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Sample records for agua hirviente bwr

  1. Cracks propagation by stress corrosion cracking in conditions of Boiling Water Reactor (BWR); Propagacion de grietas por corrosion bajo esfuerzo en condiciones de reactor de agua hirviente (BWR)

    Energy Technology Data Exchange (ETDEWEB)

    Fuentes C, P

    2003-07-01

    This work presents the results of the assays carried out in the Laboratory of Hot Cells of the National Institute of Nuclear Research (ININ) to a type test tube Compact Tension (CT), built in steel austenitic stainless type 304L, simulating those conditions those that it operates a Boiling Water Reactor (BWR), at temperature 288 C and pressure of 8 MPa, to determine the speed to which the cracks spread in this material that is of the one that different components of a reactor are made, among those that it highlights the reactor core vessel. The application of the Hydrogen Chemistry of the Water is presented (HWC) that is one alternative to diminish the corrosion effect low stress in the component, this is gets controlling the quantity of oxygen and of hydrogen as well as the conductivity of the water. The rehearsal is made following the principles of the Mechanics of Elastic Lineal Fracture (LEFM) that considers a crack of defined size with little plastic deformation in the tip of this; the measurement of crack advance is continued with the technique of potential drop of direct current of alternating signal, this is contained inside the standard Astm E-647 (Method of Test Standard for the Measurement of Speed of Growth of Crack by fatigue) that is the one that indicates us as carrying out this test. The specifications that should complete the test tubes that are rehearsed as for their dimensions, it forms, finish and determination of mechanical properties (tenacity to the fracture mainly) they are contained inside the norm Astm E-399, the one which it is also based on the principles of the fracture mechanics. The obtained results were part of a database to be compared with those of other rehearsals under different conditions, Normal Chemistry of the Water (NWC) and it dilutes with high content of O{sub 2}; to determine the conditions that slow more the phenomena of stress corrosion cracking, as well as the effectiveness of the used chemistry and of the method of

  2. Propagation of cracks by stress corrosion in conditions of BWR type reactor; Propagacion de grietas por corrosion bajo esfuerzo en condiciones de reactor de agua en ebullicion (BWR)

    Energy Technology Data Exchange (ETDEWEB)

    Merino C, F.J. [ININ, 52045 Estado de Mexico (Mexico); Fuentes C, P. [ITT, Metepec, Estado de Mexico (Mexico)]. E-mail: fjmc@nuclear.inin.mx

    2004-07-01

    In this work, the obtained results when applying the Hydrogen Chemistry to a test tube type Compact Tension (CT), built in austenitic stainless steel 304l, simulating the conditions to those that it operates a Boiling Water Reactor (BWR), temperature 288 C and pressure of 8 MPa are presented. With the application of this water chemistry, seeks to be proven the diminution of the crack propagation speed. (Author)

  3. Recent trends in the mitigation of the IGSCC through modifications in the water chemistry of BWR reactors; Tendencias recientes en la mitigacion del IGSCC mediante modificaciones en la quimica del agua de reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Diaz S, A.; Robles, E.F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2003-07-01

    During the last years, the Nuclear Power stations had been that to adequate or to modify the parameters and operational conditions, attempting to maintain and to safeguard the integrity and functionality of its components and systems, as well as the personnel safety involved in its operation. In a Boiling water reactor (BWR), the chemical control of the water, constitutes one of the fundamental aspects to get a sure and reliable operation, having as main objectives: (a) The protection of the reactor vessel, of the structural materials of the same one and of the pipes and components of those recirculation systems against the Intergranular stress corrosion phenomena (IGSCC); (b) To guarantee the integrity of the nuclear fuel minimizing the corrosion phenomena in the fuel elements; and (c) The reduction of the operational dose of the personnel involved directly in the operation and maintenance by means of the control of the activated corrosion products. (Author)

  4. Simulation of the automatic depressurization system (Ads) for a boiling water reactor (BWR) based on RELAP; Simulacion del sistema de despresurizacion automatica (ADS) para un reactor de agua en ebullicion (BWR) basado en RELAP

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez G, C.; Chavez M, C., E-mail: ces.raga@gmail.com [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2012-10-15

    The automatic depressurization system (Ads) of the boiling water reactor (BWR) like part of the emergency cooling systems is designed to liberate the vapor pressure of the reactor vessel, as well as the main vapor lines. At the present time in the Engineering Faculty, UNAM personnel works in the simulation of the Laguna Verde reactor based on the nuclear code RELAP/SCADAP and in the incorporation to the same of the emergency cooling systems. The simulation of the emergency cooling systems began with the inclusion of two hydrodynamic volumes, one source and another drain, and the incorporation of the initiation logic for each emergency system. In this work is defined and designed a simplified model of Ads of the reactor, considering a detail level based on the main elements that compose it. As tool to implement the proposed model, the RELAP code was used. The simulated main functions of Ads are centered in the quick depressurization of the reactor by means of the vapor discharge through the relief/safety valves to the suppression pool, and, in the event of break of the main vapor line, the reduction of the vessel pressure operates for that the cooling systems of the core to low pressure (Lpcs and Lpci) they can begin their operation. (Author)

  5. Mitigation strategies of intergranular corrosion in systems of reactors of water boiling (BWR). Combined action of the chemistry of the hydrogen and the oxygen; Estrategias de mitigacion de la corrosion intergranular en sistemas de reactores de agua en ebullicion (BWR). Accion combinada de la quimica del hidrogeno y del oxigeno

    Energy Technology Data Exchange (ETDEWEB)

    Verdugo, M.

    2015-07-01

    Inter-Granular Stress Corrosion cracking (IGSCC) in austenitic stainless steel and in austenitic nickel-based alloys has been the subject of many studies the aim of which was to resolve one of the main problems faced by BWR nuclear power plants since the 1960s. This corrosion phenomenon is the result of the combined action of three factors: sensitization of the material, high local stresses and an aggressive medium. This paper deals with these factors separately and analyzes the oxidative chemistry of BWR reactors (aggressivity of the medium) as one the main causes if IGSCC. (Author)

  6. Agua(s) remisión de V. nivelador de (las) agua(s).

    OpenAIRE

    2011-01-01

    [ES] Definición del término Agua(s) remisión de V. nivelador de (las) agua(s). en el diccionario Dicter. [EN] Definition of the word Agua(s) remisión de V. nivelador de (las) agua(s). in the dictionary Dicter.

  7. Sector agua

    OpenAIRE

    Mabel Scharfhausen

    2012-01-01

    El agua constituye un recurso esencial para muchos aspectos de la vida humana como son el desarrollo y el bienestar humano. Gracias a los importantes avances en TICs es posible avanzar hacia soluciones que ofrecen una gestión eficiente e integral de los recursos hídricos, proporcionando datos en tiempo real respecto a la calidad, al consumo y la demanda del agua que permiten. Esto, no solamente para tener un mejor control del recurso, sino para hacer seguimiento del mismo y, quizás lo más imp...

  8. Trends in BWR transient analysis

    International Nuclear Information System (INIS)

    While boiling water reactor (BWR) analysis methods for transient and loss of coolant accident analysis are well established, refinements and improvements continue to be made. This evolution of BWR analysis methods is driven by the new applications. This paper discusses some examples of these trends, specifically, time domain stability analysis and analysis of the simplified BWR (SBWR), General Electric's design approach involving a shift from active to passive safety systems and the elimination/simplification of systems for improved operation and maintenance

  9. BWR fuel performance

    International Nuclear Information System (INIS)

    The General Electric experience base on BWR fuel includes over 29,000 fuel assemblies which contain 1,600,000 fuel rods. Over the last five years, design, process and operating changes have been introduced which have had major effects in improving fuel performance. Monitoring this fuel performance in BWRs has been accomplished through cooperative programs between GE and utilities. Activities such as plant fission product monitoring, fuel sipping and fuel and channel surveillance programs have jointly contributed to the value of this extensive experience base. The systematic evaluation of this data has established well-defined fuel performance trends which provide the assurance and confidence in fuel reliability that only actual operating experience can provide

  10. BWR type reactor

    International Nuclear Information System (INIS)

    In a coolant circulation in BWR type reactors, since the mixed stream of steam fluid undergoes a great resistance, the pressure loss due to the flow rate distribution when the coolants flow from the upper plenum into the stand pipe is increased upon passing stand pipe. Also in the spontaneous recycling reactor, pressure loss is still left upon passing the swirling blade of a gas-liquid separator. In view of the above, a plurality of vertical members each having a lower end opened to a gas-liquid two phase boundary and an upper end directly suspended from a steam dryer to the gas-liquid separator. The liquid droplets from the 2-phase boundary heated in the reactor core and formed into a mixed gas-liquid 2-phase stream is directed in the vertical direction accompanied with the steam. The liquid droplets spontaneously fallen by gravity from greater ones successively and the droplets in the steam abutted against the vertical member are fallen as a liquid membrane. Thus, the gas-liquid separation is conducted, the dry steam is directly flown into the steam dryer, thereby capable of providing a gas-liquid separator having gas-liquid separation performance with lower loss than usual. (N.H.)

  11. BWR type nuclear reactor

    International Nuclear Information System (INIS)

    Purpose: To simplify the structure of an emergency core cooling system while suppressing the flow out of coolants upon rapture accidents in a coolant recycling device of BWR type reactors. Constitution: Recirculation pumps are located at a position higher than the reactor core in a pressure vessel, and the lower plenum is bisected vertically by a partition plate. Further, a gas-liquid separator is surrounded with a wall and the water level at the outer side of the wall is made higher than the water level in the inside of the wall. In this structure, coolants are introduced from the upper chamber in the lower plenum into the reactor core, and the steams generated in the reactor core are separated in the gas-liquid separator, whereby the separated liquid is introduced as coolants by way of the inner chamber into the lower chamber of the lower plenum and further sent by way of the outer chamber into the reactor core. Consequently, idle rotation of the recycling pumps due to the flow-in of saturated water is prevented and loss of coolants in the reactor core can also be prevented upon raptures in the pipeway and the driving section of the pump connected to the pressure vessel and in the bottom of the pressure vessel. (Horiuchi, T.)

  12. Development of a computer program of fast calculation for the pre design of advanced nuclear fuel 10 x 10 for BWR type reactors; Desarrollo de un program de computo de calculo rapido para el prediseno de celdas de combustible nuclear avanzado 10 x 10 para reactores de agua en ebullicion

    Energy Technology Data Exchange (ETDEWEB)

    Perusquia, R.; Montes, J.L.; Ortiz, J.J. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)]. e-mail: mrpc@nuclear.inin.mx

    2005-07-01

    In the National Institute of Nuclear Research (ININ) a methodology is developed to optimize the design of cells 10x10 of assemble fuels for reactors of water in boil or BWR. It was proposed a lineal calculation formula based on a coefficients matrix (of the change reason of the relative power due to changes in the enrichment of U-235) for estimate the relative powers by pin of a cell. With this it was developed the computer program of fast calculation named PreDiCeldas. The one which by means of a simple search algorithm allows to minimize the relative power peak maximum of cell or LPPF. This is achieved varying the distribution of U-235 inside the cell, maintaining in turn fixed its average enrichment. The accuracy in the estimation of the relative powers for pin is of the order from 1.9% when comparing it with results of the 'best estimate' HELIOS code. With the PreDiCeldas it was possible, at one minimum time of calculation, to re-design a reference cell diminishing the LPPF, to the beginning of the life, of 1.44 to a value of 1.31. With the cell design with low LPPF is sought to even design cycles but extensive that those reached at the moment in the BWR of the Laguna Verde Central. (Author)

  13. Concesiones de aguas

    Directory of Open Access Journals (Sweden)

    Carlos Labaure Aliseris

    2014-07-01

    Full Text Available El objeto del estudio que nos proponemos realizar es el de las concesiones de aguas.Dicho tema se inscribe en el más amplio de las concesiones en general, y de las concesiones de bienes del dominio público en particular.El estudio especial de las concesiones de aguas se justifica, ya que como en el caso de las demás concesiones sobre bienes del dominio público y privado del Estado, presenta particularidades en su régimen jurídico.El tema planteado fue objeto de nuestro análisis hace unos años, ya que precisamente nuestra tesis para aspirar al título de Profesor Adscripto fue el Código de Aguas, en que uno de los capítulos era el "Uso de las Aguas", que incluía a los permisos y concesiones de uso

  14. Potencial del agua del suelo

    OpenAIRE

    Bustamante Heliodoro

    2012-01-01

    La energía potencial del agua presenta diferencias de un punto del suelo a otro; esas diferencias son las que originan el movimiento del agua de acuerdo a la tendencia universal de la materia en el sentido de moverse de donde la energía potencial es mayor a donde dicha energía es menor. En el suelo el agua en consecuencia se mueve hacia donde su energía decrece hasta lograr su estado de equilibrio. Se desprende entonces que la cantidad de energía potencial absoluta contenida en el agua, no es...

  15. BWR Assembly Optimization for Minor Actinide Recycling

    Energy Technology Data Exchange (ETDEWEB)

    G. Ivan Maldonado; John M. Christenson; J.P. Renier; T.F. Marcille; J. Casal

    2010-03-22

    The Primary objective of the proposed project is to apply and extend the latest advancements in LWR fuel management optimization to the design of advanced boiling water reactor (BWR) fuel assemblies specifically for the recycling of minor actinides (MAs).

  16. Advances in BWR water chemistry

    International Nuclear Information System (INIS)

    This paper reviews recent advances in Boiling Water Reactor (BWR) water chemistry control with examples of plant experiences at U.S. designed BWRs. Water chemistry advances provide some of the most effective methods for mitigating materials degradation, reducing fuel performance concerns and lowering radiation fields. Mitigation of stress corrosion cracking (SCC) of materials remains a high priority and improved techniques that have been demonstrated in BWRs will be reviewed, specifically hydrogen injection combined with noble metal chemical addition (NMCA) and the newer on-line noble metal application process (OLNC). Hydrogen injection performance, an important part of SCC mitigation, will also be reviewed for the BWR fleet, highlighting system improvements that have enabled earlier injection of hydrogen including the potential for hydrogen injection during plant startup. Water chemistry has been significantly improved by the application of pre-filtration and optimized use of ion exchange resins in the CP (condensate polishing) and reactor water cleanup (RWCU) systems. EPRI has monitored and supported water treatment improvements to meet water chemistry goals as outlined in the EPRI BWR Water Chemistry Guidelines, particularly those for SCC mitigation of reactor internals and piping, minimization of fuel risk due to corrosion and crud deposits and chemistry control for radiation field reduction. In recent years, a significant reduction has occurred in feedwater corrosion product input, particularly iron. A large percentage of plants are now reporting <0.1 ppb feedwater iron. The impacts to plant operation and chemistry of lower feedwater iron will be explored. Depleted zinc addition is widely practiced across the fleet and the enhanced focus on radiation reduction continues to emphasize the importance of controlling radiation source term. In addition, shutdown chemistry control is necessary to avoid excessive release of activated corrosion products from fuel

  17. Improvement for BWR operator training

    International Nuclear Information System (INIS)

    BWR Operator Training Center was founded in April, 1971, and in April, 1974, training was begun, since then, 13 years elapsed. During this period, the curriculum and training facilities were strengthened to meet the training needs, and the new training techniques from different viewpoint were developed, thus the improvement of training has been done. In this report, a number of the training techniques which have been developed and adopted recently, and are effective for the improvement of the knowledge and skill of operators are described. Recently Japanese nuclear power stations have been operated at stable high capacity factor, accordingly the chance of experiencing the occurrence of abnormality and the usual start and stop of plants decreased, and the training of operators using simulators becomes more important. The basic concept on training is explained. In the standard training course and the short period fundamental course, the development of the guide for reviewing lessons, the utilization of VTRs and the development of the techniques for diagnosing individual degree of learning were carried out. The problems, the points of improvement and the results of these are reported. (Kako, I.)

