Détection des événements de "Minimum Bias" et neutrons avec les détecteurs ATLAS-MPX par simulations

Un réseau de seize détecteurs ATLAS-MPX a été mis en opération dans le détecteur ATLAS au LHC du CERN. Les détecteurs ATLAS-MPX sont sensibles au champ mixte de radiation de photons et d’électrons dans la caverne d’ATLAS et sont recouverts de convertisseurs de fluorure de lithium et de polyéthylène pour augmenter l’efficacité de détection des neutrons thermiques et des neutrons rapides respectivement. Les collisions à haute énergie sont dominées par des interactions partoniques avec petit moment transverse pT , associés à des événements de “minimum bias”. Dans notre cas la collision proton-proton se produit avec une énergie de 7 TeV dans le centre de masse avec une luminosité de 10³⁴cm⁻²s⁻¹ telle que fixée dans les simulations. On utilise la simulation des événements de "minimum bias" générés par PYTHIA en utilisant le cadre Athena qui fait une simulation GEANT4 complète du détecteur ATLAS pour mesurer le nombre de photons, d’électrons, des muons qui peuvent atteindre les détecteurs ATLASMPX dont les positions de chaque détecteur sont incluses dans les algorithmes d’Athena. Nous mesurons les flux de neutrons thermiques et rapides, générés par GCALOR, dans les régions de fluorure de lithium et de polyéthylène respectivement. Les résultats des événements de “minimum bias” et les flux de neutrons thermiques et rapides obtenus des simulations sont comparés aux mesures réelles des détecteurs ATLAS-MPX.

Thermal neutron capture effects in radioactive and stable nuclide systems

Neutron capture effects in meteorites and lunar surface samples have been successfully used in the past to study exposure histories and shielding conditions. In recent years, however, it turned out that neutron capture effects produce a nuisance for some of the short-lived radionuclide systems. The most prominent example is the 182Hf-182W system in iron meteorites, for which neutron capture effects lower the 182W/184W ratio, thereby producing too old apparent ages. Here, we present a thorough study of neutron capture effects in iron meteorites, ordinary chondrites, and carbonaceous chondrites, whereas the focus is on iron meteorites. We study in detail the effects responsible for neutron production, neutron transport, and neutron slowing down and find that neutron capture in all studied meteorite types is not, as usually expected, exclusively via thermal neutrons. In contrast, most of the neutron capture in iron meteorites is in the epithermal energy range and there is a significant contribution from epithermal neutron capture even in stony meteorites. Using sophisticated particle spectra and evaluated cross section data files for neutron capture reactions we calculate the neutron capture effects for Sm, Gd, Cd, Pd, Pt, and Os isotopes, which all can serve as neutron-dose proxies, either in stony or in iron meteorites. In addition, we model neutron capture effects in W and Ag isotopes. For W isotopes, the GCR-induced shifts perfectly correlate with Os and Pt isotope shifts, which therefore can be used as neutron-dose proxies and permit a reliable correction. We also found that GCR-induced effects for the 107Pd-107Ag system can be significant and need to be corrected, a result that is in contrast to earlier studies.

Finnish Dosimetric Practice for Epithermal Neutron Beam Dosimetry in Boron Neutron Capture Therapy

