There has been increasing interest in the nature of happiness and how to achieve it in psychological, sociological, economic and political realms along with discourse on the happiness and well being of children and young people. The aim of the current research was to explore young people's constructs of happiness. There were two research questions: firstly to explore the young people's definitions of happiness; secondly to explore what they felt contributed to this happiness. Ten young people aged thirteen to fourteen volunteered to participate in an individual semi-structured interview with the researcher. The data were analysed and theory was developed using the Grounded Theory method taking a social constructionist approach. The subsequent theory of happiness according to the young people was: friendships bring enduring happiness and are represented by knowing one is cared for and understood as part of a reciprocal relationship, and the activities people share together, particularly talking. Enduring happiness is also achieved through accomplishment whereas temporary happiness is achieved via material factors. Happiness impacts on friendships and accomplishment, and without it there is only unhappiness. Happiness and unhappiness are influenced by environmental factors which are both active and passive. The theory was discussed according to the existing literature. Implications of the findings for the research area and Educational Psychology practice are discussed with suggestions for future research.

Thesis (D.B.A.)--Boston University / PLEASE NOTE: Boston University Libraries did not receive an Authorization To Manage form for this thesis or dissertation. It is therefore not openly accessible, though it may be available by request. If you are the author or principal advisor of this work and would like to request open access for it, please contact us at open-help@bu.edu. Thank you. / This study has three parts. The first part focuses at the business segment definition of SFAS No. 131. One of the expected improvements of SFAS No. 131 was to provide business segment information that corresponds to internal organizational structure. I provide an empirical test of whether segment information prepared under SFAS No. 131 discloses the internal organizational structure of a company. The results show that segment information provided in financial reports under SFAS No. 131 is consistent with the internal organizational structures [TRUNCATED] / 2031-01-02

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O 131I é um radioisótopo de iodo amplamente utilizado em medicina nuclear, pode ser utilizado tanto para diagnóstico quanto para tratamento devido às suas características físicas de decaimento - e sua elevada emissão de raios-y. Sua produção no IPEN é realizada utilizando um reator nuclear a partir da reação indireta: 130Te (n,y) 131mTe 131Te 131I, onde são irradiados alvos contendo Te. Pode também ser produzido via produto de fissão de 235U, onde, o 235U irradiado produz cerca de 300 elementos diferentes, entre eles o 131I. O 131I produzido nesse método apresenta altas atividade específica e concentração radioativa, o que facilita a produção de compostos marcados com o radionuclídeo. O objetivo deste trabalho é desenvolver um método de recuperação de 131I no processo de produção de 99Mo pela rota de dissolução ácida de alvos de 235U, com a qualidade necessária para ser utilizado em Medicina Nuclear. O 131I encontra-se em 2 fases no processo, tanto na fase gasosa produzida na dissolução ácida dos alvos de U metálico e a menor parte em solução. Foram utilizados diversos materiais para captura e recuperação de 131I nas 2 fases do processo, a fase gasosa e a solução de dissolução dos alvos de U. Foram testadas colunas de alumina com Cu, alumina ácida com Cu, nanoesferas de Ag, cartuchos aniônicos, resina aniônica, colunas de carvão ativado, microesferas de Ag e microesferas de Cu. Soluções contendo 131I em NaOH 0,1 mol.L-1 foram percoladas pelos materiais e os eluídos foram analisados em calibrador de dose. Foi também estudada a precipitação de AgI e dissolução desse precipitado em NH4OH 0,1 mol L-1 e Na2S2O3 5%. Dentre os testes realizados, a princípio, os resultados de recuperação variaram de acordo com o material, o carvão ativado apresentou rendimento de recuperação entre 42% a 83%. Já o rendimento de recuperação da coluna de alumina com Cu variou de 20% a 85%. Os testes com nanoesferas de Ag apresentaram rendimento de recuperação de 26% utilizando NaOH 0,1 mol L-1 e 72% utilizando Na2S2O3 como eluentes. Testes com cartuchos aniônicos apresentaram os melhores resultados com uma porcentagem de recuperação de 81 a 90%. Testes utilizando 131I na sua forma gasosa apresentaram uma retenção de 66,45% e não foram realizados testes para recuperação do 131I retido. Nos testes utilizando precipitação de AgI a porcentagem de retenção de 131I foi de 100%. É possível concluir que os cartuchos aniônicos e a precipitação de AgI foram as melhores opções para a retenção de 131I, e as colunas de alumina com Cu tem um grande potencial para eluição do radionuclídeo 131I na forma química adequada. / 131I is an iodine radioisotope widely used in nuclear medicine that can be used either for diagnostic or for treatment due to its physical decay by - and its high emission of -rays. It is produced at IPEN using the indirect reaction: 130Te(n,)131mTe 131Te 131I where TeO2 targets are irradiated in a Nuclear Reactor. There is also the possibility of producing 131I by the fission of 235U, where about 300 different elements are produced together with 131I. The 131I produced through this method presents high specific activity and radioactive concentration suitable for the labeling of molecules. The aim of this work was to develop a recovery method of 131I with the required quality to be used in Nuclear Medicine in the 99Mo production process through the route of acid dissolution of metallic 235U targets. 131I can appear in two phases of the process, both in the gaseous phase produced during the dissolution of metallic U targets and in the dissolution solution. This work studied the recovery of 131I in these two phases. Several materials were used for the capture and recovery of 131I at the two phases of the process, the gaseous one and the solution of dissolution of U targets. Columns of alumina with Cu, acid alumina with Cu, Ag microspheres, Cu microspheres, Ag nanospheres, anionic cartridges, Ag cartridges, anion exchange resin and activated charcoal columns were tested. Solutions containing 131I in 0.1 mol.L-1 NaOH were percolated through the materials and the eluted solutions were analyzed in a dose calibrator. The precipitation of AgI was also studied wth further dissolution of this precipitate with 0.1 mol L-1 NH4OH and 5% Na2S2O3. The recovery results varied according to the material, activated charcoal showed recovery yields between 42% and 83% but the recovery yield of the alumina column with Cu ranged from 20% to 85%. Tests with Ag nanospheres showed recovery yield of 26% using 0.1 mol L-1NaOH and 72% for Na2S2O3. Tests with anionic cartridges showed the best results with a recovery percentage ranging between 81 to 90%. Tests using 131I in the gaseous phase presented retention of 66.45% and its elution was not studied. The experiments with the AgI precipitation showed total retention of 131I. It can be concluded that the anionic cartridges and the precipitation of AgI have higher affinity for the retention of 131I, and alumina columns with Cu have great potential for its elution in a suitable chemical form.

