus Clay from an exploratory borehole at Benken (Canton of Zurich) using MC-ICP-MS. The aim of U-234 was to assess the in situ, long-term migration behaviour in this rock. Very low hydraulic conductivities of the Opalinus Clay, reducing potential of the pore water and its chemical equilibrium with the host rock are expected to render both U-238 and Th-230 immobile. If U is heterogeneously distributed in the Opalinus Clay, gradients in the supply of U-234 from the rock matrix to the pore water by the decay of U-238 will be established. Diffusive redistribution separates U-234 from its immobile parent U-238 resulting in bulk rock U-234/U-238 activity disequilibria. These may provide a means of estimating the mobility of U-234 in the rock if the diffusion rate of U-234 is significant compared to its decay rate. Sampling was carried out on two scales. Drilling of cm-spaced samples from the drill-core was done to study mobility over short distances and elucidate possible small-scale lithological control. Homogenized 25-cm-long portions of a 2-m-long drill-core section were prepared to provide information on transport over a longer distance. Variations in U and/or Th content on the cm-scale between clays and carbonate-sandy layers are revealed by beta-scanning, which shows that the (dominant) clay is richer in both elements. Samples were digested using aqua regia followed by total HF dissolution, yielding two fractions. in all studied samples U was found to be concentrated in the HF digestion fraction. It has a high U/Th ratio and a study by SEM-EDS points to sub-mu m up to several mu m in size zircon grains as the main U-rich phase. This fraction consistently has U-234/U-238 activity ratios below unity. The minute zircon grains constitute the major reservoir of U in the rock and act as constant rate suppliers of U-234 into the rock matrix and the pore water. The aqua regia leach fraction was found to be enriched in Th, and complementary to the HF fraction, having U-234/U-238 activity ratios above unity. It is believed that these U activity ratios reflect the surplus of having U-234 delivered from the zircon grains. Some cm-spaced samples show bulk rock U-234/U-238 activity ratios that are markedly out of equilibrium. In most of them a striking negative correlation between the total U content and the bulk rock U-234/U-238 activity ratios is observed. This is interpreted to indicate net U-234 transfer from regions of higher supply of U-234 towards those of lower supply which is, in most cases, equivalent to transfer from clayey towards carbonate/sandy portions of the rock. In contrast, the 25 cm averaged samples all have uniform bulk rock U-234/U-238 activity ratios in equilibrium, indicating U immobility in the last 1-1.5 Ma on this spatial scale. It is concluded that the small-scale lithological variations which govern U spatial distribution in the Opalinus Clay are the major factor determining U-234 in situ supply rates, regulating its diffusive fluxes and controlling the observed bulk rock U-234/U-238 activity ratios. A simple box-model is presented to simulate the measured bulk rock U-234/U-238 activity ratios and to give an additional insight into the studied system. (C) 2008 Elsevier Ltd. All rights reserved.

Matrix Porewater In Crystalline Rocks: Extraction and Analysis

The chemical and isotopic characterization of porewater residing in the inter- and intragranular pore space of the low-permeability rock matrix is an important component with respect to the site characterization and safety assessment of potential host rocks for a radioactive waste disposal. The chemical and isotopic composition of porewater in such low permeability rocks has to be derived by indirect extraction techniques applied to naturally saturated rock material. In most of such indirect extraction techniques – especially in case of rocks of a porosity below about 2 vol.% – the original porewater concentrations are diluted and need to be back-calculated to in-situ concentrations. This requires a well-defined value for the connected porosity – accessible to different solutes under in-situ conditions. The derivation of such porosity values, as well as solute concentrations, is subject to various perturbations during drilling, core sampling, storage and experiments in the laboratory. The present study aims to demonstrate the feasibility of a variety of these techniques to charac-terize porewater and solute transport in crystalline rocks. The methods, which have been de-veloped during multiple porewater studies in crystalline environments, were applied on four core samples from the deep borehole DH-GAP04, drilled in the Kangerlussuaq area, Southwest Greenland, as part of the joint NWMO–Posiva–SKB Greenland Analogue Project (GAP). Potential artefacts that can influence the estimation of in situ porewater chemistry and isotopes, as well as their controls, are described in detail in this report, using specific examples from borehole DH-GAP04

Experimental Characterization and Quantification of Cement-Bentonite Interaction using Core Infiltration Techniques Coupled with X-ray Tomography

