The effect of water ingress in two pebble bed high temperature gas-cooled reactors i.e. the PBMR-200 MWthermal and the PBMR-400 MWthermal were simulated and compared using the VSOP 99/05 suite of codes. To investigate the effect of this event on reactivity, power profiles and thermal neutron flux profiles, the addition of partial steam vapour pressures in stages up to 400 bar into the primary circuit for the PBMR-400 and up to 300 bar for the PBMR- 200 was simulated for both reactors. During the simulation, three scenarios were simulated, i.e. water ingress into the core only, water ingress into the reflectors only and water ingress into both the core and reflectors. The induced reactivity change effects were compared for these reactors. An in-depth analysis was also carried out to study the mechanisms that drive the reactivity changes for each reactor caused by water ingress into the fuel core only, the riser tubes in the reflectors only and ingress into both the fuel core and the riser tubes in the reflectors. The knowledge gained of these mechanisms and effects was used in order to propose design changes aimed at mitigating the reactivity increases, caused by realistic water ingress scenarios. Past results from simulations of water ingress into Pebble Bed Reactors were used to validate and verify the present simulation approach and results. The reactivity increase results for both reactors were in agreement with the German HTR-Modul calculations. / Thesis (MSc (Engineering Sciences in Nuclear Engineering))--North-West University, Potchefstroom Campus, 2013

Social and environmental justice for a growing and developing global population requires significant increases in energy use. A possible means of contributing to this energy increase is to incinerate plutonium from spent fuel of pressurised light water reactors (Pu(PWR)) in high-temperature reactors such as the Pebble Bed Modular Reactor Demonstration Power Plant 400 MWth (PBMR-DPP-400). Previous studies showed that at low temperatures a 3 g Pu(PWR) loading per fuel sphere or less had a positive uniform temperature reactivity coefficient (UTC) in a PBMR DPP-400. The licensing of this fuel design is consequently unlikely. In the present study it was shown by diffusion simulations of the neutronics, using VSOP-99/05, that there is a fuel design containing thorium and plutonium that achieves a negative maximum UTC. Further, a fuel design containing 12 g Pu(PWR) loading per fuel sphere achieved a negative maximum UTC as well as the other PBMR (Ltd.) safety limits of maximum power per fuel sphere, fast fluence and maximum temperatures. It is proposed that the low average thermal neutron flux, caused by reduced moderation and increased absorption of thermal neutrons due to the higher plutonium loading, is responsible for these effects. However, to fully understand the mechanisms involved a detailed quantitative analysis of the roll of each factor is required. A 12 g Pu(PWR) loading per fuel sphere analysis shows a burn-up of 180.7 GWd/tHM which is approximately double the proposed PBMR (Ltd.) low enriched uranium fuel burn-up. The spent fuel has only a decrease of 24.5 % in the Pu content which is sub-optimal with respect to proliferation and waste disposal objectives. Incinerating Pu(PWR) in the PBMR-DPP 400 MWth is potentially licensable and economically feasible and should be considered for application by industry. / MIng (Nuclear Engineering), North-West University, Potchefstroom Campus, 2012

Artificial insemination using cooled, transported semen has become a popular practice in the equine industry. However, equine sperm are assumed to show a decline in their fertilizing ability after 24 to 48 hours of cooled storage. Two measures that are commonly used to estimate the fertility of an ejaculate are sperm motility and sperm membrane integrity (SMI). Recently, it has been suggested that SMI may have a better correlation with fertility of an inseminate than sperm motility. The effect of cooled-storage on sperm quality over an extended time period was evaluated to illustrate changes in sperm characteristics that might be related to an ejaculate’s fertility. Semen was stored at 4°C in INRA 96 extender containing 10% seminal plasma for a period of 10 days. Data were collected daily on sperm motion characteristics, SMI, mitochondrial membrane potential, and DNA quality. To measure daily changes in SMI in stallion sperm, two fluorescent vital-staining protocols used in flow cytometric analysis were compared – a combination of SNARF-1, Yo-Pro-1, and Ethidium Homodimer 1 (SYE) and a combination of lectin from Pisum sativum and propidium iodide (PSA/PI). We hypothesized that the SYE protocol adapted for use with stallion sperm could detect more subtle, and perhaps earlier, damage to the sperm plasma membrane than the PSA/PI protocol. A combination of SYBR 14, propidium iodide, and JC-1 (SYPIJC) was used to measure mitochondrial membrane potential, as well as SMI. A computer-assisted sperm motion analysis (CASA) instrument was used to evaluate sperm motion characteristics; the sperm chromatin structure assay (SCSA) was used to measure the degree of DNA fragmentation. In this study, with the exception of sperm motility, the measures of sperm quality retained values consistent with “viability” after 10 days of cooled-storage. This suggests that the fertility of some stallions may last considerably longer than previously assumed, which could ultimately alter the time-table used for artificial insemination using cooled, transported semen.