O 131I é um radioisótopo de iodo amplamente utilizado em medicina nuclear, pode ser utilizado tanto para diagnóstico quanto para tratamento devido às suas características físicas de decaimento - e sua elevada emissão de raios-y. Sua produção no IPEN é realizada utilizando um reator nuclear a partir da reação indireta: 130Te (n,y) 131mTe 131Te 131I, onde são irradiados alvos contendo Te. Pode também ser produzido via produto de fissão de 235U, onde, o 235U irradiado produz cerca de 300 elementos diferentes, entre eles o 131I. O 131I produzido nesse método apresenta altas atividade específica e concentração radioativa, o que facilita a produção de compostos marcados com o radionuclídeo. O objetivo deste trabalho é desenvolver um método de recuperação de 131I no processo de produção de 99Mo pela rota de dissolução ácida de alvos de 235U, com a qualidade necessária para ser utilizado em Medicina Nuclear. O 131I encontra-se em 2 fases no processo, tanto na fase gasosa produzida na dissolução ácida dos alvos de U metálico e a menor parte em solução. Foram utilizados diversos materiais para captura e recuperação de 131I nas 2 fases do processo, a fase gasosa e a solução de dissolução dos alvos de U. Foram testadas colunas de alumina com Cu, alumina ácida com Cu, nanoesferas de Ag, cartuchos aniônicos, resina aniônica, colunas de carvão ativado, microesferas de Ag e microesferas de Cu. Soluções contendo 131I em NaOH 0,1 mol.L-1 foram percoladas pelos materiais e os eluídos foram analisados em calibrador de dose. Foi também estudada a precipitação de AgI e dissolução desse precipitado em NH4OH 0,1 mol L-1 e Na2S2O3 5%. Dentre os testes realizados, a princípio, os resultados de recuperação variaram de acordo com o material, o carvão ativado apresentou rendimento de recuperação entre 42% a 83%. Já o rendimento de recuperação da coluna de alumina com Cu variou de 20% a 85%. Os testes com nanoesferas de Ag apresentaram rendimento de recuperação de 26% utilizando NaOH 0,1 mol L-1 e 72% utilizando Na2S2O3 como eluentes. Testes com cartuchos aniônicos apresentaram os melhores resultados com uma porcentagem de recuperação de 81 a 90%. Testes utilizando 131I na sua forma gasosa apresentaram uma retenção de 66,45% e não foram realizados testes para recuperação do 131I retido. Nos testes utilizando precipitação de AgI a porcentagem de retenção de 131I foi de 100%. É possível concluir que os cartuchos aniônicos e a precipitação de AgI foram as melhores opções para a retenção de 131I, e as colunas de alumina com Cu tem um grande potencial para eluição do radionuclídeo 131I na forma química adequada. / 131I is an iodine radioisotope widely used in nuclear medicine that can be used either for diagnostic or for treatment due to its physical decay by - and its high emission of -rays. It is produced at IPEN using the indirect reaction: 130Te(n,)131mTe 131Te 131I where TeO2 targets are irradiated in a Nuclear Reactor. There is also the possibility of producing 131I by the fission of 235U, where about 300 different elements are produced together with 131I. The 131I produced through this method presents high specific activity and radioactive concentration suitable for the labeling of molecules. The aim of this work was to develop a recovery method of 131I with the required quality to be used in Nuclear Medicine in the 99Mo production process through the route of acid dissolution of metallic 235U targets. 131I can appear in two phases of the process, both in the gaseous phase produced during the dissolution of metallic U targets and in the dissolution solution. This work studied the recovery of 131I in these two phases. Several materials were used for the capture and recovery of 131I at the two phases of the process, the gaseous one and the solution of dissolution of U targets. Columns of alumina with Cu, acid alumina with Cu, Ag microspheres, Cu microspheres, Ag nanospheres, anionic cartridges, Ag cartridges, anion exchange resin and activated charcoal columns were tested. Solutions containing 131I in 0.1 mol.L-1 NaOH were percolated through the materials and the eluted solutions were analyzed in a dose calibrator. The precipitation of AgI was also studied wth further dissolution of this precipitate with 0.1 mol L-1 NH4OH and 5% Na2S2O3. The recovery results varied according to the material, activated charcoal showed recovery yields between 42% and 83% but the recovery yield of the alumina column with Cu ranged from 20% to 85%. Tests with Ag nanospheres showed recovery yield of 26% using 0.1 mol L-1NaOH and 72% for Na2S2O3. Tests with anionic cartridges showed the best results with a recovery percentage ranging between 81 to 90%. Tests using 131I in the gaseous phase presented retention of 66.45% and its elution was not studied. The experiments with the AgI precipitation showed total retention of 131I. It can be concluded that the anionic cartridges and the precipitation of AgI have higher affinity for the retention of 131I, and alumina columns with Cu have great potential for its elution in a suitable chemical form.

