The purpose of this thesis is to assemble an HPGe detector intended to be used in a mass experiment during the autumn of 2018. After assembly, the detector will be characterized and a shielding, consisting of approximately two tons of lead, will be assembled around the detector. Different modules will be tested to find the optimal energy resolution possible for the planned measurements. To characterize the detector several measurements will be taken at different measurement geometries. Measurements of the background radiations will be performed before and after the assembly of the lead shielding such that a comparison of the shielding's effect on measurements can be made. These measurements will also be analyzed in an attempt to identify the different radionuclides contributing to the background radiation. The result was a reliable set-up with a good energy resolution. However, more tests are required to gain a greater understanding of the inner structure of the detector.

A técnica de análise por ativação com nêutrons instrumental tem sido amplamente utilizada pelo Laboratório de Ativação Neutrônica (LAN) do IPEN, com emprego do método comparativo, utilizando-se como fonte de nêutrons o reator de pesquisa do tipo piscina IEA-R1, do Instituto de Pesquisas Energéticas e Nucleares (IPEN). Neste método uma amostra é irradiada, simultaneamente, com um padrão do elemento a ser determinado. Para contornar a dificuldade de uma análise multielementar, por ser necessário preparar vários padrões, foi desenvolvido o método k0 de ativação neutrônica. No método k0 a concentração dos elementos de interesse da amostra é calculada em relação a um elemento comparador, geralmente o ouro. Todavia, esse método requer, com precisão, a eficiência de detecção no intervalo de energia de interesse e na geometria do arranjo experimental. Para contornar o tratamento manual dos dados em planilhas eletrônicas, passíveis de incidência de erros, foi desenvolvido, então, um software web, com acesso de qualquer dispositivo com Internet, livre, para calibração da eficiência absoluta de detectores do tipo HPGe. Utilizou-se a linguagem de programação Python, livre, de baixa curva de aprendizagem e padronizada no projeto eScience, a qual o referido software faz parte, e o framework web Django. No sistema é possível realizar todos os cadastros das informações utilizadas no cálculo da eficiência. Além de calcular a eficiência, o sistema plota o gráfico com os pontos da eficiência, linha de regressão, com possibilidade de ajustes, e barra de erro representando as incertezas. Como parte integrante do projeto e-science, o software emite relatórios referentes aos dados dos espectros e da eficiência, permitindo seu compartilhamento. / The technique of instrumental neutron activation analysis has been widely used by IPEN\'s Neutron Activation Laboratory (LAN), using the comparative method, using the IEA-R1 pool-type research reactor as the neutron source Energy and Nuclear Research (IPEN). In this method a sample is simultaneously irradiated with a pattern of the element to be determined. In order to overcome the difficulty of a multielementary analysis, because it isnecessary to prepare several standards, the k0 method of neutron activation was developed. In method k0 the concentration of the elements of interest of the sample is calculated in relation to a comparator element, generally gold. However, this method accurately requires the detection efficiency in the energy range of interest and the geometry of the experimental arrangement. In order to circumvent the manual processing of the data in electronic spreadsheets, which could lead to errors, a web software was developed with access from any free Internet device for calibration of the absolute efficiency of HPGe type detectors. It was used the free and low learning curve, Python programming language, standardized in the eScience project, to which the software is part, and the Django web framework. In the softwareit is possible to carry out all the registers of the information used in the calculation of the efficiency. In addition to calculating efficiency, the software plots the graph with the efficiency points, regression line, with possibility of adjustments, and error bar representing the uncertainties. As part of the e-science project, the software issues reports on spectra and efficiency data, allowing it to share.