  18. Radiactividad en aguas de consumo

    Directory of Open Access Journals (Sweden)

    José Luis Gutiérrez-Villanueva

    2011-12-01

    Full Text Available La directiva europea sobre calidad en el agua potable del año 2003 estableció los límites para los valores de los parámetros radiactivos. Esta directiva europea fue incorporada a la legislación 2003. Los parámetros a analizar son los índices alfa y beta total, el contenido en tritio y la dosis indicativa total. El correspondiente real decreto, en el caso de España, se comenzó a aplicar en el año 2008. No solamente el agua potable procedente de captaciones públicas está sujeta a control, sino que también se deben controlar las aguas comerciales. En ambos casos se han llevado a cabo estudios en todo el mundo. Existe un rango amplio de técnicas para la medida de la radiactividad en el agua de consumo. Este artículo describe tales técnicas e indica cuando se debe aplicar cada una de ellas. Por último, se muestran los resultados más importantes obtenidos tras el análisis de aguas potables y comerciales, tanto en aguas españolas como de fuera de España. Los resultados muestran que se superan los límites en algunos casos y por lo tanto se debe prestar especial atención a fin de reducir los niveles de radiactividad en las aguas potables todo lo posible.

  19. 44-BWR WASTE PACKAGE LOADING CURVE EVALUATION

    International Nuclear Information System (INIS)

    The objective of this calculation is to evaluate the required minimum burnup as a function of initial boiling water reactor (BWR) assembly enrichment that would permit loading of spent nuclear fuel into the 44 BWR waste package configuration as provided in Attachment IV. This calculation is an application of the methodology presented in ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003). The scope of this calculation covers a range of enrichments from 0 through 5.0 weight percent (wt%) U-235, and a burnup range of 0 through 40 GWd/MTU. This activity supports the validation of the use of burnup credit for commercial spent nuclear fuel applications. The intended use of these results will be in establishing BWR waste package configuration loading specifications. Limitations of this evaluation are as follows: (1) The results are based on burnup credit for actinides and selected fission products as proposed in YMP (2003, Table 3-1) and referred to as the ''Principal Isotopes''. Any change to the isotope listing will have a direct impact on the results of this report. (2) The results of 100 percent of the current BWR projected waste stream being able to be disposed of in the 44-BWR waste package with Ni-Gd Alloy absorber plates is contingent upon the referenced waste stream being sufficiently similar to the waste stream received for disposal. (3) The results are based on 1.5 wt% Gd in the Ni-Gd Alloy material and having no tuff inside the waste package. If the Gd loading is reduced or a process to introduce tuff inside the waste package is defined, then this report would need to be reevaluated based on the alternative materials

  20. Ciclo cósmico del agua

    OpenAIRE

    Martínez-Frías, J.

    2008-01-01

    1 página.-- Trabajo presentado en la Exposición Internacional "Agua y Desarrollo Sostenible" celebrada en Zaragoza del 14 de Junio al 14 de septiembre del 2008 (Pabellón: Torre del Agua. Agua para la vida).

  1. EPRI BWR Water Chemistry Guidelines Revision

    International Nuclear Information System (INIS)

    BWRVIP-190: BWR Water Chemistry Guidelines – 2008 Revision has been revised. The revision committee consisted of U.S. and non-U.S. utilities (members of the BWR Vessel and Internals Protection (BWRVIP) Mitigation Committee), reactor system manufacturers, fuel suppliers, and EPRI and industry experts. The revised document, BWRVIP-190 Revision 1, was completely reformatted into two volumes, with a simplified presentation of water chemistry control, diagnostic and good practice parameters in Volume 1 and the technical bases in Volume 2, to facilitate use. The revision was developed in parallel and in coordination with preparation of the Fuel Reliability Guidelines Revision 1: BWR Fuel Cladding Crud and Corrosion. Guidance is included for plants operating under normal water chemistry (NWC), moderate hydrogen water chemistry (HWC-M), and noble metal application (GE-Hitachi NobleChem™) plus hydrogen injection. Volume 1 includes significant changes to BWR feedwater and reactor water chemistry control parameters to provide increased assurance of intergranular stress corrosion cracking (IGSCC) mitigation of reactor materials and fuel reliability during all plant conditions, including cold shutdown (≤200°F (93°C)), startup/hot standby (>200°F (93°C) and ≤ 10%) and power operation (>10% power). Action Level values for chloride and sulfate have been tightened to minimize environmentally assisted cracking (EAC) of all wetted surfaces, including those not protected by hydrogen injection, with or without noble metals. Chemistry control guidance has been enhanced to minimize shutdown radiation fields by clarifying targets for depleted zinc oxide (DZO) injection while meeting requirements for fuel reliability. Improved tabular presentations of parameter values explicitly indicate levels at which actions are to be taken and required sampling frequencies. Volume 2 provides the technical bases for BWR water chemistry control for control of EAC, flow accelerated corrosion

  2. Crud deposition modeling on BWR fuel rods

    International Nuclear Information System (INIS)

    Deposition of boiling water reactor (BWR) system corrosion products (crud) on operating fuel rods has resulted in performance-limiting conditions in a number of plants. The operational impact of performance-limiting conditions involving crud deposition can be detrimental to a BWR operator, resulting in unplanned or increased frequency of fuel inspections, fuel failure and associated radiological consequences, operational restrictions including core power derate and/or forced shutdowns to remove failed fuel, premature discharge of individual bundles or entire reloads, and/or undesirable core design restrictions. To facilitate improved management of crud-related fuel performance risks, EPRI has developed the CORAL (Crud DepOsition Risk Assessment ModeL) tool. This paper presents a summary of the CORAL elements and benchmarking results. Applications of CORAL as a tool for fuel performance risk assessment are also discussed. (author)

  3. The design of large natural circulation BWR's

    International Nuclear Information System (INIS)

    Boiling water reactors (BWR) with natural circulation are applied for capacities up to 60 MWe. Based on scale studies, however, it appears that larger production units are more efficient. It is recommended to investigate the bottlenecks in realizing larger reactors (>1000 MWe). The aim of the study on the title subject is to study to what extent the production capacity of BWRs with natural circulation can be increased. Based on data from the literature a simple analytic method has been chosen and existing BWR designs were compared. Capacities of 1300 MWe appear to be possible. These reactors will have a smaller pin diameter and a lower water supply temperature. Also steam separators with a minor pressure reduction must be available. The reliability of the stability measurement must be increased. Based on the results of this investigation the priorities for research on the design of future BWRs have been determined

  4. BWR radiation buildup control with ionic zinc

    International Nuclear Information System (INIS)

    In 1983 a hypothesis was disclosed which suggested that the presence of ionic zinc in the reactor water of the BWR could reduce radiation buildup. This hypothesis was developed from correlations of plant data, and subsequently, from laboratory experiments which demonstrated clearly that ionic zinc inhibits the corrosion of stainless steel. The benefits of zinc addition have been measured at the Vallecitos Nuclear Center under and EPRI/GE project. Experimentation and analyses have been performed to evaluate the impact of intentional zinc addition on the IGSCC characteristics of primary system materials and on the performance of the nuclear fuel. It has been concluded that no negative effects are expected. The author conclude that the intentional addition of ionic zinc to the BWR reactor water at a concentration of approximately 10 ppb will provide major benefits in controlling the Co-60 buildup on primary system stainless steel surfaces. The intentional addition of zinc is now a qualified technique for use in BWRs

  5. Recent developments in BWR water chemistry

    International Nuclear Information System (INIS)

    Water chemistry is of critical importance to the operation and economic viability of the Boiling Water Reactor (BWR). A successful water chemistry program will satisfy the following goals: - Minimize the incidence and growth of SCC/IASCC, - Minimize plant radiation fields controllable by chemistry, -Maintain fuel integrity by minimizing cladding corrosion, - Minimize flow-accelerated corrosion (FAC) in balance-of-plant components. The impact of water chemistry on each of these goals is discussed in more detail in this paper. It should be noted that water chemistry programs also include surveillance and operating limits for other plant water systems (e.g., service water, closed cooling water systems, etc.) but these are out of the scope of this paper. This paper reviews developments in water chemistry guidelines for U.S. BWR nuclear power plants. (author). 2 figs., 2 tabs., 7 refs

  6. a considerar. II. Aguas residuales urbanas

    Directory of Open Access Journals (Sweden)

    Fernando Ortega Sastriques

    2007-01-01

    Full Text Available El precio del agua potable es elevado y en muchas ciudades su disponibilidad está limitada y disminuirá en el futuro. La agricultura urbana es una concurrente en el uso del agua, en el futuro es muy probable que haya fuertes limitaciones para el riego con agua potable. Así es que para la producción de vegetales en medio urbano será necesario el empleo de agua de fuentes alternativas y no de los acueductos. Por lo general, el agua del subsuelo en el entorno de las ciudades, así como las corrientes superficiales está contaminada. En este trabajo se señalan los aspectos a tomar en cuenta para el riego seguro con aguas residuales, incluyendo las aguas albañales.

  7. Decontamination techniques for BWR power generation plant

    International Nuclear Information System (INIS)

    The present report describes various techniques used for decontamination in BWR power generation plants. Objectives and requirements for decontamination in BWR power plants are first discussed focusing on reduction in dose, prevention of spread of contamination, cleaning of work environments, exposure of equipment parts for inspection, re-use of decontaminated resources, and standards for decontamination. Then, the report outlines major physical, chemical and electrochemical decontamination techniques generally used in BWR power generation plants. The physical techniques include suction of deposits in tanks, jet cleaning, particle blast cleaning, ultrasonic cleaning, coating with special paints, and flushing cleaning. The chemical decontamination techniques include the use of organic acids etc. for dissolution of oxidized surface layers and treatment of secondary wastes such as liquids released from primary decontamination processes. Other techniques are used for removal of penetrated contaminants, and soft and hard cladding in and on equipment and piping that are in direct contact with radioactive materials used in nuclear power generation plants. (N.K.)

  8. Agua Caliente and Their Music.

    Science.gov (United States)

    Ryterband, Roman

    1979-01-01

    Discusses the traditional music of the Agua Caliente band of California's Desert Cahuilla Indian tribe, including accompanying instruments, types of songs, thematic material, and performance routines. Exploring the structure of the music, the article describes meter, tempo, harmony and tonal gravitations, and use of words. (DS)

  9. Túnel bajo el agua

    Directory of Open Access Journals (Sweden)

    Stamhuis, E.

    1964-03-01

    Full Text Available This article describes the results obtained by the Dutch Central Institute of Scientific Research when studying the problem of underwater tunnels. This Institute has sought to establish general specifications for the design of this type of tunnels, so that they shall be more efficient than those at present in use. Firstly, a study was made of the strength, waterproof qualities, and most rational type of ventilation, with a view to drawing up of general principles on this aspect of the design. An analysis is given of the shape, suitable cross sections and constructive methods, and these are compared with those adopted in the construction of underwater tunnels at present in use in America. Particular attention has been given to designs which are largely based on prefabrication and the use of factory made structural parts, and also on the transport and erection of these at the site. The author goes on to discuss the interplay of soil and water pressures, buoyancy forces, and cases in which the tunnel is subjected to important bending and shear forces on particular sections of it. In this connection care is taken to give the theoretical considerations a ready practical interpretation. In particular, a description is given of special distance pieces which connect the two tubes making up a tunnel, also the system of joining two sections of the tube, and the measure of watertightness and flexibility which such joints provide. Finally, a summary is given of the theoretical foundations, as well as a number of observations and items of advise, which are applicable to these types of structures.El ingeniero A. Eggink describió, en un trabajo publicado últimamente, un nuevo tipo de túnel bajo el agua para canalizar la circulación rodada. En este trabajo se desarrolla un análisis sobre las consideraciones que han jugado un papel predominante en la redacción del proyecto de ejecución de un túnel subacuo. Acompañan al trabajo los resultados referentes

  10. Investigation of burnup credit implementation for BWR fuel

    International Nuclear Information System (INIS)

    Burnup Credit allows considering the reactivity decrease due to fuel irradiation in criticality studies for the nuclear fuel cycle. Its implementation requires to carefully analyze the validity of the assumptions made to define the axial profile of the burnup and void fraction (for BWR), to determine the composition of the irradiated fuel and to compute the criticality simulation. In the framework of Burnup Credit implementation for BWR fuel, this paper proposes to investigate part of these items. The studies presented in this paper concern: the influence of the burnup and of the void fraction on BWR spent fuel content and on the effective multiplication factor of an infinite array of BWR assemblies. A code-to-code comparison for BWR fuel depletion calculations relevant to Burnup Credit is also performed. (authors)

  11. El agua y el arte

    Directory of Open Access Journals (Sweden)

    Chueca Goitia, Fernando

    1999-10-01

    Full Text Available Not available.En el artículo «El agua y el arte» se analiza la importancia que tiene el agua en el mundo del arte, a través de los jardines y sus muchas variedades. El autor se refiere luego a los diversos aspectos que tienen el jardín francés, el jardín inglés, y el jardín español, de acuerdo con su geografía, pluviometría y cultura propias. El jardín español de abolengo musulmán es el jardín de los países secos que atesoran el agua como bien precioso, porque no lo regala la naturaleza y es necesario transportarlo y encerrarlo en el cofre de una arquitectura sugerente. Por eso el jardín español es un jardín recoleto y misterioso, enclaustrado y secreto, sin lejanías ni perspectivas. Se extiende luego el autor en los jardines de la Alhambra granadina, sin olvidar otros, principalmente andaluces. Jardines de los claustros monacales, de El Escorial y de los Sitios reales, también interesan, en suma, al articulista.