Thesis (M. S.)--Mechanical Engineering, Georgia Institute of Technology, 2008. / Committee Chair: Willem F.G. Van Rooijen; Committee Member: Ghiaasiaan, Seyed M; Committee Member: Weston M. Stacey

Les futurs réacteurs à neutrons rapides refroidis au sodium (RNR-Na) doivent remplir les critères GEN-IV à savoir présenter des qualités d'économie, de sûreté améliorée, de résistance à la prolifération et de minimisation des déchets. Ce projet de thèse est dédié à l'étude de l'impact des combustibles innovants (spécialement le combustible oxyde sphere-pac chargé en actinides mineurs) sur les performances de sûreté des RNR-Na dédiés à la transmutation.Le code de calcul SIMMER-III, développé à l'origine pour les phases avancées d'un accident grave, est utilisé pour les simulations. Ce code a été étendu dans le cadre de cette thèse afin d'améliorer la simulation de la phase primaire de l'accident, en introduisant le traitement des effets en réactivité liés à la dilatation du cœur et les spécificités du combustible sphere-pac (conductivité thermique, gap). Les transitoires complets (de la phase d'initiation aux phases avancées) sont simulés avec cette version étendue du code. Dans le cadre de cette thèse, les propriétés thermiques du combustible sphere-pac ont été modélisées et adaptées à SIMMER. Une méthodologie innovante tenant compte des effets en réactivité liés à la dilation thermique du cœur dans un maillage Eulérien et dans le cadre de la cinétique spatiale a ensuite été développée. A chaque pas de temps, les dimensions et densités dilatées sont calculées pour chaque cellule suite aux variations de températures. Des facteurs correctifs sont appliqués aux densités dilatées pour obtenir une configuration équivalente (en réactivité) ayant les dimensions non-dilatées et des densités modifiées. De nouvelles sections efficaces sont calculées à partir de ces densités et l'effet en réactivité lié à la dilatation est calculé. Les résultats sont prometteurs pour des dilatations uniformes et non-uniformes. Des limitations dans le cas de dilatations non-uniformes ont été identifiées et des calculs neutroniques ont été effectués en vue de futurs développements SIMMER. Les résultats préliminaires sont encourageants. Enfin, deux cœurs RNR-Na, issus du précédent projet CP-ESFR, ont été modélisés avec des combustibles sphere-pac : le Working Horse et le CONF2 (présentant un plénum sodium élargi pour une diminution de l'effet de vide sodium). Des analyses de sûreté ont été effectuées afin de fournir une première évaluation du comportement du combustible sphere-pac comparé au combustible pastille. Les deux options sont analysées en situation nominale et accidentelle (accident de perte de débit primaire) en début de vie du cœur et après irradiation. Les analyses révèlent deux phases à considérer en début de vie pour le combustible sphere-pac. Au démarrage du réacteur, ce combustible n'est pas restructuré et sa conductivité thermique est très inférieure à celle du combustible pastille. Après quelques heures sous irradiation, il se restructure suite aux importants gradients de température, ce qui améliore sa conductivité. Il se comporte alors de façon similaire au combustible pastille. Ce travail a également permis d'évaluer le comportement accidentel du cœur CONF2 qui subit un transitoire doux, prouvant que le large plénum sodium prévient efficacement de larges insertions de réactivité positive. Cependant, avec l'ajout d'américium ou suite à l'irradiation, des excursions de puissance et de réactivité plus prononcées sont observées. Ce travail a permis de démontrer que le combustible sphere-pac ne semble pas causer de problèmes de sûreté spécifiques comparé au combustible pastille, dans les conditions de simulations actuelles. La prise en compte des effets en réactivité liés à la dilatation du cœur avec cette version étendue de SIMMER retarde et réduit le potentiel énergétique lors d'un accident. Les analyses confirment également l'action atténuante du plénum sodium sur les transitoires conduisant à la vidange du sodium du coeur. Le comportement du combustible sphere-pac dans ces conditions ouvre une perspective à son utilisation en RNR-Na. / Future sodium cooled fast reactors (SFRs) have to fulfill the GEN-IV requirements of enhanced safety, minimal waste production, increased proliferation resistance and high economical potential. This PhD project is dedicated to the evaluation of the impact of innovative fuels (especially minor actinides bearing oxide sphere-pac fuels) on the safety performance of advanced SFRs with transmutation option. The SIMMER-III code, originally tailored to mechanistically analyze later phases of core disruptive accidents, is employed for accident simulations. During the PhD project, the code has been extended for a better simulation of the early accident phase introducing the treatment of thermal expansion reactivity effects and for taking into account the specifics of sphere-pac fuels (thermal conductivity and gap conditions). The entire transients (from the initiating event to later accident phases) have been modeled with this extended SIMMER version. Within this PhD work, first the thermo-physical properties of sphere-pac fuel have been modeled and casted into SIMMER-III. Then, a new computational method to account for thermal expansion feedbacks has been developed to improve the initiation phase modeling of the code. The technique has the potential to evaluate these reactivity feedbacks for a fixed Eulerian mesh and in a spatial kinetics framework. At each time step, cell-wise expanded dimensions and densities are calculated based on temperature variations. Density factors are applied to the expanded densities to get an equivalent configuration (in reactivity) with original dimensions and modified densities. New cross sections are calculated with these densities and the reactivity of the equivalent configuration is computed. The developed methods show promising results for uniform and non-uniform expansions. For non-uniform expansions, model improvement needs have been identified and neutronics simulations have been carried out to support future SIMMER extensions. Preliminary results are encouraging. In the third part of the PhD, two core designs with conventional and sphere pac fuels are compared with respect to their transient behavior. These designs were established in the former CP-ESFR project: the working horse core and the optimized CONF2 core (with a large sodium plenum above the core for coolant void worth reduction). The two fuel design options are compared for steady state and transient conditions (Unprotected Loss of Flow accident, ULOF) either at beginning of life (BOL) or under irradiated conditions. Analyses for sphere-pac fuel reveal two main phases to consider at BOL. At start-up, the non-restructured sphere-pac fuel shows a low thermal conductivity compared to pellet fuel of same density. However, the fuel restructures quickly (in a few hours) due to the high thermal gradients and its thermal conductivity recovers. The fuel then shows a behavior close to the pellet one. The study also shows that the CONF2 core leads to a very mild transient for a ULOF accident at BOL. The large upper sodium plenum seems to effectively prevent large positive reactivity insertions. However, stronger reactivity and power peaks are observed under irradiated conditions or when americium is loaded in the core and lower axial blanket. This PhD work demonstrates, under current simulation conditions, that sphere-pac fuels do not seem to cause specific safety issues compared to standard pellet fuels, when loaded in SFRs. The accurate simulation of core thermal expansion reactivity feedbacks by means of the extended SIMMER version plays an important role in the accident timing (simulations confirm the expected delay in the first power peak) and on the energetic potential compared to the case where these feedbacks are omitted. The analyses also confirm the mitigating impact of a large sodium plenum on transients with voiding potential. The behavior of sphere-pac fuel in these conditions opens a perspective to its practical application in SFRs.