Gamma-ray spectrometry measurements performed on site, or “in situ”, is a widely used and powerful method that can be employed both to identify and quantify ground deposited radionuclides. The purpose of this thesis is to improve the calibration of high purity germanium (HPGe) detectors for in situ measurements, and calculate the combined uncertainty and potential systematic effects. An improved semi-empirical calibration method is presented, based on a novel expression for the intrinsic detector efficiency that includes both the energy and angular response of the detector. A three-layer model for the description of the depth distribution of the radionuclide and the soil density is proposed. The combined uncertainty of intrinsic detector efficiency calibrations and in situ measurements according to the proposed method was estimated. The uncertainty in the intrinsic detector efficiency was found to be 5.1 and 8.1% (coverage factor k=1, i.e. for a confidence interval of about 68%), for the two detectors calibrated. These numbers were, however, at a later stage reduced to 3.7 and 4.2%, using a revised expression for the intrinsic detector efficiency. For in situ measurements, the combined standard uncertainty was found to be 15-20% (k=1), based on the original expression for the intrinsic detector efficiency. Monte Carlo models of the two detectors were created and Monte Carlo calculated values for intrinsic detector efficiency were compared with experimental data. As a discrepancy was found, a thorough investigation of the detector response was performed. Scanning of the detector surface with a collimated 59.5 keV photon beam revealed the detector response to be highly irregular over the detector surface. It was concluded that the efficiency deficit of the detector could most likely be attributed to an increase in dead layer thickness compared with manufacturer supplied data. The thickness of the dead layer was estimated to be 1.5-1.9 mm, whereas the nominal value was 0.7 mm. Radiographs of the detectors were produced that provided valuable information about the physical dimensions of the germanium crystal, as well as its actual location within the detector housing. The Monte Carlo models were employed to calculate in situ measurement efficiencies for measurements of 137Cs deposition from the Chernobyl fallout. Results from the Monte Carlo simulations were compared both with the semi-empirical method and with soil sample data, and satisfactory agreement was confirmed. It was then proceeded to employ the Monte Carlo model to calculate the effect on in situ measurement results by two influencing parameters: ground curvature and activity in trees. Neither of these parameters was found to influence the result by more than about 25%. This deviation is comparable with the measurement uncertainty, and should not deter from measurements in such terrain.

Escape of photoelectrons, Compton-scattered photons and Ge X-rays from a HPGe detector was studied as a function of energy in the range 8-52 keV. A variable-energy source producing Cu, Rb, Mo, Ag, Ba, and Tb X-rays was used. All three mechanisms for energy loss were observed in the same experiment for Ba and Tb, while only X-ray and photoelectron escapes were evident in the spectra for Ag, Mo, Rb, and Cu. Spectral features and possible mechanisms for partial energy deposition were investigated. A Monte Carlo program was used to simulate the relevant interactions and to estimate the escape probabilities.

Components of the response function of a high-purity germanium (HPGe) detector due to full or partial energy deposition by gamma- and X-rays were studied. Experimental response functions for 241Am, Ba and Tb were compared with those obtained from the Monte Carlo simulations. The role of physical mechanisms for each component was investigated by considering escape/absorption of photons, photoelectrons, Auger electrons, recoil electrons and X-rays of the detector material. A detailed comparison of the experimental Compton, photoelectron, detector X-ray escape components and full-energy peaks with those obtained from Monte Carlo program are presented.

In a collaboration with limnologists at Uppsala University a planar HPGe detector has been used to find 210Pb in lake bottom sediment in hopes of getting an estimation for the sedimentation rate. Using a least squares fit to the data, the sedimentation rate was calculated to 0.08 ± 0.01 cm/year with background subtraction, and with it a timescale for the age of the sediment could be implemented. With this timescale the lake bottom sediment can be dated as far back as a century. Along with this, using 137Cs traces from the Chernobyl disaster of 1986 a consistency check can be made for our timescale. It is estimated that the Chernobyl disaster occurred at 1989 ± 7 years which is consistent with reality since 1986 is included in the interval 1982-1989. This helps us validate the determined sedimentation rates.

