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Funder: Knut and Alice Wallenberg Foundation; Id: http://dx.doi.org/10.13039/501100004063, Enzymes are effective biological catalysts that accelerate almost all metabolic reactions in living organisms. Synthetic modulators of enzymes are useful tools for the study of enzymatic reactions and can provide starting points for the design of new drugs. Here, we report on the discovery of a class of biologically active compounds that covalently modifies lysine residues in human liver pyruvate kinase (PKL), leading to allosteric activation of the enzyme (EC50 =0.29 μM). Surprisingly, the allosteric activation control point resides on the lysine residue K282 present in the catalytic site of PKL. These findings were confirmed by structural data, MS/MS experiments, and molecular modelling studies. Altogether, our study provides a molecular basis for the activation mechanism and establishes a framework for further development of human liver pyruvate kinase covalent activators.

Carbohydrate metabolism is the most important energy source for many organisms, and its disorder is involved in a variety of diseases including cancer and diabetes. glucose is metabolized to pyruvate by glycolytic enzymes to produce various metabolites including ATP. Glycolytic enzymes are regulated by specific metabolite as well as various environmental changes to induce metabolic alteration, which are required for adaptation to environmental changes. For example, under an oxidative stress condition, specific glycolytic enzymes are downregulated to change the metabolic flow from glycolysis to a branching pathway, pentose phosphate pathway（PPP）, which is a major source for reduced form of nicotinamide adenine dinucleotide phosphate（NADPH）. NADPH is required for antioxidant enzymes as a proton donor. It is well known that inhibition of glyceraldehyde 3-phosphate dehydrogenase（GAPDH）and pyruvate kinase（PK）activity via oxidation of specific cysteine residues in the enzymes by reactive oxygen species（ROS）are required to suppress the enzyme activity and the resulting glycolytic flow. Such mechanisms are particularly crucial for cancer cell growth. We elucidated a novel regulatory mechanism of glucose metabolism under oxidative stress. These results indicate that oxidative stress and glucose metabolism are closely related and are important for many organisms, from yeast to human. In this review, we will discuss its relationship and present the latest findings.

This thesis studied the performance of the thermal hydraulic software TRACE applied on an intermediate sized break (IB) happening on the cold leg in a pressurized water reactor (PWR), causing a loss-of-coolant accident (LOCA). The same accident has previously been simulated in the PKL Test Facility, which is a scaled version of a PWR and is used to simulate transients stemming from different accidents. The thesis was performed as a semi-blind study: firstly, the accident was simulated without any knowledge of the PKL results. When a final blind model was chosen, the PKL results were revealed, and the TRACE model was improved. Before the simulations of the IB-LOCA took place, the new internal parts in the upper parts of the reactor pressure vessel in PKL had to be modelled, and the steady state had to be tuned to attain the correct initial conditions. The simulations were performed by using the software SNAP together with TRACE, providing a graphical interface. TRACE achieved steady state with satisfying results regarding water levels, pressure losses and mass flows. The temperatures in TRACE deviated from the PKL temperatures but an explanation is uncertainties in PKL. To verify TRACE’s core output power, the calculation of the power was done by using mass flow rate and specific entropy and comparing to the heaters’ specified power. This resulted in lower output power meaning that the coolant was not heated enough. This indicated non-physical energy losses in the TRACE model and should be further investigated.The blind transient simulation, modelled with default choked flow and no offtake model, resulted in TRACE overestimating the break mass flow and the peak cladding temperatures, compared to the PKL reference solution. This resulted in the pressure decreasing too quickly and too early activation of the safety system. The modified simulations showed that it is important that the offtake model, which accounts for different flow regimes, is activated. Default choked flow multipliers were the multipliers that performed the best. However, none of the transient simulations could be completed due to fatal errors and memory problems, but some conclusions could be drawn from the observed trends. This concluded in the offtake model being most important due to stratified flow occurring.

25 p. -- Bibliogr.: p. 22-25 When in classroom contexts, learners tend to experience communication breakdowns which apart from making them believe that they are not making any progress in their Target Language (TL), they lead them to get stuck at some point in their production. In order to cope with these situations, learners usually resort to their Previously Known Languages (PKL). In recent years, the use of these PKL has been studied from two different perspectives, a cognitive and a sociocultural perspective. The cognitive perspective deals with both learning and communication strategies, and the sociocultural perspective is more aimed at exploring the First Language (L1) as a useful tool to assist during collaborative dialogue, which has been demonstrated to mediate Second Language (L2) acquisition (Swain & Lapkin, 2000). This paper provides a review of investigations framed within sociocultural perspectives carried out on different factors that constrain PKL use: task-modality, task repetition, age and proficiency, instructional context and gender. Differences between adults and children have been found in some variables. Regarding task-modality, children seem to resort to their PKL to a higher extent. Furthermore, with respect to PKL functions, whereas adult learners resorted to their PKL to discuss grammar issues in the speaking + writing tasks, grammar talk was not frequent in young learners. In speaking tasks, whereas adults made a greater use of PKL for vocabulary, children resorted to their PKL for this function in equal proportions in both tasks. As for proficiency and age, in general terms, in the case of adults, their need to use their PKL decreases as their proficiency increases. In addition, in the case of children, not only the variable proficiency might affect their use of PKL, but also age. Concerning gender, while investigations targeting adults have found that females make greater use of their PKL, studies dealing with young learners have indicated that males use their PKL to a higher extent. This dissertation finishes with a set of pedagogical implications and identifies where more research should be done.

After the Fukushima accident, “stress-test” activities carried out worldwide pointed out the need to study additional accident management measures to deal with prolonged Station Black Out (SBO) scenarios. Without any operator actions, a total loss of the secondary side heat sink leads to core uncovery, to core damage and ultimately to a melt-down scenario. The international NEA/OECD PKL-3 project has addressed the efficiency of possible accident management actions to re-establish core cooling by experiments at the PKL test facility. Since best estimate system codes were mainly developed to simulate LOCA scenarios, their performance and the general guidelines followed to simulate PWR power plants are called into question. In this paper, RELAP5 simulations of three SBO experiments are presented. An assessment of the code for the particular phenomenology in the experiments have been conducted. Specific guidelines on modelling and a list of the most important sources of uncertainties are provided.

En las últimas décadas ha crecido el número de instalaciones a pequeña escala (test facilities) que permiten reproducir experimentos, situaciones accidentales en las centrales nucleares tomadas como modelo en su diseño. Paralelamente, las bases de datos generadas durante los experimentos se utilizan para la validación de los códigos termohidráulicos empleados en el licenciamiento de los sistemas de seguridad de las centrales nucleares. Dada la importancia de estos códigos, la Organization for Economical Cooperation and Development (OECD) ha promovido diversos proyectos internacionales (OECD-PKL, OECD-ATLAS y OECD-ROSA) orientados al análisis y simulación de secuencias accidentales en reactores nucleares. En este marco, en el Trabajo Fin de Master propuesto se realiza un estudio del calorifugado de la instalación experimental PKL (Primärkreislauf-Versuchsanlage), y su modelado mediante el código termohidráulico TRACE5. Este estudio se realiza a partir de tests de carácter integral y diferencial, documentados en los informes Determination of Thermal Losses in the PKL Test Facility y Determination of Heat Losses in the PKL III Test Facility de Areva y Framatome, respectivamente. En el enfoque integral, se analizan las pérdidas de calor considerando la instalación como dos subsistemas, circuito primario y secundario. En el enfoque diferencial, sólo se considera el circuito primario, el cual se divide en 11 secciones para estudiar las pérdidas de calor locales. Asimismo, en los experimentos se consideran diferentes modos de operación de la planta y un amplio rango de temperaturas del fluido. Estos tests se reproducen mediante un modelo de TRACE5 de la instalación, en el que se caracterizan las pérdidas de calor mediante coeficientes de convección y la geometría de las paredes de los conductos y otros componentes. A partir de los resultados de las simulaciones se desarrolla un único modelo de pérdidas de calor, verificado con valores experimentales de la instalación, y válido para la simulación de transitorios.

[EN] Nuclear power plant risk has to be quantified in full power and in other modes of operation. This latter situation corresponds to low power and shutdown modes of operation in which the residual heat removal (RHR) system is required to extract the heat generated in the core. These accidental sequences are great contributors to the total plant risk. Thus, it is important to analyze the plant behavior to establish the accident mitigation measures required. In this way, PKL facility experimental series were undertaken to analyze the plant behavior in other modes of operation when the RHR is lost. In these experiments, the plant configurations were changed to analyze the influence of steam generators secondary side configurations, the temperature inside the pressurizer, and the inventory level on the plant behavior. Moreover, different accident management measures were proposed in each experiment to reach the conditions to restart the RHR. To understand the physical phenomena that takes place inside the reactor, the experiments are simulated with thermal-hydraulic codes, and this makes it possible to analyze the code capabilities to predict the plant behavior. This work presents the simulation results of four experiments included in PKL experimental series obtained using RELAP5/Mod3.3., This study is part of the work developed by the Polytechnic University of Valencia within a project of the OECD, in which authors are participating under the leadership of the Consejo de Seguridad Nuclear (STN/4524/2015/640). The authors thank PKL III, especially AREVA, program organizers for the information supplied.

[ES] El objetivo de este Trabajo Final de Grado es contribuir a la evaluación del código termohidráulico TRACE para aplicación en reactores nucleares en temas relacionados con la seguridad. Esta contribución se basa particularmente en el análisis del comportamiento transitorio de una instalación experimental en situación de pérdida de potencia exterior (Station Black Out). Se trata de la instalación experimental Primärkreislauf Versuchsanlage (PKL), situada en Alemania. El experimento realizado pertenece al programa PKL III que tiene como objetivo la realización de experimentos termohidráulicos relativos a diseños PWR actuales y avanzados. Dentro de este programa, se encuentra la serie H2 que engloba a accidentes más allá de la base de diseño con calentamiento significativo en el núcleo. El tema principal se centra en evaluar la validez de la simulación del transitorio frente a una base de datos experimentales que cubre todos los procesos termohidráulicos principales, así como el comportamiento de los elementos que componen la instalación. Para lograr este objetivo, se ha modificado un modelo de la instalación PKL con el código termohidráulico TRACE (TRAC/RELAP Advanced Computational Engine). A continuación, se ha realizado la evaluación de los resultados del código a nivel del sistema, es decir, un análisis de la respuesta termohidráulica global de la instalación PKL, comparándolos con los datos experimentales de la prueba realizada en la instalación PKL. Del mismo modo, a lo largo de este trabajo se han estudiado distintas alternativas del modelo en TRACE con el objetivo de realizar un análisis de los fenómenos asociados., [CA] L’objectiu d’aquest Treball Fi de Grau és contribuir a l’avaluació del codi termohidràulic TRACE per a l’aplicació en reactors nuclears en temes relacionats amb la seguretat. Aquesta contribució es basa particularment en l’anàlisi del comportament transitori d’una instal·lació experimental en la situació de pèrdua de potència exterior (Station Black Out). Es tracta de la instal·lació experimental Primärkreislauf Versuchsanlage (PKL), situada a Alemanya. L’experiment realitzat pertany al programa PKL III que te com objectiu la realització d’experiments termohidràulics relatius a dissenys PWR actuals i avançats. Dins d’aquest programa es troba la sèrie H2 que considera accidents més enllà de la base de disseny amb calfament significatiu en el nucli. El tema principal es centra en avaluar la validesa de la simulació del transitori davant d’una base de dades experimentals que continguen tots els processos termohidràulics principals, així com el comportament dels elements que comporten la instal·lació. Per aconseguir aquest objectiu, s’ha modificat un model de la instal·lació PKL amb el codi termohidràulic TRACE (TRAC/RELAP Advanced Computational Engine). Dresprés, s’ha realitzat l’avaluació dels resultats del codi a nivell del sistema, és a dir, una anàlisi de la resposta termohidràulica global de la instal·lació PKL, comparant-los amb les dades del model en TRACE amb l’objectiu de realitzar un anàlisi dels fenòmens associats., [EN] The objective os this essay is to contribute to the evaluation of the thermohydraulic TRACE code for application in nuclear reactors in security related topics. The contribution is based in particular on the analysis of the transient behaviour of a experimental installation in a situation of external power loss (Station Black Out). This is the PKL test facility Primärkreislauf Versuchsanlage (PKL), situated in Erlangen, Germany. The test was carried out by the PKL III program, which aims to conduct thermohydraulic experiments on current and advanced PWR designs. Within this program, there is the H2 series that encompasses accidents beyond the design base with significant core heat-up. The main topic is to evaluate the validity of the transient simulation in front of an experimental daba base that covers all the main thermohydraulic processes, as well as the behaviour of the elementos that make up the installation. To achieve this objective, a model of the PKL test facility with the TRACE (TRAC/RELAP Advanced Computational Engine) has been modified. Next, the evaluation of the results of the code at the system level, ie an analysis of the global thermohidraulic response of the PKL test facility has been carried out, comparing them with the experimental data of the test carried out at the PKL test facility. In the same way, throughout this work have studied different alternatives of the model in TRACE with the objective of performing an analysis of the associated phenomena.

[EN] The Nuclear Energy Agency auspices simulation of experiments in different facilities under several programs. One on them consisted of performing a counterpart test between ROSA/LSTF and PKL facilities, with the main objective of determining the effectiveness of late accident management actions in a small break loss of coolant accident. The results obtained by TRACE code for PKL experiment SBLOCA G7.1 (a scaled model of Konvoi reactor) were in good agreement with the experiments. However, in the simulation process, uncertainty was not accounted. Uncertainty, analysis, following the principles of Best Estimate Plus Uncertainty (BEPU) approach, must be performed to measure the effect of uncertainties on the evolution of safety variables of interest, such as the maximum of the Peak Cladding Temperature (PCTmax) in the experiment. In this paper we present a comparison between two uncertainty analysis techniques. The first technique is based on order statistics that makes use of Wilks' formula. The second technique is based on a Generalized Additive Model (GAM) that substitutes the thermal-hydraulic code, without and with consideration of errors in adjusting the GAM model. The comparison of the uncertainty analysis results makes use of several performance metrics such as coverage, Coefficient of Variation and conservativeness. Based on the results of these metrics it can be concluded that the GAMPE (GAM Plus Error) provides the best performance, in particular, when using small sample size, i.e. n = 59, 93. For larger sample sizes, i.e. n = 124, 153, GAMPE and Wilks' results presents similar performance., This work has been developed partially with the support of Programa de Apoyo a la Investigacion y Desarrollo of UPV (PAID). Authors are grateful to Spanish CSN (Consejo de Seguridad Nuclear) for the financial support of these researches: (Research Project SIN/4078/2013/640; MASA Project) and (Research Project STN/4524/2015/640; CAMP Project).

[EN] The origin of the scaling-issue is the impossibility to obtain measured data in case of an accident in nuclear reactors. The knowledge of thermal hydraulic phenomena oc-curring in Nuclear Power Plants (NPP) during an accident is very important in nuclear safety. As full-scale testing is usually impossible to perform it, thus, a number of small-scale Integral Test Facilities (ITF) of prototype systems have been built to inves-tigate the physical phenomena of transients or possible accidents in NPPs. The design and implementation of these small-scale ITF is performed in the frame of several international projects, among which are the promoted by the Nuclear Safety Council (CSN) and the Organization for Economic Cooperation and Development (OECD) aimed at assimilation, application and improvement of thermalhydraulic codes. Among them, the projects "Analysis and simulation of accidental sequences in PWR reactors. SPAIN CAMP Project" and "Analysis and simulation of the OECD/NEA PKL and OECD/NEA ROSA experiments. Application to the Spanish NPP" are based on a series of experiments in Large Scale Test Facility (LSTF) and Primärkreislauf Versuchsanlage (PKL), both ITF.To analyze the applicability and/or extension of these results to the safety and opera-tion of a generic NPP in this Thesis a methodology applied to the scaling has been developed. This methodology consists of the following points.First, a LSTF model has been developed using the thermalhydraulic code TRACE (TRAC / RELAP Advanced Computational Engine). This model has been used to reproduce different experiments based on Small Break Loss-Of-Coolant Accident (SBLOCA) produced in different locations of the ITF (upper head of the vessel, hot legs, cold legs, etc.). After comparing the simulation results with experimental ones, the differences between both have been analyzed. Furthermore, the special TRACE5 models have been considered to improve the simulation of determined phenomena. With this, a validated LSTF model developed using TRACE5 has been obtained. From the LSTF model, a scaled-up model has been developed applying the volumetric scaling methodology. The use of this methodology is based on the LSTF is a Full-Height, Full- Pressure (FHFP) facility and all the accidents considered are SBLOCA. Under these conditions, the fluid properties are maintained; therefore, it is appropriate to use the volumetric scaling methodology.The same experiments reproduced using the LSTF model have been simulated with the scaled-up model to assess if TRACE5 code is able to well reproduce the same phe-nomenology happening in a small scale facility. The simulation results have been compared with experimental results and those obtained with the LSTF model.Furthermore, trying to study in depth the scaling methodology, a TRACE5 model of the PKL facility has been used to reproduce the counterpart test, which is common to LSTF and PKL facilities. These facilities are not equal in design and operation condi-tions. It allows studying the phenomenology and scaling aspects in systems with dif-ferent design and operation conditions as well as to obtain scaling relations between both facilities., [ES] El origen de la herramienta del escalado en el campo de la seguridad nuclear surge ante la imposibilidad de tener datos reales medidos sobre los fenómenos termohidráu-licos que ocurren en una central nuclear durante un accidente y la importancia del conocimiento de dichos fenómenos. De ahí la necesidad de desarrollar instalaciones que representen determinadas centrales nucleares a pequeña escala donde se puedan reproducir diferentes experimentos. El diseño y la puesta en marcha de dichas instalaciones a pequeña escala se enmarca dentro de diversos proyectos internacionales, entre los que se encuentran los promovi-dos por el Consejo de Seguridad Nuclear (CSN) y la Organización para la Coopera-ción y el Desarrollo Económico (Organisation for Economic Co-operation and Deve-lopment, OECD) encaminados a la asimilación, aplicación y mejora de los códigos termohidráulicos. Entre ellos, los proyectos "Análisis y simulación de secuencias acci-dentales en reactores PWR. Proyecto CAMP ESPAÑA" y "Análisis y simulación de los experimentos OECD/NEA PKL y OECD/NEA ROSA. Aplicación a las CC.NN. españolas". Los proyectos, OECD/NEA PKL y OECD/NEA ROSA, se basan en una serie de experimentos realizados en las instalaciones experimentales a pequeña escala o Integral Test Facilities (ITFs), Large Scale Test Facility (LSTF) y Primärkreislauf Versuchsanlage (PKL).Para analizar la aplicabilidad y/o extensión de estos resultados a la seguridad y opera-ción de una planta genérica en la presente Tesis se ha desarrollado una metodología aplicada al escalado que ha consistido en los siguientes puntos. En primer lugar, se ha desarrollado un modelo de la instalación LSTF con el código termohidráulico TRACE (TRAC/RELAP Advanced Computational Engine) y se han reproducido diferentes experimentos basados en pequeñas roturas con pérdida de refri-gerante o Small Break Loss-Of-Coolant Accident (SBLOCA) que se producen en dife-rentes localizaciones de la instalación (upper head de la vasija, ramas calientes, ramas frías, etc.). Tras comparar los resultados de simulación con los resultados experimenta-les y estudiar los modelos especiales de TRACE para mejorar la simulación de deter-minados fenómenos se han analizado las posibles diferencias existentes y se ha consi-derado el modelo de LSTF como validado. A partir de dicho modelo de LSTF se ha desarrollado un modelo escalado, aplicando la metodología de escalado volumétrico. La utilización de dicha metodología se basa en que la instalación LSTF es una instalación que conserva la misma altura y presión que su central de referencia, Full-Height, Full- Pressure, (FHFP) y los accidentes considerados son SBLOCA. En estas condiciones, el fluido mantiene sus propiedades y, por tanto, resulta adecuada la aplicación de la metodología de escalado volumétrico. Con el modelo escalado se han reproducido los mismos experimentos que con el mo-delo de LSTF con el objetivo de comprobar si el código TRACE5 es capaz de repro-ducir la misma fenomenología que ocurre a pequeña escala. Para ello los resultados de simulación también se han comparado con los resultados experimentales y con los obtenidos con el modelo de LSTF. Además, para profundizar más en la metodología de escalado, se ha utilizado un mo-delo de la instalación PKL con el que se ha reproducido el experimento counterpart, común a las instalaciones LSTF y PKL, que tienen diferentes condiciones de diseño y operación. Esto permite estudiar la fenomenología y aspectos relativos al escalado en instalaciones con diferentes condiciones de diseño y operación, así como obtener las relaciones de escalado entre ambas instalaciones., [CAT] L'origen de l'eina de l'escalat en el camp de la seguretat nuclear sorgeix davant la im-possibilitat de tenir dades reals mesurades sobre els fenòmens termohidràulics que ocorren en una central nuclear durant un accident i la importància del coneixement d'aquests fenòmens. D'ahí la necessitat de desenvolupar instal·lacions que representen determinades centrals nuclears a escala menuda on es puguen reproduir diferents expe-riments. El disseny i la posta en marxa d'aquestes instal·lacions a escala menuda s'emmarca dins de diversos projectes internacionals, entre els quals es troben els que promou el Con-sell de Seguretat Nuclear (CSN) i l'Organització per a la Cooperació i el Desenvolu-pament Econòmic (Organisation for Economic Cooperation and Development, OECD) encaminats a l'assimilació, aplicació i millora dels codis termohidráulics. En-tre ells, els projectes "Anàlisis i simulació de seqüències accidentals en reactors PWR. Projecte CAMP ESPANYA" i "Anàlisi i simulació dels experiments OECD/NEA PKL i OECD/NEA ROSA. Aplicació a les CC.NN. espanyoles". Els projectes, OECD/NEA PKL i OECD/NEA ROSA, es basen en una sèrie d'experiments realitzats en les insta-llacions experimentals a escala menuda o Integral Test Facilities (ITFs), Large Scale Test Facility (LSTF) i Primärkreislauf Versuchsanlage (PKL).Per analitzar l'aplicabilitat i/o extensió d'aquests resultats a la seguretat i operació d'una planta genèrica en la present Tesi s'ha desenvolupat una metodologia aplicada a l'esca-lat que ha consistit en els següents punts. En primer lloc, s'ha desenvolupat un model de la instal·lació LSTF amb el codi ter-mohidráulic TRACE (TRAC/RELAP Advanced Computational Engine) i s'han repro-duït diferents experiments basats en trencaments menuts amb pèrdua de refrigerant o Small Break Loss-Of-Coolant Accident (SBLOCA) que es produeixen en diferents localitzacions de la instal·lació (upper head de l'atuell, branques calentes, branques fredes, etc.). Després de comparar els resultats de simulació amb els resultats experi-mentals i estudiar els models especials de TRACE per millorar la simulació de deter-minats fenòmens s'han analitzat les possibles diferències existents i s'ha consi-deratel model de LSTF com validat. A partir d'aquest model de LSTF s'ha desenvolupat un model escalat, aplicant la meto-dologia d'escalat volumètric. La utilització d'aquesta metodologia es basa en que la instal·lació LSTF és una instal·lació que conserva la mateixa altura i pressió que la seva central de referència, Full-Height, Full-Pressure, (FHFP) i els accidents conside-rats són SBLOCA. En aquestes condicions, el fluid manté les seves propietats i, per tant, resulta adequada l'aplicació de la metodologia d'escalat volumètric. Amb el model escalat s'han reproduït els mateixos experiments que amb el model de LSTF amb l'objectiu de comprovar si el codi TRACE5 és capaç de reproduir la matei-xa fenomenologia que ocorre a escala menuda. Per això els resultats de simulació tam-bé s'han comparat amb els resultats experimentals i amb els obtinguts amb el model de LSTF. A més, per aprofundir més en la metodologia d'escalat, s'ha utilitzat un model de la instal·lació PKL amb el qual s'ha reproduït l'experiment counterpart, comú a les ins-tal·lacions LSTF i PKL, que tenen diferents condicions de disseny i operació. Això permet estudiar la fenomenologia i aspectes relatius a l'escalat en instal·lacions amb diferents condicions de disseny i operació, així com obtenir les relacions d'escalat entre ambdues instal·lacions., Querol Vives, A. (2015). Análisis termohidráulico de la instalación LSTF/ROSA utilizando el código TRACE5. Aportaciones a la metodología de escalado [Tesis doctoral no publicada]. Universitat Politècnica de València. doi:10.4995/Thesis/10251/59445., TESIS

Kawasan Kaki Jembatan Suramadu (KKJS) sisi Surabaya memuat tiga kepentingan pemerintah karena merupakan kawasan strategis nasional, kawasan strategis provinsi, dan kawasan strategis kota. Permasalahan pedagang kaki lima (PKL) di kawasan tersebut disebabkan karena kurangnya sinergi pembagian peran dan wewenang antar pemerintah, termasuk dalam hal perencanaan ruang sehingga membutuhkan kerjasama antar pemerintah. Penelitian ini bertujuan untuk merumuskan model kerjasama perencanaan ruang dalam menangani masalah PKL di kawasan KKJS sisi Surabaya. Identifikasi akar permasalahan PKL menggunakan Root Cause Analysis (RCA) dan content analysis. Content analysis juga digunakan dalam menganalisis model kerjasama perencanaan ruang untuk menangani akar permasalahan PKL. Hasil penelitian menunjukkan bahwa akar permasalahan PKL di KKJS sisi Surabaya adalah kontradiksi regulasi dan kebijakan yang tidak sinkron. Kemudian dapat disusun sebuah model kerjasama yang efektif untuk menangani akar permasalahan tersebut, yaitu model kerjasama perencanaan ruang. Model ini berbentuk perjanjian tertulis (written agreement) dan melibatkan 4 pihak yang bekerjasama yaitu Badan Pengembangan Wilayah Suramadu (BPWS), Badan Perencanaan Pembangunan Daerah (Bappeda) Provinsi Jawa Timur, Badan Perencanaan Pembangunan Kota (Bappeko) Surabaya, dan Badan Khusus Gerbangkertosusila (BK-GKS).

Bacterial spore formation is a complex process of fundamental relevance to biology and human disease. The spore coat structure is complex and poorly understood, and the roles of many of the protein components remain unclear. We describe a new family of spore coat proteins, the bacterial spore kinases (BSKs), and the first crystal structure of a BSK, YtaA (CotI) from Bacillus subtilis. BSKs are widely distributed in spore-forming Bacillus and Clostridium species, and have a dynamic evolutionary history. Sequence and structure analyses indicate that the BSKs are CAKs, a prevalent group of small molecule kinases in bacteria that is distantly related to the eukaryotic protein kinases. YtaA has substantial structural similarity to CAKs, but also displays distinctive features that broaden our understanding of the CAK group. Evolutionary constraint analysis of the protein surfaces indicates that members of the BSK family have distinct clade-conserved patterns in the substrate binding region, and probably bind and phosphorylate distinct targets. Several classes of BSKs have apparently independently lost catalytic activity to become pseudokinases, indicating that the family also has a major noncatalytic function. Proteins 2010. © 2009 Wiley-Liss, Inc.

Penelitian dengan judul “Opini komunitas warga sekitar tentang maraknya Pedagang Kaki Lima (PKL)” ini, dilakukan oleh pengajar/dosen tetap Fakultas Ilmu Komunikasi (FIK). Permasalahan penelitian adalah tentang bagaimana opini komunitas warga sekitar PKL mengenai keamanan, ketertiban, ketenangan, kenyamanan, keindahan, kebersihan, dan keramah-tamahan (7“K”) akibat maraknya PKL. Sasaran strategis dalam penelitian ini adalah komunitas warga di sekitar lingkungan PKL Jalan Kepatihan, Dalem Kaum, dan Tamansari. Tujuan penelitian adalah untuk mengetahui, mengkaji, dan menganalisis faktor 7“K” yang dirasakan komunitas warga sekitar, akibat maraknya PKL, sehingga tanggapan yang diekspresikan mereka dapat menjadi masukan bagi Humas Pemerintah Kota Bandung dalam upaya mensosialisasikan kebijakan pemerintah tentang PKL khususnya dalam merumuskan konsep community relations berkaitan dengan 7 “K” yang dirasakan oleh komunitas warga sekitar terhadap maraknya PKL tersebut. Kesimpulan hasil penelitian ini adalah: pada umumnya opini komunitas warga sekitar terhadap maraknya PKL, dilihat dari faktor 7“K” sangatlah bervariasi di antara opini positif dan negatif, Dalam arti, untuk responden tertentu penilaiannya sangat relatif tergantung dari persepsi masing-masing dan atas dasar pengalaman masing-masing dengan para PKL tersebut. Dengan demikian tidak sepenuhnya berada pada kecenderungan tertentu yang bersifat negatif atau positif. Oleh karena itu dari opini tersebut selanjutnya dapat berkembang untuk diyakini tentang adanya kemungkinan di antara kedua belah pihak saling membina hubungan, dan pemerintah memfasilitasi hubungan tersebut dalam kebijakan-kebijakannya.

Within the pressurized water reactor (PWR) safety analyses, attention has increasingly focused in recent years on boron dilution events that could potentially lead to reactivity transients. Mixing of the low-boron water with the ambient coolant of higher boron content provides an important mitigation mechanism before the low-boron water enters the core.Experimental support is needed to validate the computational tools to be applied to analyze the mixing of the low-boron water. Experiments were performed in the three test facilities - the Upper Plenum Test Facility (UPTF), the Primaerkreislauf (PKL), and the Rossendorf coolant mixing model (ROCOM) - in Germany.The relevant PKL and UPTF tests were focused on small-break loss-of-coolant accident (SBLOCA) scenarios with reflux-condenser mode and restart of natural circulation. The two test facilities represent a typical western-type PWR and are/were operated by Siemens/KWU now Framatome ANP in Germany. While the restart of natural circulation was investigated in the PKL system test facility (volume 1:145, height 1:1), the UPTF experiments dealt with the mixing of water flows with different boron concentration in the cold legs, reactor pressure vessel (RPV) downcomer, and the lower plenum (all these components were full-scale models).The results from the PKL test facility demonstrate that in case ofmore » a postulated SBLOCA with reflux condensation phase, natural circulation does not start up simultaneously in all loops. This means that slugs of condensate, which might have accumulated in the pump seal during reflux-condenser mode of operation, would reach the RPV at different points in time. The UPTF tests showed an almost ideal mixing of water flows with different boron concentration in the RPV downcomer.The ROCOM test facility has been built in a linear scale of 1:5 for the investigation of coolant mixing phenomena in a wide range of flow conditions in the RPV of the German KONVOI-type PWR. The test results presented are focused on the mixing of a slug of deborated water during the startup of the first reactor coolant pump. Based on experimentally determined pulse responses, a semianalytical model for the description of coolant mixing inside the KONVOI RPV has been developed. Calculations for a presumed boron dilution event during the startup of the first reactor coolant pump have been carried out by means of the semianalytical model and independently by means of the computational fluid dynamics code CFX-4. The semianalytical model is able to describe the time dependent behavior of the deboration front at each fuel element position in a good agreement with the experiment. All main mixing effects, observed in the experiment, are also reproduced by the CFX calculation.« less

The objectives of this study to find out the presence of competence and self-confidence of students in Civil Engineering after implementing the practice of fieldwork. The research was conducted at the majoring in civil engineering, Faculty of Engineering, State University of Jakarta in October 2011, the odd semesters (095) academic year 2011 – 2012. This study used a qualitative descriptive method. The population is affordable students of civil engineering who have implementing the practice of fieldwork on semester 095 as many as 130 students. Study sample was 50 students from the existing population was determined using the purposive sampling method. The research instrument is a test to test the competence and questionnaire to test the self-confidence. The scale used is a Gauttman scale and the scale LikertResults of this study is the competence of civil engineering students after implementing the practice of fieldwork to work in the field of building construction has been achieved by 76%. The percentage of each competency indicator variables are cognitive indicators 75%, affective indicator of 94%, and psychomotor indicator 73%. The self-confidence of civil engineering students to work in the field of building construction is also achieved by 77%. The percentage of each self-confidence indicator variable is indicators of self-esteem 74%, indicators of self-afficacy 84%, optimistic indicator of 84%, objective indicator of 94%, and responsibility indicator of 96%.The results of this study was competence and self-confidence of students to work in the field of building construction has been reached on the students after implementing the practice of fieldwork. Competence and self-confidence is the foundation that must be possessed by the student to work in the field of building construction

The small GTPases of the Rho family are intimately involved in integrin-mediated changes in the actin cytoskeleton that accompany cell spreading and motility. The exact means by which the Rho family members elicit these changes is unclear. Here, we demonstrate that the interaction of paxillin via its LD4 motif with the putative ARF-GAP paxillin kinase linker (PKL) (Turner et al., 1999), is critically involved in the regulation of Rac-dependent changes in the actin cytoskeleton that accompany cell spreading and motility. Overexpression of a paxillin LD4 deletion mutant (paxillinΔLD4) in CHO.K1 fibroblasts caused the generation of multiple broad lamellipodia. These morphological changes were accompanied by an increase in cell protrusiveness and random motility, which correlated with prolonged activation of Rac. In contrast, directional motility was inhibited. These alterations in morphology and motility were dependent on a paxillin–PKL interaction. In cells overexpressing paxillinΔLD4 mutants, PKL localization to focal contacts was disrupted, whereas that of focal adhesion kinase (FAK) and vinculin was not. In addition, FAK activity during spreading was not compromised by deletion of the paxillin LD4 motif. Furthermore, overexpression of PKL mutants lacking the paxillin-binding site (PKLΔPBS2) induced phenotypic changes reminiscent of paxillinΔLD4 mutant cells. These data suggest that the paxillin association with PKL is essential for normal integrin-mediated cell spreading, and locomotion and that this interaction is necessary for the regulation of Rac activity during these events.

The present paper deals with the analytical study of the PKL experiment G3.1 performed using the TRACE code (version 5.0 patch1). The test G3.1 simulates a fast cooldown transient, namely, a main steam line break. This leads to a strong asymmetry caused by an increase of the heat transfer from the primary to the secondary side that induces a fast cooldown transient on the primary side-affected loop. The asymmetric overcooling effect requires an assessment of the reactor pressure vessel integrity considering PTS (pressurized thermal shock) and an assessment of potential recriticality following entrainment of colder water into the core area. The aim of this work is the qualification of the heat transfer capabilities of the TRACE code from primary to secondary side in the intact and affected steam generators (SGs) during the rapid depressurization and the boiloff in the affected SG against experimental data. © 2013 Eugenio Coscarelli et al.

Análisis del Ejercicio Counterpart Test en las instalaciones PKL y ROSA. Comparación entre las instalaciones PKL y ROSA y estudio del comportamiento termohidráulico ante el cambio de los coeficientes de descarga en la instalación PKL.

12 páginas, 7 figuras., Dynamic regulation of chromatin structure is of fundamental importance for modulating genomic activities in higher eukaryotes. The opposing activities of Polycomb group (PcG) and trithorax group (trxG) proteins are part of a chromatin-based cellular memory system ensuring the correct expression of specific transcriptional programs at defined developmental stages. The default silencing activity of PcG proteins is counteracted by trxG proteins that activate PcG target genes and prevent PcG mediated silencing activities. Therefore, the timely expression and regulation of PcG proteins and counteracting trxG proteins is likely to be of fundamental importance for establishing cell identity. Here, we report that the chromodomain/helicase/DNA–binding domain CHD3 proteins PICKLE (PKL) and PICKLE RELATED2 (PKR2) have trxG-like functions in plants and are required for the expression of many genes that are repressed by PcG proteins. The pkl mutant could partly suppress the leaf and flower phenotype of the PcG mutant curly leaf, supporting the idea that CHD3 proteins and PcG proteins antagonistically determine cell identity in plants. The direct targets of PKL in roots include the PcG genes SWINGER and EMBRYONIC FLOWER2 that encode subunits of Polycomb repressive complexes responsible for trimethylating histone H3 at lysine 27 (H3K27me3). Similar to mutants lacking PcG proteins, lack of PKL and PKR2 caused reduced H3K27me3 levels and, therefore, increased expression of a set of PcG protein target genes in roots. Thus, PKL and PKR2 are directly required for activation of PcG protein target genes and in roots are also indirectly required for repression of PcG protein target genes. Reduced PcG protein activity can lead to cell de-differentiation and callus-like tissue formation in pkl pkr2 mutants. Thus, in contrast to mammals, where PcG proteins are required to maintain pluripotency and to prevent cell differentiation, in plants PcG proteins are required to promote cell differentiation by suppressing embryonic development., This research was supported by Swiss National Science Foundation (http://www.snf.ch/D/Seiten/default.aspx) grant PP00A-106684/1 to CK, grant 3100AO-116060 to LH, and by the ETH Research Grant (http://www.vpf.ethz.ch/services/TH/index​_EN) TH-12 06-1 to CK.