In the planned linear accelerator called Compact Linear Collider, CLIC, electrons and positrons will be accelerated to velocities near the speed of light. A limiting factor in accelerating structures are vacuum breakdowns, which are electrical discharges from a surface as a result of a large electric field being applied. In the preparatory studies for the CLIC, Uppsala University in collaboration with The European Organization for Nuclear Research, CERN, is building a DC Spark system to analyze vacuum breakdowns. This system containing large planar electrodes will be cooled down all the way down to around 4 K in order to limit the rate of wich vacuum breakdowns happen. When cooling a system like this, which consists of different components made of different materials there is the question of how the system will be affected. The objective of this project is to investigate how the cooling will affect the stability in terms of stresses and to analyze the cool down time of the system. Another goal is to make a material recommendation for a few parts based on the results. This will be done by simulating the cooling in COMSOL Multiphysics, which is a program that uses finite element analysis to solve complex problems where different branches of physics interact. The conclusion is that the system will most likely be stable as it is and there is no need to redesign it. The choice of recommended material is alumina with the reason being it should cause the least stress and the smallest gap between the electrodes when the cooling is done. There was no big difference in the cool down time between the materials. Further studies and simulations on the system is also recommended since there are many factors not taken into consideration in this study.

Made available in DSpace on 2014-10-09T12:44:01Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:07:25Z (GMT). No. of bitstreams: 1 06864.pdf: 11106654 bytes, checksum: 851c7803db872d59fc1f49dc465fa8af (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