The nuclear design of fusion devices such as ITER (International Thermonuclear Experimental Reactor), which is an experimental fusion reactor based on the "tokamak" concept, rely on the results of neutron physical calculations. These depend on the knowledge of the neutron and photon flux spectra which is particularly important because it permits to anticipate the possible answers of the whole structure to phenomena such as nuclear heating, tritium breeding, atomic displacements, radiation shielding, power generation and material activation. The flux spectra can be calculated with transport codes, but validating measurements are also required. An important constituent of structural materials and divertor areas of fusion reactors is tungsten. This thesis deals with the measurement of the neutron fluence and neutron energy spectrum in a tungsten assembly by means of multiple foil neutron activation technique. In order to check and qualify the experimental tools and the codes to be used in the tungsten benchmark experiment, test measurements in the D-T and D-D neutron fields of the neutron generator at Technische Universität Dresden were performed. The characteristics of the D-D and D-T reactions, used to produce monoenergetic neutrons, together with the selection of activation reactions suitable for fusion applications and details of the activation measurements are presented. Corrections related to the neutron irradiation process and those to the sample counting process are discussed, too. The neutron fluence and its energy distribution in a tungsten benchmark, irradiated at the Frascati Neutron Generator with 14 MeV neutrons produced by the T(d, n)4He reaction, are then derived from the measurements of the neutron induced γ-ray activity in the foils using the STAYNL unfolding code, based on the linear least-square-errors method, together with the IRDF-90.2 (International Reactor Dosimetry File) cross section library. The differences between the neutron flux spectra measured by means of neutron foil activation and the neutron flux spectra obtained in the same assembly, making use of an NE213 liquid-scintillation spectrometer were studied. The comparison of measured neutron spectra with the spectra calculated with the MCNP-4B (Monte Carlo neutron and photon transport) code, which allows a crucial test of the evaluated nuclear data used in fusion reactor design, is discussed, too. In conclusion, this thesis shows the applicability of the neutron foil activation technique for the measurement of neutron flux spectra inside a thick tungsten assembly irradiated with 14 MeV from a D-T generator. / Die Konstruktion von Fusionsreaktoren wie ITER (International Thermonuclear Experimental Reactor), der ein experimenteller Fusionsreaktor ist und auf dem "Tokamak"-Konzept beruht, basiert unter neutronenphysikalischen Gesichtspunkten auf den Ergebnissen von umfangreichen Simulationsrechnungen. Diese setzen die Kenntnis der Spektren des Neutronen- und Photonenflusses voraus die besonders wichtig ist, weil sie, die möglichen Antworten der ganzen Struktur auf physikalische Prozesse vorauszuberechnen erlaubt wie z.B.: Heizen durch nukleare Prozesse, Tritium-Brüten, Atomverschiebung, Abschirmung von Strahlung, Leistungserzeugung und Materialaktivierung. Die Flußspektren können mittels Transportcodes berechnet werden, aber es werden auch Messungen zu ihrer Bestätigung benötigt. Ein wichtiger Bestandteil des Strukturmaterials und der Divertor-Flächen der Fusionsreaktoren ist Wolfram. Diese Dissertation behandelt die Messungen der Neutronspektren und ?fluenz in einer Wolfram-Anordnung mittels der Multifolien-Neutronenaktivierungstechnik. Um die anzuwendenden experimentellen Geräte und die Codes, die im Wolfram-Benchmark-Experiment eingesetzt werden, zu überprüfen und zu bestimmen, wurden Testmessungen in den D-T und D-D Neutronenfeldern des Neutronengenerator der Technischen Universität Dresden durchgeführt. Die Eigenschaften der D-T und D-D Reaktionen, die für die Erzeugung von monoenergetischen Neutronen verwendet werden, sowie die Auswahl der Aktivierungsreaktionen, die für Fusionsanwendungen geeignet sind und die Aktivierungsmessung werden detailliert vorgestellt. Korrekturen, die sich auf den Neutronen-Bestrahlungsprozess und auf den Probenzählungsprozess beziehen, werden ebenfalls besprochen. Die Neutronenfluenz und ihre Energieverteilung in einem Wolfram-Benchmark, bestrahlt am Frascati Neutronen Generator mit 14 MeV-Neutronen aus der T(d, n)4He Reaktion, werden aus den Messungen der γ-Strahlenaktivität, die von Neutronen in den Folien induziert ist, durch den STAYNL Entfaltungscode, der auf der Methode der kleinsten Fehlerquadrate basiert, zusammen mit der IRDF-90.2 Wirkungsquerschnitt-Bibliothek abgeleitet. Die Unterschiede zwischen den Neutronenflußspektren, die mit Hilfe der Multifolien-Neutronenaktivierung ermittelt wurden, und den Neutronenflußspektren, gemessen im selben Aufbau mit einem NE-213 Flüssigszintillator, wurden untersucht. Die gemessenen Neutronenspektren werden den aus MCNP-4B Rechnungen (Monte Carlo neutron and photon transport) ermittelten Spektren gegenüber gestellt. Der Vergleich stellt einen wichtigen Test der evaluierten Kerndaten für Fusionsreaktorkonzepte dar. Zusammenfassend zeigt diese Arbeit die Anwendbarkeit der Multifolien-Neutronenaktivierungstechnik bei Messungen der Neutronenflussspektren innerhalb eines massiven Wolframblocks bei Bestrahlung mit schnellen Neutronen aus D-T Generatoren.

