Refueling in nuclear engineering: the FUELCON project

Over a time span of almost a decade, the FUELCON project in nuclear engineering has led to a fully functional expert system and spawned sequel projects. Its task is in-core fuel management, also called `refueling', i.e., good fuel-allocation for reloading the core of a given nuclear reactor, for a given operation cycle. The task is crucial for keeping down operation costs at nuclear power plants. Fuel comes in different types and is positioned in a grid representing the core of a reactor. The tool is useful for practitioners but also helps the expert in the domain to test his or her rules of thumb and to discover new ones.

Desempenho de sondas Lambda no monitoramento de motores do ciclo Otto alimentados por etanol e GNV

Pós-graduação em Engenharia Mecânica - FEB

Impact of E22 on two-stroke and four-stroke snowmobiles

A push to reduce dependency on foreign energy and increase the use of renewable energy has many gas stations pumping ethanol blended fuels. Recreational engines typically have less complex fuel management systems than that of the automotive sector. This prevents the engine from being able to adapt to different ethanol concentrations. Using ethanol blended fuels in recreational engines raises several consumer concerns. Engine performance and emissions are both affected by ethanol blended fuels. This research focused on assessing the impact of E22 on two-stroke and four-stroke snowmobiles. Three snowmobiles were used for this study. A 2009 Arctic Cat Z1 Turbo with a closed-loop fuel injection system, a 2009 Yamaha Apex with an open-loop fuel injection system and a 2010 Polaris Rush with an open-loop fuel injection system were used to determine the impact of E22 on snowmobile engines. A five mode emissions test was conducted on each of the snowmobiles with E0 and E22 to determine the impact of the E22 fuel. All of the snowmobiles were left in stock form to assess the effect of E22 on snowmobiles currently on the trail. Brake specific emissions of the snowmobiles running on E22 were compared to that of the E0 fuel. Engine parameters such as exhaust gas temperature, fuel flow, and relative air to fuel ratio (λ) were also compared on all three snowmobiles. Combustion data using an AVL combustion analysis system was taken on the Polaris Rush. This was done to compare in-cylinder pressures, combustion duration, and location of 50% mass fraction burn. E22 decreased total hydrocarbons and carbon monoxide for all of the snowmobiles and increased carbon dioxide. Peak power increased for the closed-loop fuel injected Arctic Cat. A smaller increase of peak power was observed for the Polaris due to a partial ability of the fuel management system to adapt to ethanol. A decrease in peak power was observed for the open-loop fuel injected Yamaha.

Performance of a transmutation advanced device for sustainable energy application

Preliminary studies have been performed to design a device for nuclear waste transmutation and hydrogen generation based on a gas-cooled pebble bed accelerator driven system, TADSEA (Transmutation Advanced Device for Sustainable Energy Application). In previous studies we have addressed the viability of an ADS Transmutation device that uses as fuel wastes from the existing LWR power plants, encapsulated in graphite in the form of pebble beds, cooled by helium which enables high temperatures (in the order of 1200 K), to generate hydrogen from water either by high temperature electrolysis or by thermochemical cycles. For designing this device several configurations were studied, including several reflectors thickness, to achieve the desired parameters, the transmutation of nuclear waste and the production of 100 MW of thermal power. In this paper new studies performed on deep burn in-core fuel management strategy for LWR waste are presented. The fuel cycle on TADSEA device has been analyzed based on both: driven and transmutation fuel that had been proposed by the General Atomic design of a gas turbine-modular helium reactor. The transmutation results of the three fuel management strategies, using driven, transmutation and standard LWR spent fuel were compared, and several parameters describing the neutron performance of TADSEA nuclear core as the fuel and moderator temperature reactivity coefficients and transmutation chain, are also presented

Modelado detallado de una central nuclear CANDU con CITVAP.