Made available in DSpace on 2015-03-26T13:55:08Z (GMT). No. of bitstreams: 1 texto completo.pdf: 621878 bytes, checksum: a616ae227883c57266ba5606898260c2 (MD5) Previous issue date: 2006-08-11 / Conselho Nacional de Desenvolvimento Científico e Tecnológico / In Brazil, the dairy goat industry is characterized by a large number of low technology farms, with an average daily milk production per goat of 1 Kg. Semen biotechnologies as artificial insemination (AI) can be an important tool to improve the genetic gain and development of these farms. The use of frozen semen in IA protocols requires a higher level of technology and costs for the farmer when compared with the use of cooled or fresh semen; besides the fertility results from field trials using frozen semen are still doubtful. However the use of fresh semen is restrict to a short period after colleted as the viability of the cells decrease fast at environmental temperatures. Therefore the use of cooled semen in low level technology farms can result in a less-expensive and more efficient tool for multiplying the genetic material in these farms. The aim of this study was to evaluate the fertility in vivo of goat semen cooled and stored at 5˚ Celsius for 24 hours. The experiment was realized in the Goat Research Center of the Animal Science Department/Federal University of Vicosa, Brazil, from May until July (end of the natural breeding season) of 2005. Animals from the Alpine (n=2) and Saanen (n=2) breed were utilized as semen donors and a total of 71 females (lactating goats and young goats) from both breeds were used in the fertility trial. Semen was collected by artificial vagina method, diluted in Ringer Lactate solution and centrifuged at 420 G for 10 minutes. After, the semen pellet was rediluted in Egg-yolk (20% v/v) Citrate extender to achieve a total of 400x106 spermatozoa/ mL. The semen was stored in 0.25 French straws and then used immediately for AI or cooled (average cooling rate = -0.5 ˚C/minute) for 1 hour and stored at 5˚ C for 24 hours before its use for IA. The animals were bred with fresh or cooled semen at 12 hours after the on set of estrus; if the animals continued in estrus for more than 12 hours a second IA was realize at 24 hours after the first insemination. Pregnancy diagnosis was realized by transrectal ultrasonography using a real time B mode scanner with a 5 MHZ linear array transducer. The ultrasonography evaluations were done at day 45 after first IA. The conception rate for young goats (31.2 x 20,0%) and goats (44.4 x 17.6%) did not differ (P>0.05) between fresh or cooled semen, respectively. The total conception rate did not differ (P>0.05) between fresh (38.2%) and cooled (18.9%) semen. The average conception rate of this same herd and period was 28.2%. Historical data from the last four years in the same experimental period and farm showed an average conception rate of 39,9% (109/273). The present study didn't find differences in the conception rates for the semen diluted in Yolk-Citrate with 20% of Egg-Yolk and used to fresh or cold and stored by 24 hours to 5ºC, however, the fertility of the semen cold was below that obtained with controlled breed in the end of the natural reproductive station. Factors climatic, environmental and of handling, besides the quality of the animals, related with the end of the reproductive station, might have contributed to the low fertilities found in the present study. / Em nosso país, a caprinocultura leiteira é praticada em propriedades pouco tecnificadas, com produção média em torno de 1 kg de leite/cabra/dia. A utilização da inseminação artificial como ferramenta para o melhoramento genético é dependente dos resultados obtidos nos testes de fertilidade a campo. A utilização do sêmen congelado, além de esbarrar nos problemas de custos, ainda apresenta resultados contraditórios, sendo sua utilização limitada a poucos rebanhos matrizeiros. Já