<p>У докторској дисертацији&nbsp; приказани су резултати развијених и примењених коинцидентних метода за временску анализу нуклеарних процеса. Експериментални коинцидентни системи засновани су на&nbsp; HPGe&nbsp; и пластичним сцинтилационим детекторима.&nbsp; Извршена су три експеримента, која су показала примењивост развијених коинцидентних система. Први део експерименталног дела обухвата анализе временских варијација интензитета космичког зрачења посредством нискоенергијских фотона. Показано је да се праћењем интензитета нискоенергијских фотона у току времена у различитим енергијским регионима остварује бољи увид у анализу фонских догађаја, стварајући предуслове за извођење експеримената који трагају за ретким нуклеарним процесима. Поред праћења временских варијација интензитета, метода се може применити и&nbsp; на детекцију периодичних и апериодичних догађаја повезаних са активношћу Сунца. Други део дисертације обухватао је истраживања везана&nbsp; за&nbsp; детекцију потенцијалних&nbsp; флуктуација константе распада 22 Na. Развијен је коинцидентни систем&nbsp; и&nbsp; у току времена је&nbsp; праћен интензитет анихилационе линије, која је резултат анихилације позитрона емитованог распадом 22Na.&nbsp; За време трајања&nbsp; аквизиције података, нису пронађена значајна одступања испитиване константе распада од стандардног експоненцијалног закона радиоактивног распада. У трећем делу експерименталног рада, приказана је коинцидентна метода за временско раздвајање догађаја индукованих мионима и неутронима у околини детекторског система. Добијена је временска крива у експерименту и извршена је детаљна анализа различитих временских региона. Извршене су Монте Карло симулације, на основу којих је добијена временска крива. Анализом различитих региона симулиране временске криве, показано је да се ови догађаји могу раздвојити у две велике групе&ndash;брзе и споре догађаје. Међу спорим догађајима, показано је да се може направити разлика између догађаја индукованих мионима, међу којима доминира анихилација, и догађаја индукованих неутронима, који спадају у закаснеле догађаје у групи спорих догађаја. Добијено је да неутрони највише доприносе нискоенергијском региону, првенствено у региону до&nbsp; &asymp;50&nbsp; keV,&nbsp; што их чини&nbsp; нежељеном кариком фонских догађаја у експериментима који трагају за ретким нуклеарним догађајима. На основу резултата симулација, анализирани су електромагнетни и хадронски процеси индуковани мионима и неутронима, као и удели мионске и неутронске компоненте у коинцидентном спектру HPGe&nbsp; детектора и директном спектру пластичног сцинтилационог детектора. Закључено је да нискоенергијском спектру,&nbsp; који је превасходно значајан за ретке нуклеарне процесе,&nbsp; доминантно доприносе неутрони.</p> / <p>U doktorskoj disertaciji&nbsp; prikazani su rezultati razvijenih i primenjenih koincidentnih metoda za vremensku analizu nuklearnih procesa. Eksperimentalni koincidentni sistemi zasnovani su na&nbsp; HPGe&nbsp; i plastičnim scintilacionim detektorima.&nbsp; Izvršena su tri eksperimenta, koja su pokazala primenjivost razvijenih koincidentnih sistema. Prvi deo eksperimentalnog dela obuhvata analize vremenskih varijacija intenziteta kosmičkog zračenja posredstvom niskoenergijskih fotona. Pokazano je da se praćenjem intenziteta niskoenergijskih fotona u toku vremena u različitim energijskim regionima ostvaruje bolji uvid u analizu fonskih događaja, stvarajući preduslove za izvođenje eksperimenata koji tragaju za retkim nuklearnim procesima. Pored praćenja vremenskih varijacija intenziteta, metoda se može primeniti i&nbsp; na detekciju periodičnih i aperiodičnih događaja povezanih sa aktivnošću Sunca. Drugi deo disertacije obuhvatao je istraživanja vezana&nbsp; za&nbsp; detekciju potencijalnih&nbsp; fluktuacija konstante raspada 22 Na. Razvijen je koincidentni sistem&nbsp; i&nbsp; u toku vremena je&nbsp; praćen intenzitet anihilacione linije, koja je rezultat anihilacije pozitrona emitovanog raspadom 22Na.