La línea de cálculo de INVAP consiste principalmente de los códigos CONDOR y CITVAP. Este último es la versión mejorada del código CITATION II que resuelve la ecuación de difusión neutrónica multigrupo por el método de diferencias finitas. CITVAP es ampliamente usado para estudiar reactores de investigación y reactores de potencia tales como PWR, BWR, VVER y últimamente se implemento nuevas funciones para estudiar una central PHWR tipo Atucha. Siguiendo con la línea de reactores PHWR, en este trabajo se estudian las capacidades y deficiencias del código de núcleo CITVAP para modelar una central nuclear tipo CANDU. Se plantean mejoras a realizar para un manejo mas eficiente desde el punto de vista del usuario, tanto de la gestión de combustibles, movimientos de barras de control y zonas líquidas como mejoras en el modelo termohidraulico. La metodología consiste en validar la línea de cálculo de INVAP, contrastando los resultados con el benchmark IAEA-tecdoc-887. El proceso de validación consiste en cálculos de celda en dos y tres dimensiones usando los códigos CONDOR y SERPENT respectivamente, obtención de secciones eficaces macroscópicas en función del quemado y cálculos de núcleo para distintas configuraciones de los dispositivos de control usando un núcleo fresco y una distribución de quemado en equilibrio. Se analizan las dificultades que se presentan al modelar el núcleo con las capacidades actuales del código y se plantean posibles soluciones a implementar. Para un estudio completo de un reactor CANDU, se estudian tres de la características distintivas de este tipo de reactor: la termohidraulica, la gestión de combustibles y los dispositivos de control de reactividad, distribución de potencia y apagado.

Modelado detallado de una central nuclear CANDU con CITVAP.

La línea de cálculo de INVAP consiste principalmente de los códigos CONDOR y CITVAP. Este último es la versión mejorada del código CITATION II que resuelve la ecuación de difusión neutrónica multigrupo por el método de diferencias finitas. CITVAP es ampliamente usado para estudiar reactores de investigación y reactores de potencia tales como PWR, BWR, VVER y últimamente se implemento nuevas funciones para estudiar una central PHWR tipo Atucha. Siguiendo con la línea de reactores PHWR, en este trabajo se estudian las capacidades y deficiencias del código de núcleo CITVAP para modelar una central nuclear tipo CANDU. Se plantean mejoras a realizar para un manejo mas eficiente desde el punto de vista del usuario, tanto de la gestión de combustibles, movimientos de barras de control y zonas líquidas como mejoras en el modelo termohidraulico. La metodología consiste en validar la línea de cálculo de INVAP, contrastando los resultados con el benchmark IAEA-tecdoc-887. El proceso de validación consiste en cálculos de celda en dos y tres dimensiones usando los códigos CONDOR y SERPENT respectivamente, obtención de secciones eficaces macroscópicas en función del quemado y cálculos de núcleo para distintas configuraciones de los dispositivos de control usando un núcleo fresco y una distribución de quemado en equilibrio. Se analizan las dificultades que se presentan al modelar el núcleo con las capacidades actuales del código y se plantean posibles soluciones a implementar. Para un estudio completo de un reactor CANDU, se estudian tres de la características distintivas de este tipo de reactor: la termohidraulica, la gestión de combustibles y los dispositivos de control de reactividad, distribución de potencia y apagado.

A novel approach to reduce fire exposure and promote nature conservation in Mediterranean ecosystems: the case study of Reserva Natural da Serra da Malcata, Portugal

Mestrado Mediterranean Forestry and Natural Resources Management - Instituto Superior de Agronomia - UL

Logistics management and costs of biomass fuel supply

Discusses part of a project conducted by the authors into the logistics planning and management and costs of supplying biomass fuels to biomass-fired power stations in the UK. Defines biomass fuels and the reasons for the growth in interest in their use for electricity generation. The activities and parties involved in the biomass fuel supply chain are discussed together with the management of the chain in order to achieve smooth and consistent flow of biomass fuel to power stations. Explains the approach used to modelling the delivered costs of biomass fuels for four types of biomass fuel included in the project: forest fuel, short rotation coppice, straw and miscanthus. Comments are given on the environmental impacts of the fuel supply chains. The results indicate that straw supply systems are capable of producing the lowest delivered costs of the four fuels studied. Short rotation coppice and miscanthus, two new energy crops, are likely to have the highest delivered costs at present. This is due to the cost of growing these fuels and the financial incentives required by farmers to persuade them to grow these crops. Logistics costs (i.e. transport, storage and handling) are shown to represent a significant proportion of total delivered cost in biomass supply. Careful supply chain planning and logistics management will be of central importance to the success of the biomass industry.