  12. LBB application in Swedish BWR design

    Energy Technology Data Exchange (ETDEWEB)

    Kornfeldt, H.; Bjoerk, K.O.; Ekstroem, P. [ABB Atom, Vaesteras (Sweden)

    1997-04-01

    The protection against dynamic effects in connection with potential pipe breaks has been implemented in different ways in the development of BWR reactor designs. First-generation plant designs reflect code requirements in effect at that time which means that no piping restraint systems were designed and built into those plants. Modern designs have, in contrast, implemented full protection against damage in connection with postulated pipe breaks, as required in current codes and regulations. Moderns standards and current regulatory demands can be met for the older plants by backfitting pipe whip restraint hardware. This could lead to several practical difficulties as these installations were not anticipated in the original plant design and layout. Meeting the new demands by analysis would in this situation have great advantages. Application of leak-before-break criteria gives an alternative opportunity of meeting modem standards in reactor safety design. Analysis takes into account data specific to BWR primary system operation, actual pipe material properties, piping loads and leak detection capability. Special attention must be given to ensure that the data used reflects actual plant conditions.

  13. A BWR licensing experience in the USA

    International Nuclear Information System (INIS)

    The US-Advanced Boiling Water Reactor (A BWR), certified by the United States Nuclear Regulatory Commission (US NRC), is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (STP3-4) Combined License Application (Cola). Nuclear Innovation North America (Nina) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. The STP3-4 project has finished the US NRC technical review of the Cola through the final meeting of the Advisory Committee on Reactor Safeguards (ACRS), and the Final Safety Evaluation Report (FSER) is scheduled to be issued by the US NRC in the middle of 2015. The next steps are to support the Mandatory Hearing process, and voting by the NRC commissioners on the motion to grant the Combined License, which is scheduled beginning of 2016 according to US NRC schedule as of March 30, 2015. This paper summarizes the history and progress of the US-A BWR licensing, including the experiences of the Licensee, Nina, and Toshiba as the Epc team worked through the Code of Federal Regulations Title 10 (10-Cfr) Part 52 process, and provides some perspectives on how the related licensing material would also be of value within a 10-Cfr Part 50, two-step process to minimize schedule and financial risks which could arise from ongoing technical developments and regulatory reviews. (Author)

  14. A BWR licensing experience in the USA

    Energy Technology Data Exchange (ETDEWEB)

    Powers, J.; Ogura, C. [Toshiba America Nuclear Energy, Charlotte, North Carolina (United States); Arai, K. [Toshiba Corporation, Yokohama, Kanagawa (Japan); Thomas, S.; Mookhoek, B., E-mail: jim.powers@toshiba.com [Nuclear Innovation North America, Lake Jackson, Texas (United States)

    2015-09-15

    The US-Advanced Boiling Water Reactor (A BWR), certified by the United States Nuclear Regulatory Commission (US NRC), is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (STP3-4) Combined License Application (Cola). Nuclear Innovation North America (Nina) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. The STP3-4 project has finished the US NRC technical review of the Cola through the final meeting of the Advisory Committee on Reactor Safeguards (ACRS), and the Final Safety Evaluation Report (FSER) is scheduled to be issued by the US NRC in the middle of 2015. The next steps are to support the Mandatory Hearing process, and voting by the NRC commissioners on the motion to grant the Combined License, which is scheduled beginning of 2016 according to US NRC schedule as of March 30, 2015. This paper summarizes the history and progress of the US-A BWR licensing, including the experiences of the Licensee, Nina, and Toshiba as the Epc team worked through the Code of Federal Regulations Title 10 (10-Cfr) Part 52 process, and provides some perspectives on how the related licensing material would also be of value within a 10-Cfr Part 50, two-step process to minimize schedule and financial risks which could arise from ongoing technical developments and regulatory reviews. (Author)

  15. Dynamic analysis of BWR scram reactivity characteristics

    International Nuclear Information System (INIS)

    An extensive study of BWR scram reactivity behavior is presented. It is based on a space-time analysis of a BWR/4 code using the two-dimensional (R, Z) dynamics code BNL-TWIGL which includes a two-phase thermal-hydraulic model. Calculations were made of the sensitivity of scram to physical quantities such as initial control rod position and power distribution, scram speed, system pressure and varying inlet flow rate and temperature. The end-of-cycle Haling operating condition was found to give rise to the limiting scram reactivity function. Even with scram a power surge was found to be possible with severely decreasing inlet temperature. Calculations were also made to find the effect on scram of commonly used modeling approximations. These included the effect of neglecting delayed neutrons (conservative), using a time invariant void distribution (non-conservative) and defining point kinetics parameters such as reactivity, amplitude function and generation time in terms of different weighting functions. The importance of defining point kinetics parameters consistent with their use in plant transient analyses was demonstrated with particular emphasis on the role of ''residual reactivity''

  16. Vibration characteristics of BWR primary containment vessel

    International Nuclear Information System (INIS)

    This paper reports on a part of a seismic proving test of a BWR Primary Containment Vessel (PCV), a vibration analysis that is carried out considering the effect of reinforcement around attached masses such as equipment hatches and a personnel airlock. A deflected shape with the local attached masses and reinforcement is expanded using free vibration modes of an axisymmetric PCV without attached masses and reinforcement. The free vibration modes are calculated considering a coupling effect between the PCV shell and suppression pool water using conical shell finite elements and ring fluid elements. The same expanding functions and free vibration modes are used to express strain energy, kinetic energy and work done by inertia forces due to input acceleration considering locally varying thickness of the PCV and attached masses. The equations of motion are obtained by substituting the strain energy, kinetic energy, and work done by inertia forces into the Lagrange's equation. Calculated natural frequencies, free vibration modes and frequency response functions are compared with numerical results obtained by a general shell finite element analysis and with test results using the large-scale high-performance vibration table of Tadotsu Engineering Laboratory, Nuclear Power Engineering Test Center (NUPEC). The comparison shows a reasonable agreement, leading to better understanding of the dynamic characteristics of the BWR PCV

  17. Thermal aging evaluation of casting stainless steel under BWR environment

    International Nuclear Information System (INIS)

    Effect of thermal aging under BWR condition on material properties of casting stainless steel were evaluated by such as Charpy impact test, using replaced BWR component material. Solution heat treatment was performed to the same material and the material properties were obtained. Comparing each material test results, impact value of thermal aging material was lower than solution heat treatment material. By the results, thermal aging effect on material properties under BWR condition was confirmed. The material properties were compared with model equation using PLM evaluation and conservativeness of model equation was confirmed. (author)

  18. a considerar. I. Aguas salinas o alcalinas

    Directory of Open Access Journals (Sweden)

    Fernando Ortega Sastriques

    2007-01-01

    Full Text Available El precio del agua potable es elevado y en muchas ciudades su disponibilidad está limitada y disminuirá en el futuro. La agricultura urbana es una concurrente en el uso del agua. En el futuro es muy probable que haya fuertes limitaciones para el riego con agua potable. Así es que para la producción de vegetales en medio urbano será necesario el empleo de agua de fuentes alternativas y no de los acueductos. La extracción de agua del manto freático para el riego es una práctica común que se incrementará en el futuro previsible. Casi todas las grandes urbes de Cuba tienen costas, es frecuente que los acuíferos subterráneos de estas ciudades presenten algún contenido de fácil solubilidad; o bien en otras ciudades interiores el agua puede ser alcalina. El riego con estos tipos de agua deprimen los rendimientos y pueden dañar los suelos y substratos. En este artículo se explican los aspectos que deben considerarse para poder emplear esta agua con seguridad.

  19. AGUA TIBIA PRIMITIVE AREA, CALIFORNIA.

    Science.gov (United States)

    Irwin, William P.; Thurber, Horace K.

    1984-01-01

    The Agua Tibia Primitive Area in southwestern California is underlain by igneous and metamorphic rocks that are siilar to those widely exposed throughout much of the Peninsular Ranges. To detect the presence of any concealed mineral deposits, samples of stream sediments were collected along the various creeks that head in the mountain. As an additional aid in evaluating the mineral potential, an aeromagnetic survey was made and interpreted. A search for records of past or existing mining claims within the primitive area was made but none was found. Evidence of deposits of metallic or nonmetallic minerals was not seen during the study.

  20. El abastecimiento de agua a Cartagena

    Directory of Open Access Journals (Sweden)

    Miguel Borja Bernabé Crespo

    2015-01-01

    Full Text Available La escasez de agua en la región del sureste peninsular, en la que se ubica Cartagena y su comarca,ha obligado a buscar y traer recursos foráneos de agua para atender sus necesidades de abastecimiento.Inicialmente, al no existir cursos permanentes de agua, se recurre a pozos y aljibes, apequeños acueductos desde fuentes y manantiales de aforo escaso, y a alumbramientos de subálveasmediante galerías con lumbreras. Las demandas aumentan y se plantea la traída de aguas dela parte alta de la Cuenca del Segura. Mediante las infraestructuras de la Mancomunidad de losCanales del Taibilla (MCT, creada por Decreto Ley de 4 de octubre de 1927 llega el agua hastaCartagena en 1945. En los últimos treinta y cinco años, a estas aguas se han unido caudales delTrasvase Tajo-Segura y finalmente aguas procedentes de desaladoras. La gestión del abastecimientode agua, a lo largo de la historia de Cartagena (desde la fundación de Carthago Nova enel 229 a.C. hasta los primeros años del siglo XXI ha generado un rico patrimonio de infraestructurashidráulicas y una experimentada cultura de usos del agua.Se expone la situación del abastecimiento de Cartagena (ciudad y barrios como demandante derecursos propios y foráneos de agua. La inversión en las redes de distribución y la concienciaciónde la mayor parte de los usuarios en un uso sostenible, que permiten un continuado abastecimientode «agua de boca», así como la regeneración de las aguas residuales para otros usos. Eneste trabajo geográfico (espacial e histórico (diacrónico, las fuentes utilizadas han sido las entrevistasa los gestores de las empresas encargadas de la distribución del agua en alta (conduccionesde gran diámetro como las de la MCT y en baja (conducciones de pequeño diámetro como las deHIDROGEA, y el acceso a la documentación del Archivo Municipal de Cartagena, del Regionalde Murcia, de la Mancomunidad de Canales del Taibilla, y el de la Confederación Hidrográficadel Segura

  1. Transportation activities for BWR fuels at NFI

    International Nuclear Information System (INIS)

    Nuclear Fuel Industries, LTD. (NFI) supplies fuel assemblies for both PWR and BWR in Japan. We can also manage transportation of the fuel assemblies from our fabrication facilities to the nuclear power plants of Japanese utilities. For the transportation of fuel assembly, we designed and fabricated the transportation containers to meet the requirements of the IAEA regulations, and licensed in Japan. This paper introduced the recent activity and R and D of NFI concerning transportation of BWR fuel assembly. NT-XII transportation container was developed for fresh BWR fuel assemblies. NT-XII container consists of inner container and outer container. Two BWR fuel assemblies with up to 5 wt.-% 235-U enriched are enclosed in an inner container. In the concept of NT-XII container design, we made the best priority to transportation efficiency, as well as ensuring fuel integrity during transportation. NT-XII has been used since 2002 in Japan. Thanks to the lightening weight of containers, the number of containers to be loaded to one transportation truck was increased up to 9 containers (equivalent to 18 fuel assemblies) compared with former type container (NT-IV transportation container) which can be loaded up to 6 containers (equivalent to 12 fuel assemblies). In addition to the design of brand-new container, we promote the improvement of the packaging methods. In Japan, in order to reduce the damage to the fuel rod and fuel spacer while transporting, polyethylene sleeves which are called 'packing separators' are inserted in the rod-to-rod gap of fuel assembly. However, packing separators requires time and cost for the installation at fuel fabrication facility. In the same way, huge time and cost are needed for removal of packing separators at nuclear power plant. For the improvement of preparation efficiency before and after transportation, we investigated the influence of vibration to fuel integrity in case of transportation without packing separators. Based on the above

  2. BWR stability using a reduced dynamical model

    International Nuclear Information System (INIS)

    BWR stability can be treated with reduced order dynamical models. When the parameters of the model came from experimental data, the predictions are accurate. In this work an alternative derivation for the void fraction equation is made, but remarking the physical struct-ure of the parameters. As the poles of power/reactivity transfer function are related with the parameters, the measurement of the poles by other techniques such as noise analysis will lead to the parameters, but the system of equations in non-linear. Simple parametric calculat-ion of decay ratio are performed, showing why BWRs become unstable when they are operated at low flow and high power. (Author). 7 refs

  3. Improvement of BWR radioactive waste disposal system

    International Nuclear Information System (INIS)

    Description is made here about the improvement of the disposal systems for liquid and solid radioactive waste in recent BWR plants. Regarding the improvement of liquid waste disposal systems in Toshiba, emphasis was laid on crud removal and laundry drain treatment; as a result, a crud removal system utilizing a centrifugal separation mechanism and an evaporative enriching system using anti-foaming agent have been practicalized. An important problem left for solution is the method of volume reduction of solid waste. A method attracting attention of late is the plastic solidification which is far superior to the conventional cement and bitumen solidification. In Toshiba, this method is promising to be practicalized, in which the waste is dried and then solidified with thermosetting resin. (author)

  4. Manufacturing technology and process for BWR fuel

    International Nuclear Information System (INIS)

    Following recent advanced technologies, processes and requests of the design changes of BWR fuel, Nuclear Fuel Industries, Ltd. (NFI) has upgraded the manufacturing technology and honed its own skills to complete its brand-new automated facility in Tokai in the latter half of 1980's. The plant uses various forms of automation throughout the manufacturing process: the acceptance of uranium dioxide powder, pelletizing, fuel rod assembling, fuel bundle assembling and shipment. All processes are well computerized and linked together to establish the integrated control system with three levels of Production and Quality Control, Process Control and Process Automation. This multi-level system plays an important role in the quality assurance system which generates the highest quality of fuels and other benefits. (author)

  5. BWR startup and shutdown activity transport control

    International Nuclear Information System (INIS)

    This paper summarizes BWR industry experience on good practices for controlling the transport of corrosion product activity during shutdowns, particularly refueling outages, and for startup chemistry control to minimize IGSCC (intergranular stress corrosion cracking). For shutdown, overall goals are to minimize adverse impacts of crud bursts and the time required to remove activated corrosion products from the reactor coolant during the shutdown process prior to refueling, and to assist plants in predicting and controlling radiation exposure during outages. For startup, the overall goals are to highlight conditions during early heatup and startup when sources of reactor coolant oxidants are high, when there is a greater likelihood for chemical excursions associated with refueling outage work activities, and when hydrogen injection is not available to mitigate IGSCC due to system design limitations. BWR water chemistry has changed significantly in recent years with the adoption of hydrogen water chemistry, zinc addition and noble metal chemical applications. These processes have, in some instances, resulted in significant activity increases during shutdown evolutions, which together with reduced time for cleanup because of shorter outages, has consequently increased outage radiation exposure. A review several recent outages shows that adverse effects from these conditions can be minimized, leading to the set of good practice recommendations for shutdown chemistry control. Most plants lose the majority of their hydrogen availability hours during early startup because feedwater hydrogen injection systems were not originally designed to inject hydrogen below 20% power. Hydrogen availability has improved through modifications to inject hydrogen at lower power levels, some near 5%. However, data indicate that IGSCC is accelerated during early startup, when dissolved oxygen and hydrogen peroxide levels are high and reactor coolant temperatures are in the 300 to 400 oF (

  6. Calidad del agua potable en Huesca

    OpenAIRE

    Sancho Arroyo, Sandra; Pablo Aranda, Miriam

    2010-01-01

    El agua es uno de los recursos naturales fundamentales; es, seguramente el recurso que condiciona de manera prioritaria el desarrollo socioeconómico de los pueblos y la mejora del bienestar de la población. El agua presta un extraordinario servicio a la comunidad para mejorar su calidad de vida, pero, sobre todo, para satisfacer sus necesidades básicas, tales como la alimentación y la salud. Sin agua no son posibles las actividades agropecuarias y, especialmente, las agrícolas, que son el may...