o sêmen fresco tem a limitação do curto tempo de viabilidade, ficando seu uso restrito a própria propriedade. Neste sentido a utilização do sêmen resfriado pode servir de alternativa barata para a multiplicação daqueles reprodutores de maior potencial genético. Assim, o presente estudo visou testar fertilidade in vivo do sêmen caprino, diluído em um extensor a base de citrato-gema e armazenado a 5ºC por 24 horas. Para tanto, conduziu-se um experimento durante os meses de maio de junho de 2005, no setor de Caprinocultura do DZO/UFV, o qual contou com quatro bodes e 71 cabras e cabritas, das raças Saanen e Alpina. O sêmen foi coletado em vagina artificial, imediatamente centrifugado em meio Ringer Lactato, a 402G por 10 minutos, em seguida o sobrenadante descartado e as células re-suspendidas em meio diluidor a base de citrato-gema, com 20% de gema de ovo, perfazendo um total de 100x106 espermatozóides móveis em um volume de 0,25 mL. Após o envase, metade das doses permanecia na bancada e a outra metade era submetida ao processo de resfriamento, com uma curva de aproximadamente 0,5ºC/minuto, atingindo a temperatura de geladeira 5ºC em 1 hora. De acordo com a ordem de manifestação do estro os animais entravam recebiam duas inseminações intervaladas de 24 horas, sendo a primeira realizada 12 horas após a observação do estro, com sêmen fresco ou resfriado. O diagnóstico de gestação foi realizado aos 45 dias, com auxilio de um ultra-som equipado com uma probe de 5 MHz de freqüência. Não houve diferenças significativas (P>0,05), quanto a fertilidade das cabritas foi de 31,2% (5/16) e 20,0% (4/20), e nem das cabras 44,4% e 17,6%, inseminadas com sêmen fresco e resfriado, respectivamente. Somando cabras e cabritas a fertilidade foi de 38,2% e 18,9%, respectivamente para o tratamento a fresco e resfriado, não sendo significativa a diferença (P>0,05). A taxa de concepção geral do experimento foi de 28,2%. Na mesma época do ano, a fertilidade do rebanho em um levantamento dos últimos quatro anos foi de 39,9% (109/273), podendo indicar problemas de fertilidade relacionados às fêmeas. O presente estudo não encontrou diferenças na taxa de concepção para o sêmen diluído em Citrato-Gema com 20% de Gema de ovo e utilizado a fresco ou resfriado e armazenado por 24 horas a 5ºC, no entanto, a fertilidade do sêmen resfriado ficou abaixo daquela obtida com a monta controlada no final da estação reprodutiva natural. Fatores climáticos, ambientais e de manejo, além da qualidade zootécnica dos animais, relacionada com o final da estação reprodutiva, podem ter contribuído para as baixas fertilidades encontradas no presente estudo.

In this work, which deals with problematics of releases from nuclear power plants, I tried to make an overview of various types of nuclear power plants and radioizotopes which are released through liquid and gasseous effluents. As a part of this comparison evaluation of czech and world nuclear power plants gaseous and liquid releases was made. Introductory part of this work contains information about different types of nuclear power plants and radioizotopes, which are produced in their reactors. It continues with today{\crq}s legislative and information about releasing levels and methods and systems used for measurement of radioactive gaseous and liquid effluents from nuclear power plants. Second part of this work describes the aim of this work and hypothesis. Third part explains the methods, which were used for completing of this work. Fourth part contains results in the form of tables and graphs. Fifth part represents discussion of the results. Last part is a summarization of the results.

Made available in DSpace on 2014-10-09T12:44:01Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:07:25Z (GMT). No. of bitstreams: 1 06864.pdf: 11106654 bytes, checksum: 851c7803db872d59fc1f49dc465fa8af (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP