Les mesures fines des faibles radioactivités par la spectrométrie gamma nécessitent l’optimisation de la géométrie de détection et la connaissance du schéma de niveaux des raies gamma. Ainsi, on peut augmenter le taux de comptage et par conséquent, réduire l’incertitude statistique des pics spectraux exploités pour le calcul de l’activité des radio-isotopes en rapprochant le plus possible l’échantillon du détecteur. Cependant, l’augmentation du volume de l’échantillon demande une correction de l’auto-absorption des émissions par l’échantillon même, et le rapprochement du détecteur est à l’origine du phénomène de pic-somme. L’utilisation de MCNPX a permis de mettre en évidence les effets séparés de la densité de l’échantillon et le nombre atomique effectif dans l’atténuation des photons d’énergie inférieure à 100 keV. Les facteurs de correction du pic-somme sont obtenus par MCNPX, GESPCOR et ETNA. Ainsi, une base des données pour 244 radionucléides a été établie pour des géométries SG50 et SG500 au contact d’un détecteur. Dans une application à la radioprotection, des échantillons de matériaux de construction ont été analysés par la spectrométrie gamma. L’Uranium-238, le Thorium-232 et le Potassium-40 ont été identifiés et corrigés des effets sus-cités. La dosimétrie de leurs rayonnements gamma a permis d’évaluer les indices de risque, la dose absorbée et la dose efficace annuelle reçues provenant de ces matériaux. Les simulations par MCNPX corroborent le modèle de calcul de la dose absorbée. Il a permis aussi d'étudier la distribution de la dose dans les habitations de différentes dimensions. Les résultats obtenus sont en accord avec les limites règlementaires. / Precisely measuring weakly radioactive samples by gamma-ray spectrometry requires optimizing the detection geometry and knowledge of the gamma-ray decay scheme. One can thus increase the counting rate and reduce the statistical uncertainty of the spectral peaks used to determine radioisotope activities. However, an increased sample volume requires a correction for the self-absorption of y-rays in the sample itself, and approaching a sample to the detector gives rise to coincidence summing. MCNPX simulations permitted finding the separate influence of sample density and effective atomic number of the sample in the attenuation of photons with energies less than 100 keV. Peak-summing corrections were obtained with MCNPX, GESPCOR and ETNA. Thus a data base for 244 radionuclides could be established for SG50 and SG500 geometries in contact with a planar detector. In an application of the results to the health physics domain, construction materials were analyzed. Naturally-occurring Uranium-238, Thorium-232 and Potassium-40 activities were identified and corrected for the above-mentioned effects in order to evaluate the risk indexes, the absorbed dose and the annual effective dose received from different dimensions built of these materials. MCNPX simulations corroborated the model used to calculate the absorbed dose and gave its distribution in an enclosed space. The results obtained are within the recommended norms.

La dosimétrie en réacteur permet de déterminer la fluence neutronique reçue pendant une irradiation et d’en caractériser le spectre (distribution énergétique des neutrons). Cette technique s’appuie sur la mesure de l’activité de dosimètres irradiés, constitués de métaux purs ou d’alliages. La mesure d’activité de ces échantillons est réalisée par spectrométrie gamma et X sur des rayonnements de faibles énergies (< 100 keV) et s’appuie actuellement sur un dosimètre étalon adapté et validé spécifiquement pour les conditions de mesure. Le but de la thèse est de s’affranchir de cette étape et de pouvoir mesurer directement l’activité des dosimètres. L’étude a concerné spécifiquement les dosimètres en niobium et en rhodium qui sont utilisés pour caractériser la signature des neutrons d’énergie autour de 1 MeV. Ils sont respectivement activés en Nb-93m et 1Rh-103m. Ces deux radionucléides se désintègrent par une transition gamma en émettant principalement des photons XK d’énergie autour de 20 keV, sur lesquels s’appuie la mesure d’activité en spectrométrie. Or, du fait de leur faible énergie, ces rayonnements présentent de nombreuses difficultés pour être analysés avec précision. Les différents paramètres nécessaires à la quantification de l’activité des dosimètres, avec une incertitude relative de l’ordre de 2 %, ont été étudiés en détails. Les travaux ont d’abord porté sur l’étalonnage en rendement des détecteurs au germanium hyper-pur (GeHP) dans la gamme d’énergie comprise entre 11 keV et 150 keV. Ceci constitue une étape cruciale dans la détermination de l’activité et s’avère délicate dans la gamme d’énergie considérée. L’approche expérimentale, utilisant des sources ponctuelles étalons, a été couplée à des modélisations semi-empiriques et à des simulations des interactions rayonnements-matière par des méthodes Monte Carlo (PENELOPE et GEANT4). Ces dernières ont permis d’approfondir l’étude du phénomène de diffusion des photons en basse énergie, aux alentours de 20 keV, qui interfère avec les pics d’absorption totale dans les spectres et perturbe leur analyse. Dans un second temps, les simulations de Monte Carlo ont également été utilisées pour établir les facteurs de corrections nécessaires à la mesure des dosimètres : auto-absorption du rayonnement dans le matériau et changement de géométrie entre les conditions d’étalonnage (source ponctuelle) et les conditions de mesure (échantillon métallique massif). Le phénomène de fluorescence lié à la présence d’impuretés (dans le matériau du dosimètre ou créées lors de l’irradiation en réacteur) a été étudié et les facteurs de corrections à appliquer pour en tenir compte ont été établis. Les données du schéma de désintégration, en particulier les intensités d'émission des rayons X, sont les principales composantes de l'incertitude sur la valeur d'activité des dosimètres. Les intensités d'émission X font rarement l'objet de mesures expérimentales, le plus souvent, leurs valeurs découlent du schéma de désintégration et des données fondamentales nucléaires et atomiques de l'élément tels les coefficients de conversion interne et le rendement de fluorescence. Plusieurs expériences ont été menées pour fournir de nouvelles données expérimentales. Les coefficients d’atténuation massique et les rendements de fluorescence K du niobium et du rhodium ont été déterminés en utilisant un rayonnement photonique monochromatique sur le synchrotron SOLEIL. Les intensités d’émission du Rh-103m ont été mesurées suivant deux approches, l’une à partir de rhodium activé au réacteur ISIS et l’autre à partir d’une solution de palladium-103. Toutes ces nouvelles valeurs sont comparées aux données publiées et le schéma de désintégration du Rh-103m est discuté. / Reactor dosimetry is used to determine the neutron fluence during an irradiation and to characterize its spectrum (neutron energy distribution). This technique is based on the analysis of the activity of irradiated dosimeters, made of pure metals or alloys. The activity measurement of these samples is performed by gamma and/or X-ray spectrometry and is currently based on specific standard dosimeters, validated for the measurement conditions. The goal of the thesis is to avoid this calibration step and to be able to directly measure the activity of the sample. The study focused specifically on niobium and rhodium dosimeters which are used to characterize neutrons in the energy range around 1 MeV. Their activation produces 93mNb and 103mRh, respectively. These two radionuclides decay through an isomeric gamma transition, emitting mainly K X-rays with energies around 20 keV, on which the spectrometric activity measurement is based. However, owing to their low energy, these X-rays are particularly difficult to measure accurately. The various parameters required to determine the activity of the dosimeters, with a relative standard uncertainty of around 2%, were studied in detail. The work initially focused on the calibration of hyper-pure germanium (HPGe) detectors in the energy range between 11 keV and 150 keV. This is a crucial step in determining the activity of a radionuclide sample and is difficult to achieve in the energy range of interest. The experimental approach, using standard point sources, was coupled with semi-empirical modelling and simulations of radiation-matter interactions by Monte Carlo methods (PENELOPE and GEANT4). These methods have made it possible to study in detail the photons scattering at low energy, around 20 keV, which interferes with the full-energy peaks in the spectra and disturbs their analysis. In a second step, Monte Carlo simulations were used to calculate the correction factors needed to derive the dosimeter activity: self-absorption of photons in the dosimeter material and the geometry change between the calibration conditions (point source) and the measurement conditions (solid metal sample). The fluorescence induced by impurities (in the dosimeter material or created during irradiation in the reactor) was studied and the correction factors to be applied were established. Radioactive decay data, particularly photon emission intensities, are the main components of the uncertainty in dosimeter activity results. X-ray emission intensities are rarely measured experimentally and most often their values are calculated from fundamental parameters i.e. internal conversion coefficients and fluorescence yields, and a balanced decay scheme, of the nuclide. Several experiments were designed to provide new experimental data. The mass attenuation coefficients and K fluorescence yields of niobium and rhodium were determined using a monochromatic photon beam at the SOLEIL synchrotron facility. The photon emission intensities of 103mRh were measured using two approaches, one from rhodium activated at the ISIS reactor and the other from a solution of palladium 103. All these new values are compared with previously published data and the decay scheme of 103mRh is discussed.