  7. Advanced Construction of Compact Containment BWR

    International Nuclear Information System (INIS)

    The reactor concept considered in this paper has a mid/small power output, a compact containment and a simplified BWR configuration with comprehensive safety features. Compact Containment BWR (CCR) is being developed with matured BWR technologies together with innovative systems/components, will provide attractiveness for the energy market in the world due to its flexibility in energy demands as well as in site conditions, its high potential in reducing investment risk and its safety feature facilitating public acceptance. The flexibility is achieved by CCR's mid/small power output of 400 MWe class and capability of long operating cycle (refueling intervals). The high investment potential is expected from CCR's simplification/innovation in design such as natural circulation core cooling with the bottom located short core, top mounted upper entry control rod drives (CRDs) with ring-type dryers and simplified safety system with high pressure resistible primary containment vessel (PCV) concept. The natural circulation core eliminates recirculation pumps as well as needs for maintenance of such pumps. The top mounted upper entry CRDs enable the bottom located short core in RPV. The safety feature mainly consists of large water inventory above the core without large penetration below the top of the core, passive cooling system by isolation condenser (IC), high pressure resistible PCV and in-vessel retention (IVR) capability. The large inventory increases the system response time in case of design base accidents including loss of coolant accidents. The IC suppresses PCV pressure by steam condensation without any AC power. Cooling the molten core inside the RPV if the core should be damaged by loss of core coolability could attain the IVR. CCR's specific self-standing steel high pressure resistible PCV is designed to contain minimum piping and valves inside with reactor pressure vessel (RPV), only 13 m in diameter and 24 m in height. This compact PCV makes it possible to

  8. BWR Source Term Generation and Evaluation

    International Nuclear Information System (INIS)

    This calculation is a revision of a previous calculation (Ref. 7.5) that bears the same title and has the document identifier BBAC00000-01717-0210-000061. The purpose of this revision is to remove TBV (to-be-verified) -41 10 associated with the output files of the previous version (Ref. 7.30). The purpose of this and the previous calculation is to generate source terms for a representative boiling water reactor (BWR) spent nuclear fuel (SNF) assembly for the first one million years after the SNF is discharged from the reactors. This calculation includes an examination of several ways to represent BWR assemblies and operating conditions in SAS2H in order to quantify the effects these representations may have on source terms. These source terms provide information characterizing the neutron and gamma spectra in particles per second, the decay heat in watts, and radionuclide inventories in curies. Source terms are generated for a range of burnups and enrichments (see Table 2) that are representative of the waste stream and stainless steel (SS) clad assemblies. During this revision, it was determined that the burnups used for the computer runs of the previous revision were actually about 1.7% less than the stated, or nominal, burnups. See Section 6.6 for a discussion of how to account for this effect before using any source terms from this calculation. The source term due to the activation of corrosion products deposited on the surfaces of the assembly from the coolant is also calculated. The results of this calculation support many areas of the Monitored Geologic Repository (MGR), which include thermal evaluation, radiation dose determination, radiological safety analyses, surface and subsurface facility designs, and total system performance assessment. This includes MGR items classified as Quality Level 1, for example, the Uncanistered Spent Nuclear Fuel Disposal Container (Ref. 7.27, page 7). Therefore, this calculation is subject to the requirements of the Quality

  9. Status update of the BWR cask simulator

    Energy Technology Data Exchange (ETDEWEB)

    Lindgren, Eric R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Durbin, Samuel G. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-09-01

    The performance of commercial nuclear spent fuel dry storage casks are typically evaluated through detailed numerical analysis of the system's thermal performance. These modeling efforts are performed by the vendor to demonstrate the performance and regulatory compliance and are independently verified by the Nuclear Regulatory Commission (NRC). Carefully measured data sets generated from testing of full sized casks or smaller cask analogs are widely recognized as vital for validating these models. Numerous studies have been previously conducted. Recent advances in dry storage cask designs have moved the storage location from above ground to below ground and significantly increased the maximum thermal load allowed in a cask in part by increasing the canister helium pressure. Previous cask performance validation testing did not capture these parameters. The purpose of the investigation described in this report is to produce a data set that can be used to test the validity of the assumptions associated with the calculations presently used to determine steady-state cladding temperatures in modern dry casks. These modern cask designs utilize elevated helium pressure in the sealed canister or are intended for subsurface storage. The BWR cask simulator (BCS) has been designed in detail for both the above ground and below ground venting configurations. The pressure vessel representing the canister has been designed, fabricated, and pressure tested for a maximum allowable pressure (MAWP) rating of 24 bar at 400 C. An existing electrically heated but otherwise prototypic BWR Incoloy-clad test assembly is being deployed inside of a representative storage basket and cylindrical pressure vessel that represents the canister. The symmetric single assembly geometry with well-controlled boundary conditions simplifies interpretation of results. Various configurations of outer concentric ducting will be used to mimic conditions for above and below ground storage configurations

  10. BWR ASSEMBLY SOURCE TERMS FOR WASTE PACKAGE DESIGN

    Energy Technology Data Exchange (ETDEWEB)

    T.L. Lotz

    1997-02-15

    This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to provide boiling water reactor (BWR) assembly radiation source term data for use during Waste Package (WP) design. The BWR assembly radiation source terms are to be used for evaluation of radiolysis effects at the WP surface, and for personnel shielding requirements during assembly or WP handling operations. The objectives of this evaluation are to generate BWR assembly radiation source terms that bound selected groupings of BWR assemblies, with regard to assembly average burnup and cooling time, which comprise the anticipated MGDS BWR commercial spent nuclear fuel (SNF) waste stream. The source term data is to be provided in a form which can easily be utilized in subsequent shielding/radiation dose calculations. Since these calculations may also be used for Total System Performance Assessment (TSPA), with appropriate justification provided by TSPA, or radionuclide release rate analysis, the grams of each element and additional cooling times out to 25 years will also be calculated and the data included in the output files.

  11. Reliability of BWR high pressure core cooling

    International Nuclear Information System (INIS)

    The high pressure coolant injection system (HPCI), and the reactor core isolation cooling system (RCIC) are steam turbine driven systems that can inject water into a boiling water reactor at full operating pressure. Their purpose is to supply water during any failure that allows water to be lost while the reactor is at pressure and temperature. A large number of BWR plants are not meeting HPCI and RCIC performance goals for core cooling. NSAC considers concurrent failure of NPCI and RCIC to be the most probable potential cause of low reactor water level and possibly fuel damage in a boiling water reactor. Between January 1978 and May 1981, 169 licensee event reports were filed where HPCI or RCIC was inoperable or was declared inoperable. The present effort has shown that at least 40% of NPCI and RCIC problems might be averted by a high quality preventive maintenance program. About half of the plants do not perform cold quick-start surveillance testing of HPCI and RCIC. They do perform routine startup tests, but the equipment is first preheated and the startup is relatively gentle. However, emergency start-ups are abrupt and from the cold condition. Therefore, cold quick-start testing is the only way to assure that all components, control systems, and instruments are functioning correctly for automatic safety initiation. (author)

  12. Method of operating BWR type reactors

    International Nuclear Information System (INIS)

    Purpose: To enable reactor control depending on any demanded loads by performing control by the insertion of control rods in addition to the control by the regulation of the flow rate of the reactor core water at high power operation of a BWR type reactor. Method: The power is reduced at high power operation by decreasing the flow rate of reactor core water from the starting time for the power reduction and the flow rate is maintained after the time at which it reaches the minimum allowable flow rate. Then, the control rod is started to insert from the above time point to reduce the power to an aimed level. Thus, the insufficiency in the reactivity due to the increase in the xenon concentration can be compensated by the withdrawal of the control rods and the excess reactivity due to the decrease in the xenon concentration can be compensated by the insertion of the control rods, whereby the reactor power can be controlled depending on any demanded loads without deviating from the upper or lower limit for the flow rate of the reactor core water. (Moriyama, K.)

  13. Operation method for BWR type reactor

    International Nuclear Information System (INIS)

    In a BWR type reactor, the number of fuels at low enrichment, among initially loaded fuels, is increased greater than that of fuels to be exchanged, and the number of fuels at low enrichment remained in a reactor core after fuel exchange is decreased to smaller than that of entire control rods. Further, the fuels at low enrichment are disposed to the inner side except for the outermost circumference in the reactor core after fuel exchange. Since fuels of high reactivity are disposed at the outermost circumference in a second cycle, leakage of neutrons is increased and effective breeding factor is decreased. However, since the number of brought over fuels at low enrichment is decreased and the number of fuels at high enrichment is increased, effective average reactor core enrichment degree is increased, to compensate the lowering thereof due to the increase of neutron leakage. Since dispersion effect for the distribution of the enrichment degree can be utilized as much as possible by greatly reducing the number and the enrichment degree of fuels at low enrichment for initially loaded fuels, irrespective of the average enrichment degree and the fueling pattern in a first cycle, a burnup degree upon take-out of initially loaded fuels at ow enrichment degree can be increased to maximum. (N.H.)

  14. An overview of the BWR ECCS strainer blockage issues

    Energy Technology Data Exchange (ETDEWEB)

    Serkiz, A.W.; Marshall, M.L. Jr.; Elliott, R. [Nuclear Regulatory Commission, Washington, DC (United States)

    1996-03-01

    This Paper provides a brief overview of actions taken in the mid 1980s to resolve Unresolved Safety Issue (USI) A-43, {open_quotes}Containment Emergency Sump Performance,{close_quotes} and their relationship to the BWR strainer blockage issue; the importance of insights gained from the Barseback-2 (a Swedish BWR) incident in 1992 and from ECCS strainer testing and inspections at the Perry nuclear power plant in 1992 and 1993; an analysis of an US BWR/4 with a Mark I containment; an international community sharing of knowledge relevant to ECCS strainer blockage, additional experimental programs; and identification of actions needed to resolve the strainer blockage issue and the status of such efforts.

  15. The BWR owners' group planning guide for life extension

    International Nuclear Information System (INIS)

    Extending the operating life of a commercial nuclear power plant has been shown to be economically beneficial to both the utility and the electric customer. As such, many utilities are planning and implementing plant life extension (PLEX) programs. A document has been developed which provides guidance to utilities in formulating a PLEX program plant for one or more boiling water reactor (BWR) plants. The guide has been developed by the BWR Owners' Group Plant Life Extension Committee. The principal bases for this guide were the BWR Pilot and Lead Plant Programs. These programs were used as models to develop the 'base plan' described in this guide. By formulating their program plant utilizing the base plan, utilities will be able to maximize the use of existing evaluations and results. The utility planner will build upon the base plan by adding any tasks or features that are unique to their programs. (author)

  16. The JAERI code system for evaluation of BWR ECCS performance

    International Nuclear Information System (INIS)

    Development of respective computer code system of BWR and PWR for evaluation of ECCS has been conducted since 1973 considering the differences of the reactor cooling system, core structure and ECCS. The first version of the BWR code system, of which developmental work started earlier than that of the PWR, has been completed. The BWR code system is designed to provide computational tools to analyze all phases of LOCAs and to evaluate the performance of the ECCS including an ''Evaluation Model (EM)'' feature in compliance with the requirements of the current Japanese Evaluation Guideline of ECCS. The BWR code system could be used for licensing purpose, i.e. for ECCS performance evaluation or audit calculations to cross-examine the methods and results of applicants or vendors. The BWR code system presented in this report comprises several computer codes, each of which analyzes a particular phase of a LOCA or a system blowdown depending on a range of LOCAs, i.e. large and small breaks in a variety of locations in the reactor system. The system includes ALARM-B1, HYDY-B1 and THYDE-B1 for analysis of the system blowdown for various break sizes, THYDE-B-REFLOOD for analysis of the reflood phase and SCORCH-B2 for the calculation of the fuel assembl hot plane temperature. When the multiple codes are used to analyze a broad range of LOCA as stated above, it is very important to evaluate the adequacy and consistency between the codes used to cover an entire break spectrum. The system consistency together with the system performance are discussed for a large commercial BWR. (author)

  17. Evaluation of PWR and BWR pin cell benchmark results

    International Nuclear Information System (INIS)

    In order to carry out reliable reactor core calculations for a boiled water reactor (BWR) or a pressurized water reactor (PWR) first reactivity calculations have to be carried out for which several calculation programs are available. The purpose of the title project is to exchange experiences to improve the knowledge of this reactivity calculations. In a large number of institutes reactivity calculations of PWR and BWR pin cells were executed by means of available computer codes. Results are compared. It is concluded that the variations in the calculated results are problem dependent. Part of the results is satisfactory. However, further research is necessary

  18. en el riego con aguas residuales

    Directory of Open Access Journals (Sweden)

    Reynaldo Roque R.

    2006-01-01

    Full Text Available Es una realidad mundial, actual, que el agua potable es cada día más escasa para todos los usos en las actividades diarias de la población. La agricultura es el mayor consumidor de agua, con marcado incremento en los países en vías de desarrollo donde a su vez se requiere de una mayor producción de alimentos. En áreas urbanas y periurbanas el agua que se requiere para los cultivos hortícolas y riego de campos deportivos y de jardines compite fuertemente por las necesidades crecientes de la población. El uso de aguas residuales de las plantas de tratamiento y lagunas de oxidación se presenta como una alternativa viable para ser utilizada como agua de riego, empleando los sistemas de riego de pivote central, tecnología de punta que ha evolucionado cualitativamente en los últimos años, ofreciendo paquetes integrales, desde los módulos de emisores hasta las posibilidades de programación de los riegos que la hacen grandemente atractivas, técnica y económicamente para estos fines.