Boron neutron capture therapy (BNCT) is a form of chemically targeted radiotherapy that utilises the high neutron capture cross-section of boron-10 isotope to achieve a preferential dose increase in the tumour. The BNCT dosimetry poses a special challenge as the radiation dose absorbed by the irradiated tissues consists of several dose different components. Dosimetry is important as the effect of the radiation on the tissue is correlated with the radiation dose. Consistent and reliable radiation dose delivery and dosimetry are thus basic requirements for radiotherapy. The international recommendations for are not directly applicable to BNCT dosimetry. The existing dosimetry guidance for BNCT provides recommendations but also calls for investigating for complementary methods for comparison and improved accuracy. In this thesis the quality assurance and stability measurements of the neutron beam monitors used in dose delivery are presented. The beam monitors were found not to be affected by the presence of a phantom in the beam and that the effect of the reactor core power distribution was less than 1%. The weekly stability test with activation detectors has been generally reproducible within the recommended tolerance value of 2%. An established toolkit for epithermal neutron beams for determination of the dose components is presented and applied in an international dosimetric intercomparison. The measured quantities (neutron flux, fast neutron and photon dose) by the groups in the intercomparison were generally in agreement within the stated uncertainties. However, the uncertainties were large, ranging from 3-30% (1 standard deviation), emphasising the importance of dosimetric intercomparisons if clinical data is to be compared between different centers. Measurements with the Exradin type 2M ionisation chamber have been repeated in the epithermal neutron beam in the same measurement configuration over the course of 10 years. The presented results exclude severe sensitivity changes to thermal neutrons that have been reported for this type of chamber. Microdosimetry and polymer gel dosimetry as complementary methods for epithermal neutron beam dosimetry are studied. For microdosimetry the comparison of results with ionisation chambers and computer simulation showed that the photon dose measured with microdosimetry was lower than with the two other methods. The disagreement was within the uncertainties. For neutron dose the simulation and microdosimetry results agreed within 10% while the ionisation chamber technique gave 10-30% lower neutron dose rates than the two other methods. The response of the BANG-3 gel was found to be linear for both photon and epithermal neutron beam irradiation. The dose distribution normalised to dose maximum measured by MAGIC polymer gel was found to agree well with the simulated result near the dose maximum while the spatial difference between measured and simulated 30% isodose line was more than 1 cm. In both the BANG-3 and MAGIC gel studies, the interpretation of the results was complicated by the presence of high-LET radiation.

Proton magnetic resonance spectroscopy of a boron neutron capture therapy 10B-carrier, L-p-boronophenylalanine-fructose complex

Boron neutron capture therapy (BNCT) is a radiotherapy that has mainly been used to treat malignant brain tumours, melanomas, and head and neck cancer. In BNCT, the patient receives an intravenous infusion of a 10B-carrier, which accumulates in the tumour area. The tumour is irradiated with epithermal or thermal neutrons, which result in a boron neutron capture reaction that generates heavy particles to damage tumour cells. In Finland, boronophenylalanine fructose (BPA-F) is used as the 10B-carrier. Currently, the drifting of boron from blood to tumour as well as the spatial and temporal accumulation of boron in the brain, are not precisely known. Proton magnetic resonance spectroscopy (1H MRS) could be used for selective BPA-F detection and quantification as aromatic protons of BPA resonate in the spectrum region, which is clear of brain metabolite signals. This study, which included both phantom and in vivo studies, examined the validity of 1H MRS as a tool for BPA detection. In the phantom study, BPA quantification was studied at 1.5 and 3.0 T with single voxel 1H MRS, and at 1.5 T with magnetic resonance imaging (MRSI). The detection limit of BPA was determined in phantom conditions at 1.5 T and 3.0 T using single voxel 1H MRS, and at 1.5 T using MRSI. In phantom conditions, BPA quantification accuracy of ± 5% and ± 15% were achieved with single voxel MRS using external or internal (internal water signal) concentration references, respectively. For MRSI, a quantification accuracy of <5% was obtained using an internal concentration reference (creatine). The detection limits of BPA in phantom conditions for the PRESS sequence were 0.7 (3.0 T) and 1.4 mM (1.5 T) mM with 20 × 20 × 20 mm3 single voxel MRS, and 1.0 mM with acquisition-weighted MRSI (nominal voxel volume 10(RL) × 10(AP) × 7.5(SI) mm3), respectively. In the in vivo study, an MRSI or single voxel MRS or both was performed for ten patients (patients 1-10) on the day of BNCT. Three patients had glioblastoma multiforme (GBM), and five patients had a recurrent or progressing GBM or anaplastic astrocytoma gradus III, and two patients had head and neck cancer. For nine patients (patients 1-9), MRS/MRSI was performed 70-140 min after the second irradiation field, and for one patient (patient 10), the MRSI study began 11 min before the end of the BPA-F infusion and ended 6 min after the end of the infusion. In comparison, single voxel MRS was performed before BNCT, for two patients (patients 3 and 9), and for one patient (patient 9), MRSI was performed one month after treatment. For one patient (patient 10), MRSI was performed four days before infusion. Signals from the tumour spectrum aromatic region were detected on the day of BNCT in three patients, indicating that in favourable cases, it is possible to detect BPA in vivo in the patient’s brain after BNCT treatment or at the end of BPA-F infusion. However, because the shape and position of the detected signals did not exactly match the BPA spectrum detected in the in vitro conditions, assignment of BPA is difficult. The opportunity to perform MRS immediately after the end of BPA-F infusion for more patients is necessary to evaluate the suitability of 1H MRS for BPA detection or quantification for treatment planning purposes. However, it could be possible to use MRSI as criteria in selecting patients for BNCT.