For about 20 years now, observations of 6Li in several old metal-poor stars inside the halo of our galaxy have been reported, which are largely independent of the stars’ metallicity, and which point to a possible primordial origin. The observations exceed the predictions of the Standard Big-Bang Nucleosynthesis model by a factor of 500. In the relevant energy range, no directly measured S-factors were available yet for the main production reaction 2H(α,γ)6Li, while different theoretical estimations have an uncertainty of up to two orders of magnitude. The very small cross section in the picobarn range has been measured with a deuterium gas target at the LUNA acceler- ator (Laboratory for Underground Nuclear Astrophysics), located deep underground inside Laboratori Nazionali del Gran Sasso in Italy. A beam-induced, neutron-caused background in the γ-detector occurred which had to be analyzed carefully and sub- tracted in an appropriate way, to finally infer the weak signal of the reaction. For this purpose, a method to parameterize the Compton background has been developed. The results are a contribution to the discussion about the accuracy of the recent 6Li observations, and to the question if it is necessary to include new physics into the Standard Big-Bang Nucleosynthesis model.

Within cosmology, there are two entirely independent pillars which can jointly drive this field towards precision: Astronomical observations of primordial element abundances and the detailed surveying of the cosmic microwave background. However, the comparatively large uncertainty stemming from the nuclear physics input is currently still hindering this effort, i.e. stemming from the 2H(p,γ)3He reaction. An accurate understanding of this reaction is required for precision data on primordial nucleosynthesis and an independent determination of the cosmological baryon density. Elsewhere, our Sun is an exceptional object to study stellar physics in general. While we are now able to measure solar neutrinos live on earth, there is a lack of knowledge regarding theoretical predictions of solar neutrino fluxes due to the limited precision (again) stemming from nuclear reactions, i.e. from the 3He(α,γ)7Be reaction. This thesis sheds light on these two nuclear reactions, which both limit our understanding of the universe. While the investigation of the 2H(p,γ)3He reaction will focus on the determination of its crosssection in the vicinity of the Gamow window for the Big Bang nucleosynthesis, the main aim for the 3He(α,γ)7Be reaction will be a measurement of its γ-ray angular distribution at astrophysically relevant energies. In addition, the installation of an ultra-low background counting setup will be reported which further enables the investigation of the physics of rare events. This is essential for modern nuclear astrophysics, but also relevant for double beta decay physics and the search for dark matter. The presented setup is now the most sensitive in Germany and among the most sensitive ones worldwide. / Innerhalb der Kosmologie gibt es zwei völlig unabhängige Ansätze, die gemeinsam die Präzision in diesem Gebiet weiter vorantreiben können: Astronomische Beobachtungen der primordialen Elementhäufigkeiten und die detaillierte Vermessung des kosmischen Mikrowellenhintergrunds. Dieses Vorhaben wird derzeit allerdings noch durch die vergleichsweise große Unsicherheit des kernphysikalischen Inputs verhindert, vor allem bedingt durch das limitierte Verständnis der 2H(p,γ)3He-Reaktion. Eine präzise Vermessung dieser Reaktion ist sowohl für die Präzisionsdaten zur primordialen Nukleosynthese erforderlich, als auch für die damit einhergehende unabhängige Bestimmung der kosmologischen Baryonendichte. Des Weiteren ist unsere Sonne ein exzellent geeignetes Objekt, um unser theoretisches Verständnis über die Physik von Sternen mit experimentellen Messungen abgleichen zu können. Während wir heutzutage in der Lage sind, solare Neutrinos in Echtzeit auf der Erde messen können, mangelt es noch an der theoretischen Vorhersagekraft von solaren Neutrinoflüssen. Auch hier ist die Präzision (erneut) begrenzt durch das limitierte Verständnis der beteiligten Kernreaktionen, vor allem bedingt durch mangelnde Kenntnis über die 3He(α,γ)7Be-Reaktion. Die vorliegende Arbeit beleuchtet diese zwei Kernreaktionen, die beide unser Verständnis des Universums auf verschiedene Weise einschränken. Während sich die Untersuchung der 2H(p,γ)3He-Reaktion auf die Bestimmung ihres Wirkungsquerschnitts in der Nähe des Gamow-Fensters für die Urknall-Nukleosynthese konzentriert, ist das Hauptanliegen für die 3He(α,γ)7Be-Reaktion eine Messung der Winkelverteilung der dabei emittierten γ-Strahlung bei astrophysikalisch relevanten Energien. Darüber hinaus wird über die Installation eines Messaufbaus zur Untersuchung niedriger Aktivitäten berichtet, das sich durch seine äußerst geringe Untergrundzählrate auszeichnet. Bedingt durch seine hohe Sensitivität kann dieser Aufbau in Zukunft bedeutende Beiträge für die moderne nukleare Astrophysik leisten und ist darüber hinaus beispielsweise auch relevant für die Untersuchung von Doppel-Betazerfällen oder die Suche nach dunkler Materie. Der präsentierte Aufbau ist nun der Sensitivste seiner Art in Deutschland und gehört zu den Sensitivsten weltweit.