Implementation of a phenomenological evaporation model into a porous network simulation for water management in low temperature fuel cells

A phenomenological transition film evaporation model was introduced to a pore network model with the consideration of pore radius, contact angle, non-isothermal interface temperature, microscale fluid flows and heat and mass transfers. This was achieved by modeling the transition film region of the menisci in each pore throughout the porous transport layer of a half-cell polymer electrolyte membrane (PEM) fuel cell. The model presented in this research is compared with the standard diffusive fuel cell modeling approach to evaporation and shown to surpass the conventional modeling approach in terms of predicting the evaporation rates in porous media. The current diffusive evaporation models used in many fuel cell transport models assumes a constant evaporation rate across the entire liquid-air interface. The transition film model was implemented into the pore network model to address this issue and create a pore size dependency on the evaporation rates. This is accomplished by evaluating the transition film evaporation rates determined by the kinetic model for every pore containing liquid water in the porous transport layer (PTL). The comparison of a transition film and diffusive evaporation model shows an increase in predicted evaporation rates for smaller pore sizes with the transition film model. This is an important parameter when considering the micro-scaled pore sizes seen in the PTL and becomes even more substantial when considering transport in fuel cells containing an MPL, or a large variance in pore size. Experimentation was performed to validate the transition film model by monitoring evaporation rates from a non-zero contact angle water droplet on a heated substrate. The substrate was a glass plate with a hydrophobic coating to reduce wettability. The tests were performed at a constant substrate temperature and relative humidity. The transition film model was able to accurately predict the drop volume as time elapsed. By implementing the transition film model to a pore network model the evaporation rates present in the PTL can be more accurately modeled. This improves the ability of a pore network model to predict the distribution of liquid water and ultimately the level of flooding exhibited in a PTL for various operating conditions.

Static and dynamic contact angle measurement on rough surfaces using sessile drop profile analysis with application to water management in low temperature fuel cells

Fuel Cells are a promising alternative energy technology. One of the biggest problems that exists in fuel cell is that of water management. A better understanding of wettability characteristics in the fuel cells is needed to alleviate the problem of water management. Contact angle data on gas diffusion layers (GDL) of the fuel cells can be used to characterize the wettability of GDL in fuel cells. A contact angle measurement program has been developed to measure the contact angle of sessile drops from drop images. Digitization of drop images induces pixel errors in the contact angle measurement process. The resulting uncertainty in contact angle measurement has been analyzed. An experimental apparatus has been developed for contact angle measurements at different temperature, with the feature to measure advancing and receding contact angles on gas diffusion layers of fuel cells.

Water transport in complex, non-wetting porous layers with applications to water management in low temperature fuel cells

An experimental setup was designed to visualize water percolation inside the porous transport layer, PTL, of proton exchange membrane, PEM, fuel cells and identify the relevant characterization parameters. In parallel with the observation of the water movement, the injection pressure (pressure required to transport water through the PTL) was measured. A new scaling for the drainage in porous media has been proposed based on the ratio between the input and the dissipated energies during percolation. A proportional dependency was obtained between the energy ratio and a non-dimensional time and this relationship is not dependent on the flow regime; stable displacement or capillary fingering. Experimental results show that for different PTL samples (from different manufacturers) the proportionality is different. The identification of this proportionality allows a unique characterization of PTLs with respect to water transport. This scaling has relevance in porous media flows ranging far beyond fuel cells. In parallel with the experimental analysis, a two-dimensional numerical model was developed in order to simulate the phenomena observed in the experiments. The stochastic nature of the pore size distribution, the role of the PTL wettability and morphology properties on the water transport were analyzed. The effect of a second porous layer placed between the porous transport layer and the catalyst layer called microporous layer, MPL, was also studied. It was found that the presence of the MPL significantly reduced the water content on the PTL by enhancing fingering formation. Moreover, the presence of small defects (cracks) within the MPL was shown to enhance water management. Finally, a corroboration of the numerical simulation was carried out. A threedimensional version of the network model was developed mimicking the experimental conditions. The morphology and wettability of the PTL are tuned to the experiment data by using the new energy scaling of drainage in porous media. Once the fit between numerical and experimental data is obtained, the computational PTL structure can be used in different types of simulations where the conditions are representative of the fuel cell operating conditions.

Increased fuel economy in transportation systems by use of energy management. Volume II - digital automotive propulsion simulator programs and description.

Transportation Department, Washington, D.C.

Increased fuel economy in transportation systems by use of energy management. Volume III. Real-time (hybrid computer) simulation program set.

Transportation Department, Washington, D.C.

Fuel cell benefits : the program management office viewpoint /

Mode of access: Internet.