Sputtering of uranium

Sputtering yields for uranium metal under bombardment by 13 - 120 keV protons and by 20 - 120 keV He+ are presented. Angular distributions of the material sputtered by these ions are also given. Sputtering yields for 40 and 80 keV Ar+ were measured as well.

The technique employed to make these measurements was the detection of fission tracks in mica produced by ^(235)U sputtered onto collector foils which were subsequently exposed to a high fluence of thermal neutrons. The technique is extremely sensitive and allowed the measurement of sputtering yields less than 10^(-4) atoms per ion. It also made possible a detailed study of the emission of chunks from the uranium targets during sputtering. Mass distributions of chunks emitted during bombardment by 40 - 120 keV protons and by 80 keV argon are presented.

Comparisons are made between the experimental results and those predicted by the Sigmund theory of sputtering.

Pulsed neutron measurements in two adjacent finite media

The pulsed neutron technique has been used to investigate the decay of thermal neutrons in two adjacent water-borated water finite media. Experiments were performed with a 6x6x6 inches cubic assembly divided in two halves by a thin membrane and filled with pure distilled water on one side and borated water on the other side.

The fundamental decay constant was measured versus the boric acid concentration in the poisoned medium. The experimental results showed good agreement with the predictions of the time dependent diffusion model. It was assumed that the addition of boric acid increases the absorption cross section of the poisoned medium without affecting its diffusion properties: In these conditions, space-energy separability and the concept of an “effective” buckling as derived from diffusion theory were introduced. Their validity was supported by the experimental results.

Measurements were performed with the absorption cross section of the poisoned medium increasing gradually up to 16 times its initial value. Extensive use of the IBM 7090-7094 Computing facility was made to analyze properly the decay data (Frantic Code). Attention was given to the count loss correction scheme and the handling of the statistics involved. Fitting of the experimental results into the analytical form predicted by the diffusion model led to

Ʃ_av = 4721 sec^-1 (±150)

D_o = 35972 cm²sec^-1 (±800) for water at 21˚C

C (given) = 3420 cm⁴sec^-1

These values, when compared with published data, show that the diffusion model is adequate in describing the experiment.

Caracterização de um sistema digital de aquisição de imagens radiográficas utilizando nêutrons térmicos e raios gama para a inspeção de componentes mecânicos.

Ensaio não destrutivo é uma ferramenta essencial quando um equipamento, dispositivo ou componente não pode ser submetido a procedimentos destrutivos ou invasivos devido a razões de segurança, alto custo ou outras restrições físicas ou logísticas. Dentro deste quadro radiografias por transmissão com raios gama e nêutrons térmicos são técnicas singulares para inspecionar um objeto e desvendar sua estrutura interna devido à capacidade de atravessar uma vasta gama de materiais utilizados na indústria. Grosso modo, raios gama são mais atenuados por materiais pesados enquanto nêutrons térmicos são mais atenuados por materiais mais leves, tornando-as ferramentas complementares. Este trabalho apresenta os resultados obtidos na inspeção de vários componentes mecânicos, através da radiografia por transmissão com nêutrons térmicos e raios gama. O fluxo de nêutrons térmicos de 4,46x105 n.cm-2.s-1 disponível no canal principal do reator de pesquisa Argonauta do Instituto de Engenharia Nuclear foi usado como fonte para as imagens radiográficas com nêutrons. Raios dekeV emitidos pelo 198Au, também produzido no reator, foram usados como fonte de radiação para radiografias . Imaging Plates, especificamente produzidos para operar com nêutrons térmicos ou com raios X, foram empregados como detectores e dispositivos de armazenamento e captação de imagens para cada uma dessas radiações. Esses dispositivos exibem varias vantagens quando comparados ao filme radiográfico convencional. Com efeito, além de maior sensibilidade e serem reutilizáveis não são necessários câmaras escuras e processamento químico para a revelação. Em vez disso, ele é lido por um feixe de laser que libera elétrons armadilhados na rede cristalina durante a exposição à radiação, fornecendo uma imagem final digital. O desempenho de ambos os sistemas de aquisição de imagens, assim constituído, foi avaliado com respeito à sensibilidade, resolução espacial, linearidade e range dinâmico, incluído uma comparação com sistemas radiográficos com nêutrons empregando filmes e folhas de gadolínio como conversor de nêutrons em partículas carregadas. Além desta caracterização, diversos equipamentos e componentes foram radiografados com ambos os sistemas visando-se avaliar suas capacidades de desvendar a estrutura interna desses objetos e detectar estruturas e estados anormais. Dentro desta abordagem, uma neutrongrafia detectou a presença de material cerâmico remanescente empregado como molde no processo de fabricação nos canais de refrigeração de uma aleta do estator de uma turbina tipo turbo-fan, que deveria estar livre desse material. O reostato danificado de um sensor de pressão automotivo, foi identificado por neutrongrafia, embora nesse caso a radiografia também conseguiu realizar essa tarefa com melhor resolução, corroborando assim as curvas de resolução espacial obtidas na caracterização dos dois sistemas. A homogeneidade da distribuição do material encapsulado em uma gaxeta explosiva de chumbo utilizada na indústria aeroespacial foi igualmente verificada por neutrongrafia porque esse metal é relativamente transparente para nêutrons, mas suficientemente opaco para o explosivo rico em hidrogênio. Diversos outros instrumentos e componentes tais como variômetro, altímetro, bússola aeronáutica, injetor automotivo de combustível, foto-camera, disco rígido de computador, motor de passo, conectores eletrônicos e projéteis foram radiografados com ambos os sistemas visando avaliar suas habilidades em desvendar diferentes peculiaridades em função do agente interrogador.