&nbsp; Za vreme trajanja&nbsp; akvizicije podataka, nisu pronađena značajna odstupanja ispitivane konstante raspada od standardnog eksponencijalnog zakona radioaktivnog raspada. U trećem delu eksperimentalnog rada, prikazana je koincidentna metoda za vremensko razdvajanje događaja indukovanih mionima i neutronima u okolini detektorskog sistema. Dobijena je vremenska kriva u eksperimentu i izvršena je detaljna analiza različitih vremenskih regiona. Izvršene su Monte Karlo simulacije, na osnovu kojih je dobijena vremenska kriva. Analizom različitih regiona simulirane vremenske krive, pokazano je da se ovi događaji mogu razdvojiti u dve velike grupe&ndash;brze i spore događaje. Među sporim događajima, pokazano je da se može napraviti razlika između događaja indukovanih mionima, među kojima dominira anihilacija, i događaja indukovanih neutronima, koji spadaju u zakasnele događaje u grupi sporih događaja. Dobijeno je da neutroni najviše doprinose niskoenergijskom regionu, prvenstveno u regionu do&nbsp; &asymp;50&nbsp; keV,&nbsp; što ih čini&nbsp; neželjenom karikom fonskih događaja u eksperimentima koji tragaju za retkim nuklearnim događajima. Na osnovu rezultata simulacija, analizirani su elektromagnetni i hadronski procesi indukovani mionima i neutronima, kao i udeli mionske i neutronske komponente u koincidentnom spektru HPGe&nbsp; detektora i direktnom spektru plastičnog scintilacionog detektora. Zaključeno je da niskoenergijskom spektru,&nbsp; koji je prevashodno značajan za retke nuklearne procese,&nbsp; dominantno doprinose neutroni.</p> / <p>In&nbsp; this&nbsp; doctoral&nbsp; thesis,&nbsp; the&nbsp; results&nbsp; of&nbsp; the&nbsp; developed and&nbsp; applied&nbsp; coincidence&nbsp;&nbsp; methods&nbsp; on&nbsp; the&nbsp; timeanalysis&nbsp; of&nbsp; nuclear&nbsp; processes&nbsp; are&nbsp; presented. Coincidence systems, used in presented experiments, are&nbsp; based&nbsp; on&nbsp; the&nbsp; HPGe&nbsp; and&nbsp; plastic&nbsp; scintillation detectors.&nbsp; Three&nbsp; experiments&nbsp; were&nbsp; performed,showing&nbsp; a&nbsp; wide&nbsp; application&nbsp; of&nbsp; the&nbsp; developed coincidence&nbsp; systems.&nbsp; The&nbsp; first&nbsp; part&nbsp; of&nbsp; the experimental work involves the analysis of the time&nbsp; variations of cosmic rays via low-energy photons. It was&nbsp; shown&nbsp; that&nbsp; by&nbsp; analyzing&nbsp; the&nbsp; intensity&nbsp; of&nbsp; lowenergy photons better insight into the behavior of thebackground&nbsp; events&nbsp; is&nbsp; provided,&nbsp; which&nbsp; is&nbsp;&nbsp; especially important&nbsp; as&nbsp; a&nbsp; precondition&nbsp; for&nbsp; rare&nbsp; nuclear&nbsp; events experiments.&nbsp; Furthermore,&nbsp; it&nbsp; was&nbsp; shown&nbsp; that&nbsp; this method can be applied in order to search for periodic or aperiodic events resulting from the Sun activity. The&nbsp; second&nbsp; part&nbsp; contains&nbsp; the&nbsp; research&nbsp; of&nbsp; the&nbsp; 22Na decay constant fluctuations. The coincidence system was&nbsp; developed&nbsp; and&nbsp; the&nbsp; intensity&nbsp; of&nbsp; the&nbsp; annihilation line,&nbsp; resulting&nbsp; from&nbsp; annihilation&nbsp; of&nbsp; the&nbsp; positrons emitted from 22Na, was followed with time. During&nbsp; he&nbsp; acquisition&nbsp; time,&nbsp; no&nbsp; significant&nbsp; deviations&nbsp; from the standard exponential radioactive decay law were found. In&nbsp; the&nbsp; third&nbsp; part&nbsp; of&nbsp; the&nbsp; experimental&nbsp; work,&nbsp; the coincidence&nbsp; method&nbsp; for&nbsp; time&nbsp; separation&nbsp; of&nbsp; the events,&nbsp; induced&nbsp; by&nbsp; cosmic&nbsp; muons&nbsp; and&nbsp; neutrons&nbsp; in the&nbsp; vicinity&nbsp; of&nbsp; the&nbsp; detectors&nbsp; system,&nbsp; was&nbsp; presented. The time curve was obtained in the experiment and the&nbsp; detailed&nbsp; analysis&nbsp; of&nbsp; the&nbsp; different&nbsp; time&nbsp; regions was&nbsp; performed.