engineering

go nuclear!

       The secret of being a bore is to tell everything. Voltaire
 

here you may find some nuclear engineering related works I have done in collaboration with other authors. I have earned both Bachelor and Master in Nuclear Engineering at Instituto Balseiro in Argentina. Currently I am working in TECNA located in Puerto Madero, Buenos Aires in the nuclear energy department assisting nuclear projects in Argentina.

my main academic interests area thermal-hydraulic instabilities with neutronic feedback in nuclear reactor geometries, especially having in mind the associated nonlinear effects. In this scope, one field of development that I have almost finnished is the MELON fuzzy controller. Also time series analysis, chaotic charaterization, artificial neural networks, experimental thermal-hydraulic loops, neutronic dynamics with 3D kinetics and two phase flow area part of my personal interests.

should you need further information about any subject you think I might be helpful, do not hesitate contacting me.

non-linear analysis of instabilities in the coupled thermalhydraulic-neutronic problem

below is my Master in Nuclear Engineering thesis at Instituto Balseiro, dated october 2008. Unfortunately, I only have translated the abstract in order to submit the full document to IAEA INIS database. The rest of the work is only in spanish.

abstract

The analysis of the role that the mutual effects of the thermal hydraulic and the neutronic aspects play in the dynamic behaviour of a nuclear reactor is the central problem of its engineering design. Particularly, stability studies are key issues, especially during conceptual stages. In this work we propose a general non-linear stability analysis method based on the computation of the fractal dimension of the orbits followed by a dynamical system in phase space, and we develop and further study two mathematical models for different nuclear power reactor designs. We start by showing how the proposed method works applying it to the well known chaotic Lorenz system. Then, on the one hand, we investigate the physical origin of the thermal hydraulic instabilities in both single and two-phase flow, and that of the neutronic dynamics on the other hand. Finally, we couple the thermal hydraulic and the neutronic problem developing two dynamical systems that model the behaviour of an integrated natural circulation reactor and a parallel vertical channel reactor. In each case, we construct stability maps in parameter space, paying special attention to the main design variables and identifying those that contribute most to rendering the system unstable.

 

 

fuzzy logic controllers and chaotic natural convection loops

this is my Bachelor of Science in Nuclear Engineering thesis at Instituto Balseiro, dated june 2007. As above, I only have translated the abstract in order to submit the full document to IAEA INIS database. The rest of the work is only in spanish.

abstract

The study of natural circulation loops is a subject of special concern for the engineering design of advanced nuclear reactors, as natural convection provides an efficient and completely passive heat removal system. However, under certain circumstances thermal-fluid-dynamical instabilities may appear, threatening the reactor safety as a whole. On the other hand, fuzzy logic controllers provide an ideal framework to approach highly non-linear control problems. In the present work, we develop a software-based fuzzy logic controller and study its application to chaotic natural convection loops. We numerically analyse the linguistic control of the loop known as the Welander problem in such conditions that, if the controller were not present, the circulation flow would be non-periodic unstable. We also design a Takagi-Sugeno fuzzy controller based on a fuzzy model of a natural convection loop with a toroidal geometry, in order to stabilize a Lorenz-chaotic behaviour. Finally, we show experimental results obtained in a rectangular natural circulation loop.

 

 

there are also some previous works related to the main field of research that may prove useful. Please note that I am not actually in active academic research. Nevertheless, I think I will start a long-term background PhD career any time now.

 

 

microaxial adq12b-b driver for linux

microaxial is an argentinian data aquisition hardware manufacturer. Sadly, they do not offer linux support for their products. So, in order to use the adq12-b card we have at our laboratory, I had to write a driver that is now part of the comedi distribution (version 0.7.76 or higher).

instructions on how to load the driver may be found in the comedi documentation. An example of loading the adq12b driver may be found in the comedi issues chapter of the melon documentation. For the particular adq12b driver, the available documentation in the main comedi distribution is automatically generated from the source code, namely:

/*
Driver: adq12b
Description: driver for MicroAxial ADQ12-B data acquisition and control card
Devices: [MicroAxial] ADQ12-B (adq12b)
Author: jeremy theler 
Updated: Thu, 21 Feb 2007 02:56:27 -0300
Status: works

Driver for the acquisition card ADQ12-B (without any add-on).