CAPES / O cimento Portland é bastante empregado na construção civil e apresenta em sua composição o gesso natural. Para minimizar custos é possível substituir parte do gesso desta composição pelo fosfogesso. O fosfogesso é um resíduo gerado a partir da produção dos fertilizantes e é constituído, essencialmente, por cálcio dihidratado e algumas impurezas, como fluoretos, metais em geral e radionuclídeos. Atualmente, toneladas de fosfogesso são armazenadas à céu aberto próximo das indústrias de fertilizantes, causando a contaminação do meio ambiente. O elemento 226Ra, presente nesses materiais, ao passar pela série de decaimento radioativo, transforma-se em gás 222Rn. Esse gás, ao ser inalado pode decair dentro dos pulmões e neste caso, os seus produtos depositam-se nas paredes pulmonares ocasionando exposição à radiação, podendo ser um potencial causador de câncer pulmonar. Dessa forma, o objetivo desta pesquisa foi medir os níveis de concentração de 222Rn em corpos de prova de argamassa de cimento Portland, de gesso e de fosfogesso provenientes do Estado do Paraná, além de caracterizar o material e estimar a concentração de radônio em um ambiente de convívio humano hipotético construído com paredes destes materiais. Para as medidas de atividade do 222Rn foi utilizado o monitor AlphaGUARD (Saphymo GmbH). A análise qualitativa e quantitativa foi realizada por meio da espectrometria gama e da EDXRF com tubos de alvos de Au e Ag (AMPTEK), e com alvo de Mo (ARTAX) e os ensaios mecânicos com equipamento de raios X (Gilardoni) e com a prensa mecânica (EMIC). Os valores médios da atividade do radônio no ar obtidos pelo estudo dos materiais armazenados no recipiente foram de 854 ± 23 Bq/m3, 60,0 ± 7,2 Bq/m3 e 52,9 ± 5,4 Bq/m3 para argamassas de cimento Portland, de gesso e de fosfogesso, respectivamente. Estes resultados extrapolados para o ambiente hipotético de 36 m3 com paredes revestidas com os materiais foram de 3366 ± 91 Bq/m3, 237 ± 28 Bq/m3 e 208 ± 21 Bq/m3 para argamassas de cimento Portland, gesso e fosfogesso. Considerando o limite de 300 Bq/m3 estabelecido pela ICRP, observa-se que, para o revestimento de cimento Portland a exposição não é segura e requer alguns procedimentos de mitigação específicos. A partir da espectrometria gama foi calculado o valor do rádio equivalente (Raeq) para as argamassas de cimento Portland, gesso e fosfogesso que resultou em 78,2 ± 0,9 Bq/kg; 58,2 ± 0,9 Bq/kg e 68,2 ± 0,9 Bq/kg, respectivamente. Os valores do Raeq das amostras encontram-se inferiores ao limite máximo de 370 Bq/kg. Em relação a análise qualitativa e quantitativa das amostras por EDXRF, os resultados permitiram identificar e quantificar os elementos que compõe as amostras como o Ca, S, Fe, entre outros. / Portland cement being very common construction material has in its composition the natural gypsum. To decrease the costs of manufacturing, the cement industry is substituting the gypsum in its composition by small quantities of phosphogypsum, which is the residue generated by the production of fertilizers and consists essentially of calcium dihydrate and some impurities, such as fluoride, metals in general, and radionuclides. Currently, tons of phosphogypsum are stored in the open air near the fertilizer industries, causing contamination of the environment. The 226 Ra present in these materials, when undergoes radioactive decay, produces the 222Rn gas. This radioactive gas, when inhaled together with its decay products deposited in the lungs, produces the exposure to radiation and can be a potential cause of lung cancer. Thus, the objective of this study was to measure the concentration levels of 222Rn from cylindrical samples of Portland cement, gypsum and phosphogypsum mortar from the state of Paraná, as well as characterizer the material and estimate the radon concentration in an environment of hypothetical dwelling with walls covered by such materials. Experimental setup of 222Rn activity measurements was based on AlphaGUARD detector (Saphymo GmbH). The qualitative and quantitative analysis was performed by gamma spectrometry and EDXRF with Au and Ag targets tubes (AMPTEK), and Mo target (ARTAX) and mechanical testing with x- ray equipment (Gilardoni) and the mechanical press (EMIC). Obtained average values of radon activity from studied materials in the air of containers were of 854 ± 23 Bq/m3, 60,0 ± 7,2 Bq/m3 e 52,9 ± 5,4 Bq/m3 for Portland cement, gypsum and phosphogypsum mortar, respectively. These results extrapolated into the volume of hypothetical dwelling of 36 m3 with the walls covered by such materials were of 3366 ± 91 Bq/m3, 237 ± 28 Bq/m3 e 208 ± 21 Bq/m3for Portland cement, gypsum and phosphogypsum mortar, respectively. Considering the limit of 300 Bq/m3 established by the ICRP, it could be concluded that the use of Portland cement plaster in dwellings is not secure and requires some specific mitigation procedure. Using the results of gamma spectrometry there were calculated the values of radium equivalent activity concentrations (Raeq) for Portland cement, gypsum and phosphogypsum mortar, which were obtained equal to 78,2 ± 0,9 Bq/kg; 58,2 ± 0,9 Bq/kg e 68,2 ± 0,9 Bq/kg, respectively. All values of radium equivalent activity concentrations for studied samples are below the maximum level of 370 Bq/kg. The qualitative and quantitative analysis of EDXRF spectra obtained with studied mortar samples allowed to evaluate quantitate and the elements that constitute the material such as Ca, S, Fe, and others.

CAPES / O cimento Portland é bastante empregado na construção civil e apresenta em sua composição o gesso natural. Para minimizar custos é possível substituir parte do gesso desta composição pelo fosfogesso. O fosfogesso é um resíduo gerado a partir da produção dos fertilizantes e é constituído, essencialmente, por cálcio dihidratado e algumas impurezas, como fluoretos, metais em geral e radionuclídeos. Atualmente, toneladas de fosfogesso são armazenadas à céu aberto próximo das indústrias de fertilizantes, causando a contaminação do meio ambiente. O elemento 226Ra, presente nesses materiais, ao passar pela série de decaimento radioativo, transforma-se em gás 222Rn. Esse gás, ao ser inalado pode decair dentro dos pulmões e neste caso, os seus produtos depositam-se nas paredes pulmonares ocasionando exposição à radiação, podendo ser um potencial causador de câncer pulmonar. Dessa forma, o objetivo desta pesquisa foi medir os níveis de concentração de 222Rn em corpos de prova de argamassa de cimento Portland, de gesso e de fosfogesso provenientes do Estado do Paraná, além de caracterizar o material e estimar a concentração de radônio em um ambiente de convívio humano hipotético construído com paredes destes materiais. Para as medidas de atividade do 222Rn foi utilizado o monitor AlphaGUARD (Saphymo GmbH). A análise qualitativa e quantitativa foi realizada por meio da espectrometria gama e da EDXRF com tubos de alvos de Au e Ag (AMPTEK), e com alvo de Mo (ARTAX) e os ensaios mecânicos com equipamento de raios X (Gilardoni) e com a prensa mecânica (EMIC). Os valores médios da atividade do radônio no ar obtidos pelo estudo dos materiais armazenados no recipiente foram de 854 ± 23 Bq/m3, 60,0 ± 7,2 Bq/m3 e 52,9 ± 5,4 Bq/m3 para argamassas de cimento Portland, de gesso e de fosfogesso, respectivamente. Estes resultados extrapolados para o ambiente hipotético de 36 m3 com paredes revestidas com os materiais foram de 3366 ± 91 Bq/m3, 237 ± 28 Bq/m3 e 208 ± 21 Bq/m3 para argamassas de cimento Portland, gesso e fosfogesso. Considerando o limite de 300 Bq/m3 estabelecido pela ICRP, observa-se que, para o revestimento de cimento Portland a exposição não é segura e requer alguns procedimentos de mitigação específicos. A partir da espectrometria gama foi calculado o valor do rádio equivalente (Raeq) para as argamassas de cimento Portland, gesso e fosfogesso que resultou em 78,2 ± 0,9 Bq/kg; 58,2 ± 0,9 Bq/kg e 68,2 ± 0,9 Bq/kg, respectivamente. Os valores do Raeq das amostras