  19. Full system decontamination experience in BWR

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, N.; Sugai, K.; Katayouse, N.; Fujimori, A.; Iida, K.; Hayashi, K. [Tokyo Electric Power Company, Tokyo (Japan); Kanasaki, T.; Inami, I. [Toshiba Corporation, Yokohama (Japan); Strohmer, F. [Framatome ANP Gmbh, Eelangen (Germany)

    2002-07-01

    At the Fukushima Daiichi Nuclear Power Station unit 3, unit 2, unit 5 and unit 1 of Tokyo Electric Power Company (TEPCO), the replacement of the core shroud and internals has been conducted since 1997 in this order. The welded core internals in operating BWR plants were replaced to improve stress corrosion cracking (SCC) resistance. At present these units are operating smoothly. The developed technology concept is to restore those internals in open air inside the reactor pressure vessel (RPV). To reduce the radiation dose rate inside the RPV, not only a shielding method was applied to cut the radiation from the irradiated structures but also a chemical decontamination method was applied to dissolve the radioactive crud deposited on the surface by using chemical agents. The calculated decontamination factor (DF) at the RPV bottom reached 35-117. As result, the dose rate decreased to approximately 0.1 mSv/h under water. Before and after the installation of the in-vessel shielding, a mechanical cleaning was extensively applied inside the RPV to remove the residual crud as well as the swarf, chips from cutting. As a result, the dose rate at the RPV bottom decreased to ranging from 0.2 to 0.4 mSv/h in air. A working environment for human access, which was better than expected, was established inside the RPV, resulting in 70, 140, 50 and 70 man-Sv (estimated) saving respectively at unit 3 (1F-3), unit 2(1F-2), unit 5(1F-5) and unit 1(1F-1). All four full system decontamination (FSDs) contributed to the successful realization of the core shroud replacement project under the dry condition in RPV.

  20. Repercusiones sanitarias de la calidad del agua: los residuos de medicamentos en el agua

    OpenAIRE

    Cristina Postigo Rebollo; Meritxell Gros Calvo; María José López de Alda Villaizán; Mira Petrovic; Antoni Ginebreda Martí; Damià Barceló Culleres

    2011-01-01

    Este trabajo resume varios estudios de monitorización de fármacos y drogas de abuso llevados a cabo en el medio ambiente acuático de las cuencas de los ríos Llobregat y Ebro con el fin de evaluar la calidad del agua en relación a la presencia de estas substancias y su potencial riesgo para la salud ambiental y pública. La identificación de estos compuestos aguas abajo del punto de vertido de las plantas depuradoras apunta a la descarga de agua residual tratada como la principal fuente de emis...

  1. Un uso eficiente del agua doméstica : tratamiento de las aguas grises

    OpenAIRE

    Castro Montilla, María

    2015-01-01

    El trabajo expuesto a continuación plantea la reutilización de las aguas grises como un método novedoso para conseguir un uso eficiente del agua en el ámbito doméstico, llevando consigo un ahorro del recurso para conseguir, por una parte, la reducción de los costes debido a un consumo menor del agua; y por otra, una reducción de la huella ecológica para contribuir a un progreso hacia una arquitectura más sostenible y solidaria con el medioambiente. Se desarrollarán conceptos que abarcan, d...

  2. Advanced methods for BWR transient and stability analysis

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, A.; Wehle, F.; Opel, S.; Velten, R. [AREVA, AREVA NP, Erlangen (Germany)

    2008-07-01

    The design of advanced Boiling Water Reactor (BWR) fuel assemblies and cores is governed by the basic requirement of safe, reliable and flexible reactor operation with optimal fuel utilization. AREVA NP's comprehensive steady state and transient BWR methodology allows the designer to respond quickly and effectively to customer needs. AREVA NP uses S-RELAP5/RAMONA as the appropriate methodology for the representation of the entire plant. The 3D neutron kinetics and thermal-hydraulics code has been developed for the prediction of system, fuel and core behavior and provides additional margins for normal operation and transients. Of major importance is the extensive validation of the methodology. The validation is based on measurements at AREVA NP's test facilities, and comparison of the predictions with a great wealth of measured data gathered from BWR plants during many years of operation. Three of the main fields of interest are stability analysis, operational transients and reactivity initiated accidents (RIAs). The introduced 3D methodology for operational transients shows significant margin regarding the operational limit of critical power ratio, which has been approved by the German licensing authority. Regarding BWR stability a large number of measurements at different plants under various conditions have been performed and successfully post-calculated with RAMONA. This is the basis of reliable pre-calculations of the locations of regional and core-wide stability boundaries. (authors)

  3. Material operating behaviour of ABB BWR control rods

    International Nuclear Information System (INIS)

    The BWR control rods made by ABB use boron carbide (B4C and hafnium as absorber material within a cladding of stainless steel. The general behaviour under operation has proven to be very good. ABB and many of their control rod customers have performed extensive inspection programs of control rod behaviour. However, due to changes in the material properties under fast and thermal neutron irradiation defects may occur in the control rods at high neutron fluences. Examinations of irradiated control rod materials have been performed in hot cell laboratories. The examinations have revealed the defect mechanism Irradiation Assisted Stress Corrosion Cracking (IASCC) to appear in the stainless steel cladding. For IASCC to occur three factors have to act simultaneously. Stress, material sensitization and an oxidising environment. Stress may be obtained from boron carbide swelling due to irradiation. Stainless steel may be sensitized to intergranular stress corrosion cracking under irradiation. Normally the reactor environment in a BWR is oxidising. The presentation focuses on findings from hot cell laboratory work on irradiated ABB BWR control rods and studies of irradiated control rod materials in the hot cells at PSI. Apart from physical, mechanical and microstructural examinations, isotope analyses were performed to describe the local isotopic burnup of boron. Consequences (such as possible B4C washout) of a under operation in a ABB BWR, after the occurrence of a crack is discussed based on neutron radiographic examinations of control rods operated with cracks. (author)

  4. Experience and reliability of Framatome ANP's PWR and BWR fuel

    International Nuclear Information System (INIS)

    Based on three decades of fuel supply to 169 PWR and BWR plants on four continents, Framatome ANP has a very large database from operating experience feedback. The performance of Framatome PWR and BWR fuel is discussed for the period 1992-2001 with special emphasis on fuel failures, countermeasures and their effectiveness. While PWR fuel performance in most reactors has been good, the performance in some years did suffer from special circumstances that caused grid-to-rod fretting failures in few PWRs. After solving this problem, fuel of all types showed high reliability again. Especially the current PWR fuel products AFA 3G, HTP, Mark B and Mark BW showed a very good operating performance. Fuel reliability of Framatome ANP BWR fuel has been excellent over the last decade with average annual fuel rod failure rates under 1x10-5 since 1991. More than 40% of all BWR fuel failures in the 1992-2001 decade were caused by debris fretting. The debris problem has been remedied with the FUELGUARDTM lower tie plate, and by reactor operators' efforts to control the sources of debris. PCI, the main failure mechanism in former periods, affected only 10 rods. All of these rods had non-liner cladding. (author)

  5. Pool swell in a nuclear containment wetwell. [BWR

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez, T.

    1976-04-01

    A brief description is presented of scale model tests conducted to study LOCA induced wetwell pool swelling in the BWR Mk 1 containment pressure suppression system. The Mk 1 containment configuration is described together with the scale model design, the conduct of the tests, and the experimental results. (DG)

  6. Transmutation of minor actinide using thorium fueled BWR core

    International Nuclear Information System (INIS)

    One of the methods to conduct transmutation of minor actinide is the use of BWR with thorium fuel. Thorium fuel has a specific behaviour of producing a little secondary minor actinides. Transmutation of minor actinide is done by loading it in the BWR with thorium fuel through two methods, namely close recycle and accumulation recycle. The calculation of minor actinide composition produced, weigh of minor actinide transmuted, and percentage of reminder transmutation was carried SRAC. The calculations were done to equivalent cell modeling from one fuel rod of BWR. The results show that minor actinide transmutation is more effective using thorium fuel than uranium fuel, through both close recycle and accumulation recycle. Minor actinide transmutation weight show that the same value for those recycle for 5th recycle. And most of all minor actinide produced from 5 unit BWR uranium fuel can transmuted in the 6th of close recycle. And, the minimal value of excess reactivity of the core is 12,15 % Δk/k, that is possible value for core operation

  7. The Advanced BWR Nuclear Plant: Safe, economic nuclear energy

    Energy Technology Data Exchange (ETDEWEB)

    Redding, J.R. [GE Nuclear Energy, San Jose, CA (United States)

    1994-12-31

    The safety and economics of Advanced BWR Nuclear Power Plants are outlined. The topics discussed include: ABWR Programs: status in US and Japan; ABWR competitiveness: safety and economics; SBWR status; combining ABWR and SBWR: the passive ABWR; and Korean/GE partnership.

  8. Advanced methods for BWR transient and stability analysis

    International Nuclear Information System (INIS)

    The design of advanced Boiling Water Reactor (BWR) fuel assemblies and cores is governed by the basic requirement of safe, reliable and flexible reactor operation with optimal fuel utilization. AREVA NP's comprehensive steady state and transient BWR methodology allows the designer to respond quickly and effectively to customer needs. AREVA NP uses S-RELAP5/RAMONA as the appropriate methodology for the representation of the entire plant. The 3D neutron kinetics and thermal-hydraulics code has been developed for the prediction of system, fuel and core behavior and provides additional margins for normal operation and transients. Of major importance is the extensive validation of the methodology. The validation is based on measurements at AREVA NP's test facilities, and comparison of the predictions with a great wealth of measured data gathered from BWR plants during many years of operation. Three of the main fields of interest are stability analysis, operational transients and reactivity initiated accidents (RIAs). The introduced 3D methodology for operational transients shows significant margin regarding the operational limit of critical power ratio, which has been approved by the German licensing authority. Regarding BWR stability a large number of measurements at different plants under various conditions have been performed and successfully post-calculated with RAMONA. This is the basis of reliable pre-calculations of the locations of regional and core-wide stability boundaries. (authors)

  9. Assessment of the Prony's method for BWR stability analysis

    International Nuclear Information System (INIS)

    Highlights: → This paper describes a method to determine the degree of stability of a BWR. → Performance comparison between Prony's and common AR techniques is presented. → Benchmark data and actual BWR transient data are used for comparison. → DR and f results are presented and discussed. → The Prony's method is shown to be a robust technique for BWR stability. - Abstract: It is known that Boiling Water Reactors are susceptible to present power oscillations in regions of high power and low coolant flow, in the power-flow operational map. It is possible to fall in one of such instability regions during reactor startup, since both power and coolant flow are being increased but not proportionally. One other possibility for falling into those areas is the occurrence of a trip of recirculation pumps. Stability monitoring in such cases can be difficult, because the amount or quality of power signal data required for calculation of the stability key parameters may not be enough to provide reliable results in an adequate time range. In this work, the Prony's Method is presented as one complementary alternative to determine the degree of stability of a BWR, through time series data. This analysis method can provide information about decay ratio and oscillation frequency from power signals obtained during transient events. However, so far not many applications in Boiling Water Reactors operation have been reported and supported to establish the scope of using such analysis for actual transient events. This work presents first a comparison of decay ratio and frequency oscillation results obtained by Prony's method and those results obtained by the participants of the Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark using diverse techniques. Then, a comparison of decay ratio and frequency oscillation results is performed for four real BWR transient event data, using Prony's method and two other techniques based on an autoregressive modeling. The four

  10. Tratamiento biológico de aguas residuales industriales

    OpenAIRE

    Lobo, Cintia Cecilia

    2014-01-01

    A nivel mundial la disponibilidad de recursos hídricos constituye un tema de gran preocupación. En la Tierra solo el 2.53% del total de agua corresponde a agua dulce y se estima que solo el 15% del total de aguas residuales de América Latina recibe tratamiento. En Argentina la principal fuente de recursos hídricos son las aguas superficiales que representan un 80% del total de disponibilidad de agua; dentro de ellas se destaca la Cuenca del Plata que representa un 34% de la superficie tot...

  11. Characteristics of fluctuating pressure generated in BWR main steam lines

    International Nuclear Information System (INIS)

    The BWR-3 steam dryer in the Quad Cities Unit 2 Nuclear Power Plant was damaged by high cycle fatigue due to acoustic-induced vibration. The dryer failure was as attributed to flow-induced acoustic resonance at the stub pipes of safety relief valves (SRVs) in the main steam lines (MSLs). The acoustic resonance was considered to be generated by interaction between the sound field and an unstable shear layer across the closed side branches with SRV stub pipes. We have started a research program on BWR dryers to develop their loading evaluation methods. Moreover, it has been necessary to evaluate the dryer integrity of BWR-5 plants which are the main type of BWR in Japan. In the present study, we used 1/10-scale BWR tests and analyses to investigate the flow-induced acoustic resonance and acoustic characteristics in MSLs. The test apparatus consisted of a steam dryer, a steam dome and 4 MSLs with 20 SRV stub pipes. A finite element method (FEM) was applied for the calculation of three-dimensional wave equations in acoustic analysis. We demonstrated that remarkable fluctuating pressures occurred in high and low frequency regions. High frequency fluctuating pressures was generated by the flow-induced acoustic resonance in the SRV stub pipes. Low frequency fluctuating pressure was generated in an MSL with the dead leg. The frequency of the latter almost coincided with the natural frequency of the MSL with the dead leg. The amplitude of the fluctuating pressures in the multiple stub pipes became more intense because of interaction between them compared with that in the single stub pipe. Acoustic analysis results showed that the multiple stub pipes caused several natural frequencies in the vicinity of the natural frequency of the single stub pipe and several modes of the standing wave in the MSLs. (author)

  12. "Zaragoza,ciudad ahorradora de agua"

    Directory of Open Access Journals (Sweden)