&nbsp; The&nbsp; Monte&nbsp; Carlo&nbsp; simulations&nbsp; were conducted&nbsp; and&nbsp; the&nbsp; time&nbsp; curve&nbsp; from&nbsp; the&nbsp; simulation results was obtained. Analyzing the different regions of the simulated time curve, it was noticed that these events can be separated into two groups&ndash;prompt and delayed.&nbsp; Between&nbsp; delayed&nbsp; events,&nbsp; it&nbsp; was&nbsp; concluded that&nbsp; events&nbsp; induced&nbsp; by&nbsp; muons,&nbsp; dominantly annihilation&nbsp; line,&nbsp; and&nbsp; events&nbsp; induced&nbsp; by&nbsp; neutrons, which&nbsp; may&nbsp; be&nbsp; classified&nbsp; as&nbsp; more&nbsp; delayed&nbsp; events&nbsp; in the&nbsp; group&nbsp; of&nbsp; the&nbsp; delayed&nbsp; events,&nbsp; can&nbsp; be distinguished.&nbsp; It&nbsp; was&nbsp; concluded&nbsp; the&nbsp; neutrons dominantly&nbsp; contribute&nbsp; to&nbsp; the&nbsp; low-energy&nbsp; region, mostly&nbsp; in&nbsp; the&nbsp; region&nbsp; to&nbsp; &asymp;50&nbsp; keV,&nbsp; which&nbsp; makes neutrons&nbsp; an&nbsp; important&nbsp; background&nbsp; in&nbsp; the experiments searching for rare nuclear events. Based on&nbsp; the&nbsp; simulation&nbsp; results,&nbsp; electromagnetic&nbsp; and hadronic processes induced by muons and neutrons, as&nbsp; well&nbsp; as&nbsp; portions&nbsp; of&nbsp; muon&rsquo;s&nbsp; and&nbsp; neutron&rsquo;s component&nbsp; in&nbsp; the&nbsp; coincidence&nbsp; spectrum&nbsp; of&nbsp; HPGe detector&nbsp; and&nbsp; direct&nbsp; spectrum&nbsp; of&nbsp; the&nbsp; plastic scintillation&nbsp; detector&nbsp; were&nbsp; analyzed.&nbsp; It&nbsp; was concluded&nbsp; that&nbsp; in&nbsp; the&nbsp; low-energy&nbsp; part&nbsp; of&nbsp; the spectrum,&nbsp; primarily important for the search for rare nuclear&nbsp; events,&nbsp; dominant&nbsp; influence&nbsp; is&nbsp; originated from cosmic neutrons.</p>

The nuclear design of fusion devices such as ITER (International Thermonuclear Experimental Reactor), which is an experimental fusion reactor based on the &amp;quot;tokamak&amp;quot; concept, rely on the results of neutron physical calculations. These depend on the knowledge of the neutron and photon flux spectra which is particularly important because it permits to anticipate the possible answers of the whole structure to phenomena such as nuclear heating, tritium breeding, atomic displacements, radiation shielding, power generation and material activation. The flux spectra can be calculated with transport codes, but validating measurements are also required. An important constituent of structural materials and divertor areas of fusion reactors is tungsten. This thesis deals with the measurement of the neutron fluence and neutron energy spectrum in a tungsten assembly by means of multiple foil neutron activation technique. In order to check and qualify the experimental tools and the codes to be used in the tungsten benchmark experiment, test measurements in the D-T and D-D neutron fields of the neutron generator at Technische Universität Dresden were performed. The characteristics of the D-D and D-T reactions, used to produce monoenergetic neutrons, together with the selection of activation reactions suitable for fusion applications and details of the activation measurements are presented. Corrections related to the neutron irradiation process and those to the sample counting process are discussed, too. The neutron fluence and its energy distribution in a tungsten benchmark, irradiated at the Frascati Neutron Generator with 14 MeV neutrons produced by the T(d, n)4He reaction, are then derived from the measurements