 - Analog input is subdevice 0 (16 channels single-ended or 8 differential)
 - Digital input is subdevice 1 (5 channels)
 - Digital output is subdevice 1 (8 channels)
 - The PACER is not supported in this version

If you do not specify any options, they will default to

  # comedi_config /dev/comedi0 adq12b 0x300,0,0

  option 1: I/O base address. The following table is provided as a help
   of the hardware jumpers.

         address            jumper JADR
          0x300                 1 (factory default)
          0x320                 2
          0x340                 3
          0x360                 4
          0x380                 5
          0x3A0                 6

  option 2: unipolar/bipolar ADC selection: 0 -> bipolar, 1 -> unipolar

        selection         comedi_config option            JUB
         bipolar                0                         2-3 (factory default)
         unipolar               1                         1-2

  option 3: single-ended/differential AI selection: 0 -> SE, 1 -> differential

        selection         comedi_config option     JCHA    JCHB
       single-ended             0                  1-2     1-2 (factory default) 
       differential             1                  2-3     2-3


   written by jeremy theler 

   instituto balseiro
   comision nacional de energia atomica
   universidad nacional de cuyo
   argentina

   21-feb-2008
     + changed supported devices string (missused the [] and ())

   13-oct-2007
     + first try

*/
further information and downloads may be found in the following links.

about almost-dead cards and the meltdown of the 74LS245

as I had to spend a lot of time measuring and dealing with different voltages, I finally managed to destroy the STRIN register located at the 74LS245 integrated circuit with a funny 24V short-circuit (who the hell puts the +12V and -12V references in two adjacent pins???), resulting in the card never setting the end-of-conversion flag properly. Anyway, I modified the driver to wait for a fixed amount of time after launching the ADC, thus reducing the driver performance but at least making it work with an almost-dead card. If you have also melted the 74LS245 (as AFAIK is a common thing that usually happens), please contact me and I will gladly send you the modified driver.

 

non-linear analysis of a stability in a boiling channel

work presented at the 2008 anual meeting of the Argentine Nuclear Technology Association at Buenos Aires.

abstract

El problema termofluidodinámico con flujo en dos fases resulta de particular interés para la tecnología nuclear tanto desde el punto de vista del diseño de reactores avanzados como para la evaluación de transitorios relacionados con estudios de seguridad de centrales nucleares. Es por eso que interesa entender los mecanismos físicos que pueden causar potenciales inestabilidades en el flujo e impactar globalmente sobre la integridad del reactor. Tradicionalmente el estudio de la estabilidad en sistemas de dos fases se realiza utilizando técnicas de lineales de análisis en el dominio de la frecuencia para determinar fronteras de estabilidad en función de parámetros adimensionales, generalmente en el plano del número de subenfriamiento Nsub vs. número de cambio de fase Npch. Por un lado, este tipo de estudios insume un esfuerzo matemático considerable y, por el otro, descarta sistemáticamente efectos no lineales característicos del problema tales como la aparición de ciclos límites estables. Si bien el análisis lineal predice la ocurrencia de bifurcaciones de Hopf en el plano Nsub-Npch causadas por la propagación de ondas de densidad con velocidad finita, nada se puede concluir acerca de lo que sucede en la zona inestable de dicho plano. Por otro lado, el agregado de otras características como un riser adiabático o el acople de varios canales paralelos hace que el análisis de estabilidad deba reformularse completamente. En este trabajo estudiamos la estabilidad de un canal vertical en ebullición aplicando una técnica no lineal de análisis en el dominio temporal. Para una combinación de parámetros dados, resolvemos las ecuaciones de conservación con una condición inicial cercana al equilibrio y, descartando el transitorio inicial, construimos una órbita en un espacio de fases tridimensional. Es posible de esta manera barrer una zona de interés del espacio de parámetros y construir mapas de estabilidad no lineal a partir del cálculo de la dimensión fractal de la órbita resultante para algún subconjunto de parámetros contenidos en el espacio estudiado. Mostramos no sólo que es posible obtener ciclos límite estables sino también que la zona donde éstos existen tiene superficie no nula en el plano Nsub vs. Npch. Estudiamos la influencia de las pérdidas de carga a la entrada y a la salida del canal sobre la estabilidad global y finalmente comparamos la estabilidad de dos canales paralelos idénticos acoplados, con respecto al caso original de un canal individual.

 

on the stability of point kinects equations with feedback

work presented at the 2008 anual meeting of the Argentine Nuclear Technology Association at Buenos Aires.

abstract

Si bien en la mayoría de los casos las ecuaciones de cinética puntual resultan sólo una descripción aproximada del comportamiento temporal de la población neutrónica en el núcleo de un reactor nuclear real, bajo ciertas condiciones bastante generales es posible deducirlas formalmente a partir de la ecuación de transporte de Boltzmann. Por otro lado, estas ecuaciones tienen la particularidad de tener una formulación matemática razonablemente sencilla y a la vez conservar la física básica del problema original. En este trabajo estudiamos la estabilidad de las ecuaciones de cinética puntual desde el punto de vista de la teoría de sistemas dinámicos. Mostramos que sin efectos de realimentación, no es posible obtener una conclusión sobre su estabilidad utilizando herramientas de análisis lineal. Estudiando el problema numéricamente y a partir de argumentos de física de reactores llegamos a la conclusión de que las ecuaciones de cinética puntual sin realimentación poseen un comportamiento poco usual ya que poseen un subespacio invariante compuesto por puntos fijos estables (aunque no asintóticamente) en el sentido de Lyapunov pero que no son estables BIBO. Para incorporar efectos de realimentación interna en la reactividad y estudiar su influencia en la estabilidad global, analizamos un modelo matemático de parámetros concentrados aplicable a un reactor nuclear de investigación. Construimos mapas de estabilidad tanto en el sentido de Lyapunov como BIBO y estudiamos la influencia de las inercias térmicas de los componentes del núcleo y del caudal de refrigeración, llegando a la conclusión que éste último es el parámetro que más influye sobre la importancia relativa entre el coeficiente de reactividad por temperatura del moderador y por temperatura del combustible para la estabilidad del reactor.