    Viñuales Edo, Victor

    2000-02-01

    Full Text Available In the year before the project was initiated, 11 million Spaniards were undergoing daily water restrictions. There were serious inter-regional conflicts over this scarce commodity. There seemed to be only one solution: more reservoirs and more water trans-shipments, what means high costs and harm to the environment. In Zaragoza, a city of 700.000 inhabitants in the north -cast of Spain, as in other cities in Spain, a triple paradox was to emerge: rainfall was scarce and irregular. water was cheap, and it was being misused. February 1997 saw the beginning of the "Zaragoza, the water-saving city" project. This aimed to promote a new water-saving consciousness through a more efficient management of this resource. It emphasised, above all, the importance of simple technological change to achieve a sustainable reduction in water consumption. The project was to issue a challenge to the city: to save 1.000 million litres of domestic water consumption in one year The project has shown that it is possible to deal with the shortage of water incities, using a cheap, ecological, fast and contentious-free app roach, by increasing efficiency in consumption. The most important lesson to be learnt is that the shared responsibility between the main players (manufacturers, retailers, consumers, distributors. plumbers, etc. has managed to create a new synergy which favours water-use efficiency. 1176 million litres of water have been saved. Spanish cities now have a successful model to follow for the most ecologically-so und method of facing up to the next drought.EI año anterior al inicio del proyecto, 11 millones de españoles sufrieron restricciones diarias de agua. Los conflictos entre regiones por el agua escasa fueron muy graves. Parecía que solo había una solución: mas pantanos y mas trasvases. Y su consecuencia inevitable: inversiones multintillonarias, daños al medio ambiente, larguisimos plazos de ejecución. En Zaragoza, ciudad del nordeste de Espa

  13. Connected analysis nuclear-thermo-hydraulic of parallel channels of a BWR reactor using distributed computation; Analisis acoplado nuclear-termohidraulico de canales paralelos de un reactor BWR empleando computacion distribuida

    Energy Technology Data Exchange (ETDEWEB)

    Campos Gonzalez, Rina Margarita

    2007-07-15

    de Estabilidad que brinda la oportunidad de contar con datos reales de planta. Ademas de que en el caso 9 del ciclo 14 de este Benchamark se presentaron oscilaciones fuera de fase, las cuales resultan de gran interes debido a que los sistemas de deteccion que registran el promedio de la potencia del nucleo no las detectan. Adicionalmente en este trabajo se obtiene de manera individual el modelo de los lazos de recirculacion como un modulo independiente, ya que este modelo pertenece a otro trabajo y trabaja acoplado con la vasija del reactor. El modelo de los lazos de recirculacion es capaz de modelar varios transitorios de interes, como se muestra en el apendice A de este trabajo, entre los que se encuentran el disparo de bombas de recirculacion o la transferencia a baja o alta velocidad de ellas. El alcance del trabajo desarrollado se centra solamente en el nucleo del reactor, pero aprovechando la modularidad que ofrece PVM, es posible agregar componentes como separadores y secadores de vapor, lineas de agua de alimentacion y de vapor para obtener un modelo de un circuito cerrado completo. Las aplicaciones se centran principalmente en el entrenamiento de personal en la fenomenologia del BWR, y como herramienta de investigacion en el estudio de la dinamica de reactores BWR. El estudio de oscilaciones fuera de fase presenta actualmente retos como son la explicacion de la variacion de la linea neutra con el tiempo, oscilaciones fuera de fase no azimutales, sino axiales, etc. Por lo pronto se tiene un primer modelo orientado en esta direccion.

  14. Como una luna en el agua [Score

    Directory of Open Access Journals (Sweden)

    Francisco del Pino

    2014-12-01

    Full Text Available The title of the solo piano piece Como una luna en el agua, composed between June and July of 2014, refers to the end of the seventh chapter of the novel Rayuela (Hopscotch by the Argentine writer Julio Cortázar, in which an allegorical description of a kiss takes the form of a prose poem.

  15. BWR refill-reflood program: core spray distribution experimental task plan

    Energy Technology Data Exchange (ETDEWEB)

    Eckert, T.

    1981-02-01

    An experimental task plan for the BWR/4 core spray task of the Refill-Reflood Test Program is presented. The test program will provide core spray distribution data for a 30 degree sector of the BWR/4 and 5-218 design. This design uses different nozzle types and different sparger elevations than the BWR/6-218 design which was tested previously. Test parameter ranges are specified; individual tests are defined; and measurement and data utilization plans are defined.

  16. Neutron noise analysis of BWR using time series analysis

    International Nuclear Information System (INIS)

    The main purpose of this paper is to give more quantitative understanding of noise source in neutron flux and to provide a useful tool for the detection and diagnosis of reactor. The space dependent effects of distributed neutron flux signals at the axial direction of two different strings are investigated by the power contribution ratio among neutron fluxes and the incoherent noise spectra of neutron fluxes derived from autoregressive spectra. The signals are measured on the medium sized commercial BWR of 460 MWe in Japan. From the obtained results, local and global noise sources in neutron flux are discussed. This method is indicated to be a useful tool for detection and diagnosis of anomalous phenomena in BWR. (orig./RW)

  17. Electrochemical potential measurements under simulated BWR water chemistry conditions

    International Nuclear Information System (INIS)

    Laboratory studies have been performed to investigate the stainless steel corrosion potential under simulated BWR coolant chemistry conditions. In addition to dissolved oxygen and hydrogen, test parameters also included chemical additives, metallic ions and hydrogen peroxide at various concentrations. The effect of water flow velocity was also investigated under various water chemistry conditions. The details of test results have been described elsewhere, and the highlights of the investigation are summarized in this paper. (J.P.N.)

  18. Thermohydraulic stability coupled to the neutronic in a BWR

    International Nuclear Information System (INIS)

    In a BWR type reactor the phenomenon of the nuclear fission is presented, in which are liberated in stochastic form neutrons, originating that the population of the same ones varies in statistic form around a mean value. This variation will cause that when the neutron flow impacts on the neutron detectors, its are had as a result neutron flow signals with fluctuations around an average value. In this article it is shown that it conforms it lapses the time, this variations in the neutron flow (and therefore, in the flow signal due only to the fission), they presented oscillations inside a stable range, which won't be divergent. Considering that the BWR is characterized because boiling phenomena are presented, which affect the moderation of the neutrons, additional variations will be had in the signal coming from the neutron detectors, with relationship to the fission itself, which will be influenced by the feedback of the moderator's reactivity and of the temperature of the fuel pellet. Also, as the BWR it has coupled control systems to maintain the coolant level one and of the thermal power of the reactor, for each control action it was affected the neutron population. This means that the reactor could end up straying of a stable state condition. By it previously described, the study of the thermohydraulic stability coupled to the neutronic is complex. In this work it is shown the phenomenology, the mathematical models and the theoretical behavior associated to the stability of the BWR type reactor; the variables that affect it are identified, the models that reproduce the behavior of the thermohydraulic stability coupled to the neutronic, the way to maintain stable the reactor and the instrumentation that can settle to detect and to suppress uncertainties is described. In particular, is make reference to the evolution of the methods to maintain the stability of the reactor and the detection system and suppression of uncertainties implemented in the Laguna Verde

  19. Latest experiences in inspecting the inside of BWR vessel shields

    Energy Technology Data Exchange (ETDEWEB)

    Alberdi, R.; Gonzalez, E.

    2001-07-01

    In the last few years, the owners of BWR nuclear power plants have been forced to address new fuel shield inspection requirements, TECNATOM has responded to this situation by launching the TEIDE projects, which include development of an inspection machine and the corresponding Non-Destructive Tests to examine the inside of this shield. With these projects, TECNATOM has performed more than 12 fuel shield inspections in different countries. This article describes the experience gained in the last three years. (Author)

  20. Determination of BWR Spent Nuclear Fuel Assembly Effective Thermal Conductivity

    Energy Technology Data Exchange (ETDEWEB)

    Matthew D. Hinds

    2001-10-17

    The purpose of this calculation is to provide an effective thermal conductivity for use in predicting peak cladding temperatures in boiling water reactor (BWR) fuel assemblies with 7x7,8x8, and 9x9 rod arrays. The first objective of this calculation is to describe the development and application of a finite element representation that predicts peak spent nuclear fuel temperatures for BWR assemblies. The second objective is to use the discrete representation to develop a basis for determining an effective thermal conductivity (described later) for a BWR assembly with srneared/homogeneous properties and to investigate the thermal behavior of a spent fuel assembly. The scope of this calculation is limited to a steady-state two-dimensional representation of the waste package interior region. This calculation is subject to procedure AP-3.124, Calculations (Ref. 27) and guided by the applicable technical work plan (Ref. 14). While these evaluations were originally developed for the thermal analysis of conceptual waste package designs emplaced in the potential repository at Yucca Mountain, the methodology applies to storage and transportation thermal analyses as well. Note that the waste package sketch in Attachment V depicts a preliminary design, and should not be interpreted otherwise.

  1. Thermohydraulic stability coupled to the neutronic in a BWR; Estabilidad termohidraulica acoplada a la neutronica en un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Calleros M, G.; Zapata Y, M.; Gomez H, R.A.; Mendez M, A. [Comision Federal de Electricidad, Central Nucleoelectrica de Laguna Verde, Carretera Cardel-Nautla Km. 42.5, Mpio. Alto Lucero, Veracruz (Mexico); Castlllo D, R. [ININ, Carretera Mexico-Toluca Km 36.5, La Marquesa, Estado de Mexico (Mexico)]. e-mail: gcm9acpp@cfe.gob.mx

    2006-07-01

    In a BWR type reactor the phenomenon of the nuclear fission is presented, in which are liberated in stochastic form neutrons, originating that the population of the same ones varies in statistic form around a mean value. This variation will cause that when the neutron flow impacts on the neutron detectors, its are had as a result neutron flow signals with fluctuations around an average value. In this article it is shown that it conforms it lapses the time, this variations in the neutron flow (and therefore, in the flow signal due only to the fission), they presented oscillations inside a stable range, which won't be divergent. Considering that the BWR is characterized because boiling phenomena are presented, which affect the moderation of the neutrons, additional variations will be had in the signal coming from the neutron detectors, with relationship to the fission itself, which will be influenced by the feedback of the moderator's reactivity and of the temperature of the fuel pellet. Also, as the BWR it has coupled control systems to maintain the coolant level one and of the thermal power of the reactor, for each control action it was affected the neutron population. This means that the reactor could end up straying of a stable state condition. By it previously described, the study of the thermohydraulic stability coupled to the neutronic is complex. In this work it is shown the phenomenology, the mathematical models and the theoretical behavior associated to the stability of the BWR type reactor; the variables that affect it are identified, the models that reproduce the behavior of the thermohydraulic stability coupled to the neutronic, the way to maintain stable the reactor and the instrumentation that can settle to detect and to suppress uncertainties is described. In particular, is make reference to the evolution of the methods to maintain the stability of the reactor and the detection system and suppression of uncertainties implemented in the

  2. Sistemas de plantas de tratamiento de aguas residuales en Colombia

    OpenAIRE

    Lizarazo Becerra, Jenny Milena; Orjuela Gutiérrez, Martha Isabel

    2013-01-01

    El establecimiento de Sistemas de tratamiento de aguas residuales son importantes para proteger el Salud Pública y el medio ambiente. Si las aguas residuales van a ser vertidas a un cuerpo receptor natural (mar, ríos, lagos), será necesario realizar un tratamiento para evitar enfermedades causadas por bacterias y virus en las personas que entran en contacto con esas aguas, y también para proteger la fauna y flora presentes en el cuerpo receptor natural. El reúso del agua tratada, riego de áre...

  3. Agua y emprendimiento social = Atrapanieblas y huertos urbanos

    OpenAIRE

    Cruz Gutiérrez, Abel

    2016-01-01

    El proyecto Acceso al Agua por Sistemas de Atrapanieblas de la Asociación “Peruanos sin Agua” con aguas no convencionales, Lluvias y Neblina. Por: Abel Cruz, Emprendedor Social y Líder del Movimiento Peruanos sin Agua El sistema atrapanieblas consiste en atrapar las gotas de agua microscópicas de la neblina a través del uso de mallas parecidas a una red. Las pequeñas gotas de la niebla quedan adheridas en los hilos de las mallas para luego ser redirigidas y acumuladas en depósitos. A...

  4. Arquitectura sostenible y conservación de agua

    OpenAIRE

    Lozano Portillo, Ana

    2008-01-01

    Esta monografía presenta la transcripción de la conferencia "Arquitectura sostenible y conservación de agua", pronunciada por Ana Lozano Portillo en el marco de la III Jornada Internacional sobre ahorro de agua organizada por el Ente Público del Agua de la Región de Murcia, celebrada el 12 de junio de 2008. Lozano Portillo, A. (2008). Arquitectura sostenible y conservación de agua. Cátedra Universidad Empresa Arquitectura Sostenible Bancaja Habitat. http://hdl.handle.net/10251/17962.

  5. The use of the partial coherence function technique for the investigation of BWR noise dynamics

    International Nuclear Information System (INIS)

    The extensive experimental investigations, at the last time, indicate that the partial coherence function technique can be a powerful method of the investigation of BWR noise dynamics. Symple BWR noise dynamics model for the global noise study, based on different noise phenomena, is proposed in this paper. (author)

  6. Simplified distributed parameters BWR dynamic model for transient and stability analysis

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa-Paredes, Gilberto [Area de Ingenieria en Recursos Energeticos, Universidad Autonoma Metropolitana-Iztapalapa, Av. San Rafael Atlixco, 186, Col. Vicentina, Mexico, DF 09340 (Mexico)]. E-mail: gepe@xanum.uam.mx; Nunez-Carrera, Alejandro [Comision Nacional de Seguridad Nuclear y Salvaguardias, Doctor Barragan 779, Col. Narvarte, Mexico, DF 03020 (Mexico); Vazquez-Rodriguez, Alejandro [Area de Ingenieria en Recursos Energeticos, Universidad Autonoma Metropolitana-Iztapalapa, Av. San Rafael Atlixco, 186, Col. Vicentina, Mexico, DF 09340 (Mexico)

    2006-09-15

    This paper describes a simplified model to perform transient and linear stability analysis for a typical boiling water reactor (BWR). The simplified transient model was based in lumped and distributed parameters approximations, which includes vessel dome and the downcomer, recirculation loops, neutron process, fuel pin temperature distribution, lower and upper plenums reactor core and pressure and level controls. The stability was determined by studying the linearized versions of the equations representing the BWR system in the frequency domain. Numerical examples are used to illustrate the wide application of the simplified BWR model. We concluded that this simplified model describes properly the dynamic of a BWR and can be used for safety analysis or as a first approach in the design of an advanced BWR.