of the neutron induced &amp;amp;#947;-ray activity in the foils using the STAYNL unfolding code, based on the linear least-square-errors method, together with the IRDF-90.2 (International Reactor Dosimetry File) cross section library. The differences between the neutron flux spectra measured by means of neutron foil activation and the neutron flux spectra obtained in the same assembly, making use of an NE213 liquid-scintillation spectrometer were studied. The comparison of measured neutron spectra with the spectra calculated with the MCNP-4B (Monte Carlo neutron and photon transport) code, which allows a crucial test of the evaluated nuclear data used in fusion reactor design, is discussed, too. In conclusion, this thesis shows the applicability of the neutron foil activation technique for the measurement of neutron flux spectra inside a thick tungsten assembly irradiated with 14 MeV from a D-T generator. / Die Konstruktion von Fusionsreaktoren wie ITER (International Thermonuclear Experimental Reactor), der ein experimenteller Fusionsreaktor ist und auf dem &amp;quot;Tokamak&amp;quot;-Konzept beruht, basiert unter neutronenphysikalischen Gesichtspunkten auf den Ergebnissen von umfangreichen Simulationsrechnungen. Diese setzen die Kenntnis der Spektren des Neutronen- und Photonenflusses voraus die besonders wichtig ist, weil sie, die möglichen Antworten der ganzen Struktur auf physikalische Prozesse vorauszuberechnen erlaubt wie z.B.: Heizen durch nukleare Prozesse, Tritium-Brüten, Atomverschiebung, Abschirmung von Strahlung, Leistungserzeugung und Materialaktivierung. Die Flußspektren können mittels Transportcodes berechnet werden, aber es werden auch Messungen zu ihrer Bestätigung benötigt. Ein wichtiger Bestandteil des Strukturmaterials und der Divertor-Flächen der Fusionsreaktoren ist Wolfram. Diese Dissertation behandelt die Messungen der Neutronspektren und ?fluenz in einer Wolfram-Anordnung mittels der Multifolien-Neutronenaktivierungstechnik. Um die anzuwendenden experimentellen Geräte und die Codes, die im Wolfram-Benchmark-Experiment eingesetzt werden, zu überprüfen und zu bestimmen, wurden Testmessungen in den D-T und D-D Neutronenfeldern des Neutronengenerator der Technischen Universität Dresden durchgeführt. Die Eigenschaften der D-T und D-D Reaktionen, die für die Erzeugung von monoenergetischen Neutronen verwendet werden, sowie die Auswahl der Aktivierungsreaktionen, die für Fusionsanwendungen geeignet sind und die Aktivierungsmessung werden detailliert vorgestellt. Korrekturen, die sich auf den Neutronen-Bestrahlungsprozess und auf den Probenzählungsprozess beziehen, werden ebenfalls besprochen. Die Neutronenfluenz und ihre Energieverteilung in einem Wolfram-Benchmark, bestrahlt am Frascati Neutronen Generator mit 14 MeV-Neutronen aus der T(d, n)4He Reaktion, werden aus den Messungen der &amp;amp;#947;-Strahlenaktivität, die von Neutronen in den Folien induziert ist, durch den STAYNL Entfaltungscode, der auf der Methode der kleinsten Fehlerquadrate basiert, zusammen mit der IRDF-90.2 Wirkungsquerschnitt-Bibliothek abgeleitet. Die Unterschiede zwischen den Neutronenflußspektren, die mit Hilfe der Multifolien-Neutronenaktivierung ermittelt wurden, und den Neutronenflußspektren, gemessen im selben Aufbau mit einem NE-213 Flüssigszintillator, wurden untersucht. Die gemessenen Neutronenspektren werden den aus MCNP-4B Rechnungen (Monte Carlo neutron and photon transport) ermittelten Spektren gegenüber gestellt. Der Vergleich stellt einen wichtigen Test der evaluierten Kerndaten für Fusionsreaktorkonzepte dar. Zusammenfassend zeigt diese Arbeit die Anwendbarkeit der Multifolien-Neutronenaktivierungstechnik bei Messungen der Neutronenflussspektren innerhalb eines massiven Wolframblocks bei Bestrahlung mit schnellen Neutronen aus D-T Generatoren.