 

linguistic fuzzy control of the welander problem in the chaotic regime

work presented at the 2007 anual meeting of the Asociacion Argentina de Tecnologia Nuclear at Buenos Aires. Again, the abstract is available in english, but the full document is only in spanish.

abstract

As natural convection provides an efficient and completely passive heat removal system, natural circulation loops are a matter of great interest in the subject of advanced nuclear reactor design. However, under certain circumstances thermal-fluid-dynamical instabilities may appear, threatening the reactor safety as a whole. On the other hand, fuzzy logic controllers provide and ideal framework to approach highly non-linear control problems. In the present work we introduce the basic ideas of the fuzzy logic theory and analyse the natural convection system known as the the Welander problem, that is one of the simplest configurations of single-phase thermal-hydraulic loops in which chaos actually occurs. Finally, we design a linguistic fuzzy controller that is able to stabilise the circulation flow in conditions that, if the controller was not present, would be otherwise non-periodic unstable.

 

control lingüistico difuso de un loop de conveccion natural caotico

poster presented at the anual ENIEF 2007 meeting on numerical methods and its applications in cordoba. Only in spanish.

poster

 

experimental lorenz chaotic waterwheel poster

this poster was presented in november 2004 in experimental physics I undergraduate course at instituto balseiro. See also the fuzzy control of the Lorenz waterwheel with MELON.

abstract

A version of the lorenzian waterwheel was built, and both its theoretical and experimental behaviour were studied. Therefore, we can assure that the evolution of our wheel ---under certain circumstances--- is, in effect, chaotic.

poster

spanish version

videos & pictures

video 320x240 9.5 mb AVI video
poster presentation poster presentation
at the lab, during the construction the presentation day

waterwheel links

 

other nuclear engineering PDFs

calculo del perfil de fraccion de vacio en un canal calefaccionado utilizando el modelo de drif-flux

en este trabajo estudiamos un canal de ebullicion uniformemente calefaccionado con el modelo de drift-flux. Identificamos que en una aproximacion unidimensional y potencia uniforme, la solucion depende de tres numeros adimensionales y estudiamos como influye cada uno de ellos en el perfil axial de fraccion de vacio. Estudiamos el problema del secado y concluimos que este brusco cambio en la fraccion de vacio depende fuertemente del perfil experimental de drift-flux utilizado. El numero de cambio de fase cambia la posicion axial donde sucede esta discontinuidad y la densidad relativa del vapor tiene influencias de segundo orden.

calculo de la temperatura externa en el silo seco cna I

en el presente trabajo calculamos la temperatura del contenedor exterior del arreglo de treinta y siete elementos combustibles gastados en el silo seco de la Central Nuclear Atucha I, dada la temperatura de la barra central. Para una temperatura central T0 = (155 +-1)C encontramos que la temperatura del contenedor es Tcont = (109+-1)C.

  • calculo de la temperatura externa en el silo seco cna I - junio 2006 - pedir el PDF aqui

estudio de choque termico en cna I

calculamos la distribucion de temperaturas en la inyeccion de un flujo de agua fria en un hipotetico accidente por perdida de refrigerante en el recipiente de presion de la central Atucha I utilizando el modelo teorico propuesto por chen. Observamos el impacto sobre los resultados de diferentes suposiciones y condiciones iniciales.

  • estudio de choque termino en cna I - noviembre 2005 - pedir el PDF aqui

yet another semi-empirical mass formula fit

determinaremos a partir de datos experimentales recientes un conjunto de coeficientes para la formula de weisacker ajustando energias de union por nucleon con minimos cuadrados. Compararemos asi mismo la solucion obtenida con otros resultados hallados anteriormente por otros metodos. Encontramos que la solucion que mejor aproxima los datos es a1 = 15,658, a2 = 17,704, a3 = 0,713, a4 = 19,186 y a5 = 3,734, todos en MeV.

estudio numerico de un pendulo simple

en el presente trabajo resolveremos numericamente las ecuaciones de movimiento de un pendulo simple, y las compararemos con datos experimentales. Asi mismo, modelaremos diferentes mecanismos de disipacion de energia y construiremos diagramas de fase para estas diferentes condiciones de rozamiento.

 

© jeremy theler 2006-2008