  7. Prevention of organic iodide formation in BWR`s

    Energy Technology Data Exchange (ETDEWEB)

    Karjunen, T. [Finnish Centre for Radiation and Nuclear Safety, Helsinki (Finland); Laitinen, T.; Piippo, J.; Sirkiae, P. [VTT Manufacturing Technology (Finland)

    1996-12-01

    During an accident, many different forms of iodine may emerge. Organic iodides, such as methyl iodide and ethyl iodide, are relatively volatile, and thus their appearance leads to increased concentration of gaseous iodine. Since organic iodides are also relatively immune to most accident mitigation measures, such as sprays and filters, they can affect the accident source term significantly even when only a small portion of iodine is in organic form. Formation of organic iodides may not be limited by the amount of organic substances available. Excessive amounts of methane can be produced, for example, during oxidation of boron carbide, which is used in BWR`s as a neutron absorber material. Another important source is cable insulation. In a BWR, a large quantity of cables is placed below the pressure vessel. Thus a large quantity of pyrolyse gases will be produced, should the vessel fail. Organic iodides can be formed as a result of many different reactions, but at least in certain conditions the main reaction takes place between an organic radical produced by radiolysis and elemental iodine. A necessary requirement for prevention of organic iodide production is therefore that the pH in the containment water pools is kept high enough to eliminate formation of elemental iodine. In a typical BWR the suppression pool water is usually unbuffered. As a result, the pH may be dominated by chemicals introduced during an accident. If no system for adding basic chemicals is operable, the main factor affecting pool water pH may be hydrochloric acid released during cable degradation. Should this occur, the conditions could be very favorable for production of elemental iodine and, consequently, formation of organic iodides. Although high pH is necessary for iodine retention, it could have also adverse effects. High pH may, for example, accelerate corrosion of containment materials and alter the characteristics of the solid corrosion products. (author) 6 figs., 1 tab., 13 refs.

  8. BWR and PWR chemistry operating experience and perspectives

    International Nuclear Information System (INIS)

    It is well recognized that proper control of water chemistry plays a critical role in ensuring the safe and reliable operation of Boiling Water Reactors (BWRs) and Pressurized Water Reactors (PWRs). State-of-the-art water chemistry programs reduce general and localized corrosion of reactor coolant system, steam cycle equipment, and fuel cladding materials; ensure continued integrity of cycle components; and reduce radiation fields. Once a particular nuclear plant component has been installed or plant system constructed, proper water chemistry provides a global tool to mitigate materials degradation problems, thereby reducing the need for costly repairs or replacements. Recognizing the importance of proper chemistry control and the value in understanding the relationship between chemistry guidance and actual operating experience, EPRI continues to collect, monitor, and evaluate operating data from BWRs and PWRs around the world. More than 900 cycles of valuable BWR and PWR operating chemistry data has been collected, including online, startup and shutdown chemistry data over more than 10 years (> 20 years for BWRs). This paper will provide an overview of current trends in BWR and PWR chemistry, focusing on plants in the U.S.. Important chemistry parameters will be highlighted and discussed in the context of the EPRI Water Chemistry Guidelines requirements (i.e., those parameters considered to be of key importance as related to the major goals identified in the EPRI Guidelines: materials integrity; fuel integrity; and minimizing plant radiation fields). Perspectives will be provided in light of recent industry initiatives and changes in the EPRI BWR and PWR Water Chemistry Guidelines. (author)

  9. Prony's method application for BWR instabilities characterization

    Energy Technology Data Exchange (ETDEWEB)

    Castillo, Rogelio, E-mail: rogelio.castillo@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico); Ramírez, J. Ramón, E-mail: ramon.ramirez@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico); Alonso, Gustavo, E-mail: gustavo.alonso@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico); Instituto Politecnico Nacional, Unidad Profesional Adolfo Lopez Mateos, Ed. 9, Lindavista, D.F. 07300 (Mexico); Ortiz-Villafuerte, Javier, E-mail: javier.ortiz@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico)

    2015-04-01

    Highlights: • Prony's method application for BWR instability events. • Several BWR instability benchmark are assessed using this method. • DR and frequency are obtained and a new parameter is proposed to eliminate false signals. • Adequate characterization of in-phase and out-of-phase events is obtained. • The Prony's method application is validated. - Abstract: Several methods have been developed for the analysis of reactor power signals during BWR power oscillations. Among them is the Prony's method, its application provides the DR and the frequency of oscillations. In this paper another characteristic of the method is proposed to determine the type of oscillations that can occur, in-phase or out-of-phase. Prony's method decomposes a given signal in all the frequencies that it contains, therefore the DR of the fundamental mode and the first harmonic are obtained. To determine the more dominant pole of the system a normalized amplitude W of the system is calculated, which depends on the amplitude and the damping coefficient. With this term, it can be analyzed which type of oscillations is present, if W of the fundamental mode frequency is the greater, the type of oscillations is in-phase, if W of the first harmonic frequency is the greater, the type of oscillations is out-of-phase. The method is applied to several stability benchmarks to assess its validity. Results show the applicability of the method as an alternative analysis method to determine the type of oscillations occurred.

  10. In-situ testing of BWR closure head studs

    International Nuclear Information System (INIS)

    Mechanized ultrasonic inspection of closure head studs often is on the critical path. In German BWR's, a floodcompensator is used which allows human access to the studs despite the water is up to a much higher level. For stud inspection this provides a potential solution to get out of the critical path. However, the space restrictions around the studs due to the geometry of the floodcompensator did not allow the use of the existing manipulators. This paper describes the design of a dedicated compact manipulator of a construction which copes with the restricted space available around the studs

  11. Void effects on BWR Doppler and void reactivity feedback

    International Nuclear Information System (INIS)

    The significance of steam voids and control rods on the Doppler feedback in a gadolinia shimmed BWR is demonstrated. The importance of bypass voids when determining void feedback is also shown. Calculations were done using a point model, i.e., feedback was expressed in terms of reactivity coefficients which were determined for individual four-bundle configurations and then appropriately combined to yield reactor results. For overpower transients the inclusion of the void effect of control rods is to reduce Doppler feedback. For overpressurization transients the inclusion of the effect of bypass void wil increase the reactivity due to void collapse. (author)

  12. Corrosion products release from steel surface into BWR water coolant

    Energy Technology Data Exchange (ETDEWEB)

    Kritsky, V.G.; Korolev, A.S.; Berezina, I.G.; Sofyin, M.V.

    1986-02-01

    Factors influencing steel corrosion product release and transfer into a BWR primary circuit have been studied and reported on in this paper. The study of corrosion kinetics and corrosion product release was carried out on the samples tested under RBMK NPP condensate-feedwater cycle conditions, as well as, under test rig conditions. The ratio of corrosion product specific mass, transferred to the water, to the whole corrosion product specific mass of steel, formed under the given conditions was determined and used as a criterion, characterizing the extent of corrosion product transfer from the steel surface into the water.

  13. Neutron dosimetry. Environmental monitoring in a BWR type reactor

    International Nuclear Information System (INIS)

    The measurements carried out on reactor dosimetry are applied mainly to the study on the effects of the radiation in 108 materials of the reactor; little is on the environmental dosimetry outside of the primary container of BWR reactors. In this work the application of a neutron spectrometer formed by plastic detectors of nuclear traces manufactured in the ININ, for the environmental monitoring in penetrations around the primary container of the unit I of the Laguna Verde central is presented. The neutron monitoring carries out with purposes of radiological protection, during the operational tests of the reactor. (Author)

  14. BWR/5 Pressure-Suppression Pool Response during an SBO

    OpenAIRE

    Javier Ortiz-Villafuerte; Andrés Rodríguez-Hernández; Enrique Araiza-Martínez; Luis Fuentes-Márquez; Jorge Viais-Juárez

    2013-01-01

    RELAP/SCDAPSIM Mod 3.4 has been used to simulate a station blackout occurring at a BWR/5 power station. Further, a simplified model of a wet well and dry well has been added to the NSSS model to study the response of the primary containment during the evolution of this accident. The initial event leading to severe accident was considered to be a LOOP with simultaneous scram. The results show that RCIC alone can keep the core fully covered, but even in this case about 30% of the original liqui...

  15. Characterization studies of BWR-4 neutron noise analysis spectra

    International Nuclear Information System (INIS)

    Neutron noise analysis measurements were made in three BWR-4 reactors under full-power conditions to determine the noise characterization spectra of the reactors with two different instrument-tube cooling configurations. Both configurations were designed to prevent flow-induced vibration of the instrument tubes and subsequent damage of fuel channel boxes caused by impacts of the tubes with the boxes. Noise spectra from these three reactors were compared with spectra previously obtained prior to changing the instrument-tube cooling configuration, and no evidence of impacting was found

  16. Pensando al agua como parte del paisaje

    OpenAIRE

    Lorena Salvatelli

    2009-01-01

    El objetivo de este trabajo es discutir la importancia de los estudios de arqueología terrestre y subacuática como parte de un mismo proceso de interpretación del pasado. Se entiende que el registro arqueológico puede hallarse actualmente en una variedad de ambientes tanto terrestres como subacuáticos a causa de varias razones, como por ejemplo las oscilaciones de los niveles de agua ocurridas entre el Pleistoceno Final y el Holoceno Medio. Por lo tanto, se propone que para su ...

  17. Safety analysis of thorium-based fuels in the General Electric Standard BWR

    International Nuclear Information System (INIS)

    A denatured (U-233/Th)O2 fuel assembly has been designed which is energy equivalent to and hardware interchangeable with a modern boiling water reactor (BWR) reference reload assembly. Relative to the reference UO2 fuel, the thorium fuel design shows better performance during normal and transient reactor operation for the BWR/6 product line and will meet or exceed current safety and licensing criteria. Power distributions are flattened and thermal operating margins are increased by reduced steam void reactivity coefficients caused by U-233. However, a (U-233/Th)O2-fueled BWR will likely have reduced operating flexibility. A (U-235/Th)O2-fueled BWR should perform similar to a UO2-fueled BWR under all operating conditions. A (Pu/Th)O2-fueled BWR may have reduced thermal margins and similar accident response and be less stable than a UO2-fueled BWR. The assessment is based on comparisions of point model and infinite lattice predictions of various nuclear reactivity parameters, including void reactivity coefficients, Doppler reactivity coefficients, and control blade worths

  18. Neutron dosimetry. Environmental monitoring in a BWR type reactor; Dosimetria de neutrones. Monitoreo ambiental en un reactor del tipo BWR

    Energy Technology Data Exchange (ETDEWEB)

    Tavera D, L.; Camacho L, M.E

    1991-01-15

    The measurements carried out on reactor dosimetry are applied mainly to the study on the effects of the radiation in 108 materials of the reactor; little is on the environmental dosimetry outside of the primary container of BWR reactors. In this work the application of a neutron spectrometer formed by plastic detectors of nuclear traces manufactured in the ININ, for the environmental monitoring in penetrations around the primary container of the unit I of the Laguna Verde central is presented. The neutron monitoring carries out with purposes of radiological protection, during the operational tests of the reactor. (Author)

  19. BWR Servicing and Refueling Improvement Program: Phase I summary report

    International Nuclear Information System (INIS)

    Under the U.S. Department of Energy sponsorship, General Electric Co. (GE) undertook a study of boiling water reactor (BWR) refueling outages for the purpose of recommending the development and demonstration of critical path time savings improvements. The Tennessee Valley Authority (TVA) joined the study as a subcontractor, providing monitoring assistance and making the Browns Ferry Site available for improvement demonstrations. Agreement was also reached with Georgia Power Co., Power Authority of the State of New York, and Commonwealth Edison Co. for monitoring and data collection at Hatch 1, FitzPatrick, and Quad Cities 1 nuclear plants, respectively. The objective was to identify, develop, and demonstrate improved refueling, maintenance, and inspection procedures and equipment. The improvements recommended in this study are applicable to BWR nuclear plants currently in operation as well as those in the design and construction phases. The recommendations and outage information can be used as a basis to plan and conduct the first outages of new plants and to improve the planning and facilities of currently operating plants. Many of the recommendations can readily be incorporated in plants currently in the design and construction phases as well as in the design of future plants. Many of these recommended improvements can be implemented immediately by utilities without further technical development

  20. BWROPT: A multi-cycle BWR fuel cycle optimization code

    Energy Technology Data Exchange (ETDEWEB)

    Ottinger, Keith E.; Maldonado, G. Ivan, E-mail: Ivan.Maldonado@utk.edu

    2015-09-15

    Highlights: • A multi-cycle BWR fuel cycle optimization algorithm is presented. • New fuel inventory and core loading pattern determination. • The parallel simulated annealing algorithm was used for the optimization. • Variable sampling probabilities were compared to constant sampling probabilities. - Abstract: A new computer code for performing BWR in-core and out-of-core fuel cycle optimization for multiple cycles simultaneously has been developed. Parallel simulated annealing (PSA) is used to optimize the new fuel inventory and placement of new and reload fuel for each cycle considered. Several algorithm improvements were implemented and evaluated. The most significant of these are variable sampling probabilities and sampling new fuel types from an ordered array. A heuristic control rod pattern (CRP) search algorithm was also implemented, which is useful for single CRP determinations, however, this feature requires significant computational resources and is currently not practical for use in a full multi-cycle optimization. The PSA algorithm was demonstrated to be capable of significant objective function reduction and finding candidate loading patterns without constraint violations. The use of variable sampling probabilities was shown to reduce runtime while producing better results compared to using constant sampling probabilities. Sampling new fuel types from an ordered array was shown to have a mixed effect compared to random new fuel type sampling, whereby using both random and ordered sampling produced better results but required longer runtimes.

  1. BWR stability analysis with three-dimensional transient code

    International Nuclear Information System (INIS)

    Recently, neutron flux oscillations of two different modes were observed in several foreign BWR plants. One is core wide oscillation mode which is characterized by a phenomenon that neutron flux oscillates in-phase over a whole core. At La Salle 2 plant (U.S.A.), the amplitude of core wide neutron flux oscillation grew considerably large to result in a reactor scram, which aroused great concern about BWR stability. The other is regional oscillation mode which is characterized by the phenomenon, as typically observed at Caorso plant (Italy), that neutron flux of a half core oscillates out-of-phase to that of the other half core. These neutron flux oscillation phenomena were caused by nuclear-thermal hydraulic coupled instability and requires an evaluation study on oscillation detectability and effect on fuel integrity. Particularly, the regional oscillation mode requires three-dimensional analysis since it may bring about locally large amplitude power oscillation. For this reason, analysis was done with the three-dimensional transient code TOSDYN-2 to study reactor condition which causes the regional oscillation and also to evaluate fuel thermal margin under the neutron flux oscillations of these two instability modes. (author)

  2. TRAB, a transient analysis program for BWR. Part 1

    International Nuclear Information System (INIS)

    TRAB is a transient analysis program for BWR. The present report describes its principles. The program has been developed from TRAWA-program. It models the interior of the pressure vessel and related subsystems of BWR viz. reactor core, recirculation loop including the upper part of the vessel, recirculation pumps, incoming and outgoing flow systems, and control and protection systems. Concerning core phenomena and all flow channel hydraulics the submodels are one-dimensional of main features. The geometry is very flexible. The program has been made particularly to simulate various reactivity transients, but it is applicable more generally to reactor incidents and accidents in which no flow reversal or no emptying of the circuit must occur below the water level. The program is extensively supplied by input and output capabilities. The user can act upon the simulation of a transient by defining external disturbances, scheduled timevariations for any system variable, by modeling new subsystems, which are representable with ordinary linear differential equations, and by defining relations of functional form between system variables. The run of the program can be saved and restarted. (author)

  3. Standard Technical Specifications, General Electric Plants, BWR/6

    International Nuclear Information System (INIS)

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

  4. BWR Servicing and Refueling Improvement Program: Phase I summary report

    Energy Technology Data Exchange (ETDEWEB)

    Perry, D.R.