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La radio à 60 GHz émerge comme l'un des candidats les plus prometteurs pour la transmission de données à haut débit (10 Gb/s) sur des courtes distances (1 à 10m). La radio 60 GHz à l’état de l’art utilise des émetteurs-récepteurs exclusivement analogiques. Les technologies CMOS sub-microniques profondes ont permis le développement de circuits de bande de base numériques pour les communications sans fil à plus basse fréquence. Dans ce travail une architecture d’émetteur numérique destinée aux communications à 60GHz a été étudiée. Elle est basée sur un interpolateur numérique et un DRFC (convertisseur direct numérique-RF), structure qui associe un DAC et un mélangeur pour réaliser une conversion directe du flux de données numériques à la fréquence RF. Le standard IEEE 802.15.3c pour communications sans fil à 60 GHz a été pris comme référence pour étudier l'émetteur proposé. Le flux de données numérique à la sortie en bande de base (échantillonnés à 2,5 Géch / s) doit être sur-échantillonné, et les répliques du signal aux multiples de la fréquence d'échantillonnage initiaux doivent être filtrés. Ces images sont atténués avec un interpolateur filtre FIR fonctionnant à 10 Gech/s.Un prototype de l'interpolateur à10Gech/s a été implémenté dans une technologie CMOS 65nm pour prouver la faisabilité du concept. Le filtre utilise des coefficients « puissances de deux » et de la logique dynamique pour atteindre le taux d'échantillonnage requis. Le circuit prototype de ce transmetteur démontre la pleine fonctionnalité jusqu'à 9,6 GHz et consomme 408mA (571mW) avec une tension d'alimentation de 1.4V. La surface de silicium centrale est de 650 x 170 um2. / Recent deep sub-micron CMOS technologies have allowed the development of digital baseband circuits for wireless communications. 60 GHz radio has emerged as one of the most promising candidates for high-data-rate (10 Gb/sec), short-distance (1 to 10 m), wireless telecommunication systems. State-of-the-art 60 GHz radio use exclusively analog transceivers. Recent deep sub-micron CMOS technologies have allowed the development of highly digital transceivers for wireless communications in the lower GHz range. In this work, a digital transmitter architecture targeted at 60GHz c communications has been studied. It is based on the combination of an interpolator and a DRFC (digital-to-RF converter), structure which combines a DAC and mixer in order to realize a direct conversion of the digital data stream to the RF frequency. The 60 GHz wireless standard IEEE 802.15.3c has been taken as a reference to study the proposed transmitter. The digital data stream at the baseband output (sampled at 2.5 GS/s) needs to be oversampled and resulting replicas of the signal at multiples of the initial sampling frequency have to be filtered. Images at multiples of the initial sampling frequency are attenuated with an interpolator FIR filter working at 10 GS/s. A prototype of the 10GS/s interpolator has been implemented in a 65nm CMOS technology to prove the feasibility of the concept. The filter uses powers of two coefficients and dynamic logic to reach the required sampling rate. The fabricated prototype transmitter IC demonstrates full functionality up to a 9.6 GHz and consumes 408mA (571mW) with a 1.4V supply voltage. The core area is 650 x 170 um2.

No abstract in the thesis