encontram-se inferiores ao limite máximo de 370 Bq/kg. Em relação a análise qualitativa e quantitativa das amostras por EDXRF, os resultados permitiram identificar e quantificar os elementos que compõe as amostras como o Ca, S, Fe, entre outros. / Portland cement being very common construction material has in its composition the natural gypsum. To decrease the costs of manufacturing, the cement industry is substituting the gypsum in its composition by small quantities of phosphogypsum, which is the residue generated by the production of fertilizers and consists essentially of calcium dihydrate and some impurities, such as fluoride, metals in general, and radionuclides. Currently, tons of phosphogypsum are stored in the open air near the fertilizer industries, causing contamination of the environment. The 226 Ra present in these materials, when undergoes radioactive decay, produces the 222Rn gas. This radioactive gas, when inhaled together with its decay products deposited in the lungs, produces the exposure to radiation and can be a potential cause of lung cancer. Thus, the objective of this study was to measure the concentration levels of 222Rn from cylindrical samples of Portland cement, gypsum and phosphogypsum mortar from the state of Paraná, as well as characterizer the material and estimate the radon concentration in an environment of hypothetical dwelling with walls covered by such materials. Experimental setup of 222Rn activity measurements was based on AlphaGUARD detector (Saphymo GmbH). The qualitative and quantitative analysis was performed by gamma spectrometry and EDXRF with Au and Ag targets tubes (AMPTEK), and Mo target (ARTAX) and mechanical testing with x- ray equipment (Gilardoni) and the mechanical press (EMIC). Obtained average values of radon activity from studied materials in the air of containers were of 854 ± 23 Bq/m3, 60,0 ± 7,2 Bq/m3 e 52,9 ± 5,4 Bq/m3 for Portland cement, gypsum and phosphogypsum mortar, respectively. These results extrapolated into the volume of hypothetical dwelling of 36 m3 with the walls covered by such materials were of 3366 ± 91 Bq/m3, 237 ± 28 Bq/m3 e 208 ± 21 Bq/m3for Portland cement, gypsum and phosphogypsum mortar, respectively. Considering the limit of 300 Bq/m3 established by the ICRP, it could be concluded that the use of Portland cement plaster in dwellings is not secure and requires some specific mitigation procedure. Using the results of gamma spectrometry there were calculated the values of radium equivalent activity concentrations (Raeq) for Portland cement, gypsum and phosphogypsum mortar, which were obtained equal to 78,2 ± 0,9 Bq/kg; 58,2 ± 0,9 Bq/kg e 68,2 ± 0,9 Bq/kg, respectively. All values of radium equivalent activity concentrations for studied samples are below the maximum level of 370 Bq/kg. The qualitative and quantitative analysis of EDXRF spectra obtained with studied mortar samples allowed to evaluate quantitate and the elements that constitute the material such as Ca, S, Fe, and others.

This master’s thesis provides a comprehensive overview of the conventional neutron sources from the perspective of reactions which lead to the production of neutrons, advantages, disadvantages, properties and their possible utilization. In the relation to the assembly of the laboratory neutron source and the unique experimental stand “Candle” basic methods of the neutron field analysis are outlined and two of them, the neutron activation analysis and the calculation using the MCNP software code are discussed in depth to apply and compare these methods. The experimental part deals with the realization of neutron activation analysis from its design itself, through gamma spectrometry to the cadmium ratio calculation. In compliance with the measurements, a calculation with MCNP code was run and both methods were evaluated and compared. The computation is complemented with the analysis of radiation situation on the borders of the supervised area, which is compared to the legal limit.