Determination of potassium and sodium in an ash sample by gamma-ray spectroscopy

Neutron activation analysis and gamma-ray spectroscopy were used to determine the quantity of potassium and sodium in an ash sample of Tabebuia sp bombarded with thermal neutrons. These techniques, widely applied in nuclear physics, can be used in the context of wood science as an alternative for the usual physical chemistry methods applied in this area. The quantity of K and Na in an 8.60 +/- 0.10 mg of ash was determined as being 1.3 +/- 0.3 mg and 11.0 +/- 1.8 mu g, respectively. The ratio of Tabebuia sp converted into ash was also determined as 0.758 +/- 0.004%.

Problems related to the employment of thin uranium films as neutron dosimeters

Thin uranium films built on muscovite mica basis and obsidian samples having known ages were irradiated with thermal neutrons at the IPEN/CNEN reactor, São Paulo. Comparing thin film performance with the obsidian one, it was observed that the latter feel a greater neutron fluence. Nominal fluences at the used facility are in agreement with the results obtained analysing the obsidian samples. A probable hypothesis to explain this disagreement, namely, the uranium loss from the thin films, was ruled out. © 1995.

Nanodiamanten in primitiven Meteoriten: Strukturuntersuchungen und Einfluss des Rückstoßes bei beta-Zerfällen

Im Rahmen dieser Arbeit wurden Untersuchungen zur Rückstoßeffekten, sowie Ausheizversuche zur Erforschung struktureller Veränderungen und Änderung der Edelgaskonzentrationen und Ausgasungsmuster in meteoritischen Nanodiamanten durchgeführt. In der ersten Versuchsserie wurden die durch prompte "?"-Strahlung bei Neutronenaktivierung von Brom in terrestrische Detonationsdiamanten und durch den "?"-Zerfall von 22Na in synthetischen und meteoritischen Diamanten verursachten Rückstoßverluste bestimmt. Diese wurden mit theoretischen Verlustwerten, berechnet mit Hilfe der SRIM-Software und der Korngrößenverteilung, verglichen. Im Fall der prompten "?"-Strahlung war der Unterschied signifikant. Hierzu können allerdings systematische Unsicherheiten in den gemessenen Verlusten, wie z.B. unbekannte Br-Verteilung innerhalb der Diamanten beigetragen haben. Die Ergebnisse des zweiten Versuchs bei kleineren Rückstoß-Energien, wie sie auch in der Natur vorkommen würden, zeigten dagegen keinen signifikanten Unterschied. Dies führt zu der Schlussfolgerung, dass weder das „Fehlen“ einiger in Supernovae Typ II gebildeter Radionuklide, wie 26Al, 44Ti, in den Diamanten noch die in einem für die Erklärung des Xe-H vorgeschlagenen Modell benötigte frühzeitige Trennung der Vorläuferkerne stabiler Xe-Isotope von den stabilen Xe-Isotopen durch Rückstoßverluste erklärt werden kann. In der zweiten Versuchsreihe wurden meteoritische Nanodiamantproben bei unterschiedlichen Temperaturen im Vakuum vorgeheizt und danach, um die Heizprodukte zu entfernen, chemisch behandelt. Bei allen Vorheiztemperaturen wurden zwiebelähnliche Strukturen registriert und auch in den nachbehandelten Proben wurden, bedingt durch die wegen Verklumpung der Proben eingeschränkte chemische Behandlung, neben Diamanten unveränderte, oder teilweise zerstörte Umwandlungsprodukte gefunden. Weiterhin wurden Edelgaskonzentrationen und Ausgasungsmuster gemessen, um die durch Vorheizen und chemische Behandlung bedingten Veränderungen im Vergleich zu den Original-Diamanten zu untersuchen. Ein unerwartetes Ergebnis dieser Untersuchungen war, dass die vorgeheizten und chemisch nachbehandelten Proben deutlich niedrigere Ausbeuten im Vergleich zu den nur vorgeheizten zeigten, was darauf hindeutete, dass die während des Vorheizens entstandenen Umwandlungsprodukte, wie z.B. zwiebelähnliche Strukturen, Edelgase zurückhalten konnten, die später (teilweise) durch chemische Behandlung entfernt wurden.