Deep geological storage of radioactive waste foresees cementitious materials as reinforcement of tunnels and as backfill. Bentonite is proposed to enclose spent fuel canisters and as drift seals. Sand/bentonite (s/b) is foreseen as backfill material of access galleries or as drift seals. The emplacement of cementitious material next to clay material generates an enormous chemical gradient in pore-water composition that drives diffusive solute transport. Laboratory studies and reactive transport modeling predicted significant mineral alteration at and near interfaces, mainly resulting in a decrease of porosity in bentonite. The goal of this thesis was to characterize and quantify the cement/bentonite interactions both spatially and temporally in laboratory experiments. A newly developed mobile X-ray transparent core infiltration device was used to perform X-ray computed tomography (CT) scans without interruption of running experiments. CT scans allowed tracking the evolution of the reaction plume and changes in core volume/diameter/density during the experiments. In total 4 core infiltration experiments were carried out for this study with the compacted and saturated cores consisting of MX-80 bentonite and sand/MX-80 bentonite mixture (s/b; 65/35%). Two different high-pH cementitious pore-fluids were infiltrated: a young (early) ordinary Portland cement pore-fluid (APWOPC; K+–Na+–OH-; pH 13.4; ionic strength 0.28 mol/kg) and a young ‘low-pH’ ESDRED shotcrete pore-fluid (APWESDRED; Ca2+–Na+–K+–formate; pH 11.4; ionic strength 0.11 mol/kg). The experiments lasted between 1 and 2 years. In both bentonite experiments, the hydraulic conductivity was strongly reduced after switching to high-pH fluids, changing eventually from an advective to a diffusion-dominated transport regime. The reduction was mainly induced by mineral precipitation and possibly partly also by high ionic strength pore-fluids. Both bentonite cores showed a volume reduction and a resulting transient flow in which pore-water was squeezed out during high-pH infiltration. The outflow chemistry was characterized by a high ionic strength, while chloride in the initial pore water got replaced as main anionic charge carrier by sulfate, originating from gypsum dissolution. The chemistry of the high-pH fluids got strongly buffered by the bentonite, consuming hydroxide and in case of APWESDRED also formate. Hydroxide got consumed by mineral reactions (saponite and possibly talc and brucite precipitation), while formate being affected by bacterial degradation. Post-mortem analysis showed reaction zones near the inlet of the bentonite core, characterized by calcium and magnesium enrichment, consisting predominately of calcite and saponite, respectively. Silica got enriched in the outflow, indicating dissolution of silicate-minerals, identified as preferentially cristobalite. In s/b, infiltration of APWOPC reduced the hydraulic conductivity strongly, while APWESDRED infiltration had no effect. The reduction was mainly induced by mineral precipitation and probably partly also by high ionic strength pore-fluids. Not clear is why the observed mineral precipitates in the APWESDRED experiment had no effect on the fluid flow. Both s/b cores showed a volume expansion along with decreasing ionic strengths of the outflow, due to mineral reactions or in case of APWESDRED infiltration also mediated by microbiological activity, consuming hydroxide and formate, respectively. The chemistry of the high-pH fluids got strongly buffered by the s/b. In the case of APWESDRED infiltration, formate reached the outflow only for a short time, followed by enrichment in acetate, indicating most likely biological activity. This was in agreement to post-mortem analysis of the core, observing black spots on the inflow surface, while the sample had a rotten-egg smell indicative of some sulfate reduction. Post-mortem analysis showed further in both cores a Ca-enrichment in the first 10 mm of the core due to calcite precipitation. Mg-enrichment was only observed in the APWOPC experiment, originating from newly formed saponite. Silica got enriched in the outflow of both experiments, indicating dissolution of silicate-minerals, identified in the OPC experiment as cristobalite. The experiments attested an effective buffering capacity for bentonite and s/b, a progressing coupled hydraulic-chemical sealing process and also the preservation of the physical integrity of the interface region in this setup with a total pressure boundary condition on the core sample. No complete pore-clogging was observed but the hydraulic conductivity got rather strongly reduced in 3 experiments, explained by clogging of the intergranular porosity (macroporosity). Such a drop in hydraulic conductivity may impact the saturation time of the buffer in a nuclear waste repository, although the processes and geometry will be more complex in repository situation.