Neutron capture on Pt isotopes in iron meteorites and the Hf–W chronology of core formation in planetesimals

The short-lived 182Hf–182W isotope system can provide powerful constraints on the timescales of planetary core formation, but its application to iron meteorites is hampered by neutron capture reactions on W isotopes resulting from exposure to galactic cosmic rays. Here we show that Pt isotopes in magmatic iron meteorites are also affected by capture of (epi)thermal neutrons and that the Pt isotope variations are correlated with variations in 182W/184W. This makes Pt isotopes a sensitive neutron dosimeter for correcting cosmic ray-induced W isotope shifts. The pre-exposure 182W/184W derived from the Pt–W isotope correlations of the IID, IVA and IVB iron meteorites are higher than most previous estimates and are more radiogenic than the initial 182W/184W of Ca–Al-rich inclusions (CAI). The Hf–W model ages for core formation range from +1.6±1.0 million years (Ma; for the IVA irons) to +2.7±1.3 Ma after CAI formation (for the IID irons), indicating that there was a time gap of at least ∼1 Ma between CAI formation and metal segregation in the parent bodies of some iron meteorites. From the Hf–W ages a time limit of <1.5–2 Ma after CAI formation can be inferred for the accretion of the IID, IVA and IVB iron meteorite parent bodies, consistent with earlier conclusions that the accretion of differentiated planetesimals predated that of most chondrite parent bodies.

The abundance and isotopic composition of Cd in iron meteorites

Cadmium is a highly volatile element and its abundance in meteorites may help better understand volatility-controlled processes in the solar nebula and on meteorite parent bodies. The large thermal neutron capture cross section of 113Cd suggests that Cd isotopes might be well suited to quantify neutron fluences in extraterrestrial materials. The aims of this study were (1) to evaluate the range and magnitude of Cd concentrations in magmatic iron meteorites, and (2) to assess the potential of Cd isotopes as a neutron dosimeter for iron meteorites. Our new Cd concentration data determined by isotope dilution demonstrate that Cd concentrations in iron meteorites are significantly lower than in some previous studies. In contrast to large systematic variations in the concentration of moderately volatile elements like Ga and Ge, there is neither systematic variation in Cd concentration amongst troilites, nor amongst metal phases of different iron meteorite groups. Instead, Cd is strongly depleted in all iron meteorite groups, implying that the parent bodies accreted well above the condensation temperature of Cd (i.e., ≈650 K) and thus incorporated only minimal amounts of highly volatile elements. No Cd isotope anomalies were found, whereas Pt and W isotope anomalies for the same iron meteorite samples indicate a significant fluence of epithermal and higher energetic neutrons. This observation demonstrates that owing to the high Fe concentrations in iron meteorites, neutron capture mainly occurs at epithermal and higher energies. The combined Cd-Pt-W isotope results from this study thus demonstrate that the relative magnitude of neutron capture-induced isotope anomalies is strongly affected by the chemical composition of the irradiated material. The resulting low fluence of thermal neutrons in iron meteorites and their very low Cd concentrations make Cd isotopes unsuitable as a neutron dosimeter for iron meteorites.