    1978-09-01

    Under the U.S. Department of Energy sponsorship, General Electric Co. (GE) undertook a study of boiling water reactor (BWR) refueling outages for the purpose of recommending the development and demonstration of critical path time savings improvements. The Tennessee Valley Authority (TVA) joined the study as a subcontractor, providing monitoring assistance and making the Browns Ferry Site available for improvement demonstrations. Agreement was also reached with Georgia Power Co., Power Authority of the State of New York, and Commonwealth Edison Co. for monitoring and data collection at Hatch 1, FitzPatrick, and Quad Cities 1 nuclear plants, respectively. The objective was to identify, develop, and demonstrate improved refueling, maintenance, and inspection procedures and equipment. The improvements recommended in this study are applicable to BWR nuclear plants currently in operation as well as those in the design and construction phases. The recommendations and outage information can be used as a basis to plan and conduct the first outages of new plants and to improve the planning and facilities of currently operating plants. Many of the recommendations can readily be incorporated in plants currently in the design and construction phases as well as in the design of future plants. Many of these recommended improvements can be implemented immediately by utilities without further technical development.

  5. Protecting AREVA ATRIUM™ BWR fuel from debris fretting failure

    International Nuclear Information System (INIS)

    Historically, debris fretting has been the leading cause of fuel rod failure in BWR fuel assemblies, costing the industry millions of dollars in lost generation and negatively impacting the working area of plant site personnel. In this paper the focus will be on recent BWR fuel product innovation designed to eliminate debris related failures. Experience feedback from more than three decades of operation history with non-line-of-sight FUELGUARD™ lower tie plate debris filters will be presented. The development and relative effectiveness of successive generations of filtration technology will be discussed. It will be shown that modern, state of the art debris filters are an effective defense against debris fretting failure. Protective measures extend beyond inlet nozzle debris filters. The comprehensive debris resistance features built into AREVA’s newest fuel design, the ATRIUM™ 11, reduce the overall risk of debris entrapment as well as providing a degree of protection from debris that may fall down on the fuel assembly from above, e.g., during refueling operations. The positive recent experience in a debris sensitive plant will be discussed showing that the combination of advanced fuel technology and a robust foreign material exclusion program at the reactor site can eliminate the debris fretting failure mechanism. (author)

  6. Logical model for the control of a BWR turbine

    International Nuclear Information System (INIS)

    In this work a design of a logical model is presented for the turbine control of a nuclear power plant with a BWR like energy source. The model is sought to implement later on inside the thermal hydraulics code of better estimate RELAP/SCDAPSIM. The logical model is developed for the control and protection of the turbine, and the consequent protection to the BWR, considering that the turbine control will be been able to use for one or several turbines in series. The quality of the present design of the logical model of the turbine control is that it considers the most important parameters in the operation of a turbine, besides that they have incorporated to the logical model the secondary parameters that will be activated originally as true when the turbine model is substituted by a detailed model. The development of the logical model of a turbine will be of utility in the short and medium term to carry out analysis on the turbine operation with different operation conditions, of vapor extraction, specific steps of the turbine to feed other equipment s, in addition to analyze the separate and the integrated effect. (Author)

  7. Standard Technical Specifications, General Electric plants, BWR/4

    International Nuclear Information System (INIS)

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  8. Managing the aging of BWR control rod drive systems

    International Nuclear Information System (INIS)

    This Phase I Nuclear Plant Aging Research (NPAR) study examines the aging phenomena associated with BWR control and rod drive mechanisms (CRDMs) and assesses the merits of various methods of ''imaging'' this aging. Information for this study was acquired from (1) the results of a special CRDM aging questionnaire distributed to each US BWR utility, (2) a first-of-its-kind workshop held to discuss CRDM aging and maintenance concerns, (3) an analysis of the Nuclear Plant Reliability Data System (NPRDS) failure cases attributed to the control rod drive (CRD) system, and (4) personal information exchange with nuclear industry CRDM maintenance experts. The report documenting the findings of this research, NUREG-5699, will be published this year. Nearly 23% of the NPRDS CRD system component failure reports were attributed to the CRDM. The CRDM components most often requiring replacement due to aging are the Graphitar seals. The predominant causes of aging for these seals are mechanical wear and thermal embrittlement. More than 59% of the NPRDS CRD system failure reports were attributed to components that comprise the hydraulic control unit (HCU). The predominant HCU components experiencing the effects of service wear and aging are value seals, discs, seats, stems, packing, and diaphragms

  9. BWR stability analysis with the BNL Engineering Plant Analyzer

    International Nuclear Information System (INIS)

    March 9, 1989 instability at the LaSalle-2 Power Plant and more than ninety related BWR transients have been simulated on the BNL Engineering Plant Analyzer (EPA). Power peaks were found to be potentially seventeen times greater than the rated power, flow reversal occurs momentarily during large power oscillations, the fuel centerline temperature oscillates between 1,030 and 2,090 K, while the cladding temperature oscillates between 560 and 570 K. The Suppression Pool reaches its specified temperature limit either never or in as little as 4.3 minutes, depending on operator actions and transient scenario. Thermohydraulic oscillations occur at low core coolant flow (both Recirculation Pumps tripped), with sharp axial or redial fission power peaking and with partial loss of feedwater preheating while the feedwater is flow kept high to maintain coolant inventory in the vessel. Effects from BOP system were shown to influence reactor stability strongly through dosed-loop resonance feedback. High feedwater flow and low temperature destabilize the reactor. Low feedwater flow restabilizes the reactor, because of steam condensation and feedwater preheating in the downcomer, which reduces effectively the destabilizing core inlet subcooling. The EPA has been found to be capable of analyzing BWR stability '' shown to be effective for scoping calculations and for supporting accident management

  10. Study of behavior on bonding and failure mode of pressurized and doped BWR fuel rod

    International Nuclear Information System (INIS)

    The study of transient behavior on the bonding and the failure mode was made using the pressurized/doped 8 x 8 BWR type fuel rod. The dopant was mullite minerals consisted mainly of silicon and aluminum up to 1.5 w/o. Pressurization of the fuel rod with pure helium was made to the magnitude about 0.6 MPa. As a reference, the non-pressurized/non-doped 8 x 8 BWR fuel rod and the pressurized/7 x 7 BWR fuel rod up to 0.6 MPa were prepared. Magnitude of energy deposition given to the tested fuel rods was 248, 253, and 269 cal/g·fuel, respectively. Obtained results from the pulse irradiation in NSRR are as follows. (1) It was found from the experiment that alternation of the fuel design by the adoption of pressurization up to 0.6 MPa and the use of wider gap up to 0.38 mm could avoid the dopant BWR fuel from the overall bonding. The failure mode of the present dopant fuel was revealed to be the melt combined with rupture. (2) The time of fuel failure of the pressurized/doped 8 x 8 BWR fuel defected by the melt/rupture mode is of order of two times shorter than that of the pressurized/ 7 x 7 BWR defected by the rupture mode. Failure threshold of the pressurized/doped 8 x 8 BWR BWR tended to be lower than that of non-pressurized/non-doped 8 x 8 BWR one. Cracked area of the pressurized/doped 8 x 8 BWR was more wider and magnitude of oxidation at the place is relatively larger than the other tested fuels. (3) Failure mode of the non-pressurized/ 8 x 8 BWR fuel rod was the melt/brittle accompanied with a significant bonding at failed location. While, failure mode of the pressurized/ 7 x 7 BWR fuel rod was the cladding rupture accompanied with a large ballooning. No bonding at failed location of the latter was observed. (author)

  11. Reciclado de las aguas de decapado

    Directory of Open Access Journals (Sweden)

    López, F. A.

    1998-05-01

    Full Text Available Pickling liquors from steel industry, listed as hazardous wastes in most industrializated countries, have been treated by means of several procedures in order to recover the iron and other metals and to obtain an environmental friendly effluent. Depending on the treatment employed, different valuable ferrous products have been obtained. Ammoniojarosite and zinc ferrite were precipitated from the previously oxidised ferrous solutions.

    En la mayoría de los países industrializados, se incluyen las aguas de decapado, tanto las procedentes de los aceros al carbono como de aceros inoxidables, dentro de las listas de residuos tóxicos y peligrosos. Se presentan en este trabajo los resultados obtenidos en las investigaciones realizadas en los últimos años en los que se ha estudiado el tratamiento y recuperación de aguas de decapado de aceros comunes e inoxidables. Su tratamiento se ha enfocado hacia la consecución de dos objetivos: la recuperación del contenido total de metales y la obtención de un efluente de menor impacto ambiental. Se presentan los procedimientos estudiados para la obtención de compuestos de hierro, amoniojarosita y ferritas de zinc, con cierto valor añadido.

  12. The Agua Salud Project, Central Panama

    Science.gov (United States)

    Stallard, R. F.; Elsenbeer, H.; Ogden, F. L.; Hall, J. S.

    2007-12-01

    The Agua Salud Project utilizes the Panama Canal's central role in world commerce to focus global attention on the ecosystem services provided by tropical forests. It will be the largest field experiment of its kind in the tropics aimed at quantifying the environmental services (water, carbon, and biodiversity) provided by tropical forests. The Agua Salud Watershed is our principal field site. This watershed and the headwaters of several adjacent rivers include both protected mature forests and a wide variety of land uses that are typical of rural Panama. Experiments at the scale of entire catchments will permit complete water and carbon inventories and exchanges for different landscape uses. The following questions will be addressed: (1) How do landscape treatments and management approaches affect ecosystem services such as carbon storage, water quality and quantity, dry- season water supply, and biodiversity? (2) Can management techniques be designed to optimize forest production along with ecosystem services during reforestation? (3) Do different tree planting treatments and landscape management approaches influence groundwater storage, which is thought to be critical to maintaining dry-season flow, thus insuring the full operation of the Canal during periods of reduced rainfall and severe climatic events such as El Niño. In addition we anticipate expanding this project to address biodiversity, social, and economic values of these forests.

  13. LECTURAS DEL AGUA (SÍMBOLOS, ECOCRÍTICA Y CULTURA DEL AGUA

    Directory of Open Access Journals (Sweden)

    Eloy Martos Núñez

    2012-08-01

    Full Text Available Existen diversos paradigmas sobre el estudio del agua que inciden en ella desde distintos puntos de vista. La gestión del agua es abordada desde las ciencias físicas y geológicas, y se soporta sobre tecnologías como la ingeniería hidráulica. En el aspecto histórico-social, se subraya la importancia de considerar el agua no como un recurso como parte esencial de una cosmovisión que vertebra el patrimonio cultural de una comunidad. Por ejemplo, en el estudio de los desastres (inundaciones, plagas, etc. se ha puesto el énfasis en los datos hidroclimáticos, las respuestas sociales o la vulnerabilidad social. Sin embargo, la ecocrítica ha subrayado el papel de las fabulaciones folklóricas y de los Imaginarios en general para aportar una comprensión holística del problema. Los discursos fabulados admonitorios sobre las aguas y sus riesgos subrayan la importancia de estos lugares de memoria y de reforzar las identidades a través de estas ecoficciones y rituales. Se convierten, pues, en tradiciones útiles porque en realidad hablan de la sostenibilidad, la ética y la necesidad de preservar la memoria y la identidad cultural de la comunidad, frente a la depredación de la Naturaleza. De este modo, el conocimiento de esta cultura del agua no sólo contribuye a la adquisición de las competencias básicas de la educación, y en particular, a la educación literaria y del patrimonio, sino que contribuye a la gobernanza del agua y a la gestión sostenible y responsable de los recursos hídricos. Como indica E. Morin, la lectura y la literatura son una escuela de complejidad, y estos mitos inciden siempre en la multicausalidad de las acciones humanas.http://dx.doi.org/10.14572/nuances.v22i23.1749

  14. Precio y manejo del agua urbana en México

    Directory of Open Access Journals (Sweden)

    Gregorio Castro Rosales

    2015-01-01

    Full Text Available Este trabajo propone evaluar el potencial del precio que pagan los usuarios como ins - trumento para el manejo de la demanda urbana de agua en México. Nuestros resulta - dos basados en un análisis de datos provenientes de cientos de organismos operadores de agua potable del país, revelan que la demanda de agua sí es sensible al precio, tal y como se ha señalado en otros estudios. No obstante, encontramos también que la demanda es aún mucho más sensible al efecto del crecimiento poblacional y económi - co. Por lo tanto, considerando la dinámica demográfica, urbana y económica del país, un aumento en el precio del agua en sí no podría contribuir significativamente a la estabilización de los requerimientos nacionales de extracción de agua para uso urbano. Además, nuestro análisis de los determinantes del precio del agua urbana revela que los organismos operadores pasan sistemáticamente el costo de sus ineficiencias técnicas y financieras a los usuarios, por lo que un aumento en el precio del agua tampoco podría contribuir al saneamiento de sus finanzas. Concluimos que para un manejo efectivo, eficiente y sustentable del uso urbano de agua, resulta imprescindible un cambio de fondo en la manera en que operan los sistemas urbanos de agua.

  15. Studies of fragileness in steels of vessels of BWR reactors; Estudios de fragilizacion en aceros de vasija de reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Robles, E.F.; Balcazar, M.; Alpizar, A.M.; Calderon, B.E. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2003-07-01

    The structural materials with those that are manufactured the pressure vessels of the BWR reactors, suffer degradation in its mechanical properties mainly to the damage taken place by the fast neutrons (E > 1 MeV) coming from the reactor core. Its are experimentally studied those mechanisms of neutron damage in this material type, by means of the irradiation of steel vessel in experimental reactors to age them quickly. Alternatively it is simulated the neutron damage by means of irradiation of steel with heavy ions. In this work those are shown first results of the damage induced by irradiation from a similar steel to the vessel of a BWR reactor. The irradiation was carried out with fast neutrons (E > 1 MeV, fluence of 1.45 x 10{sup 18} n/cm{sup 2}) in the TRIGA MARK lll reactor and separately with Ni{sup +3} ions in a Tandetrom accelerator, E = 4.8 MeV and range of the ionic flow of 0.1 to 53 iones/A{sup 2}. (Author)

  16. System control model of a turbine for a BWR; Modelo del sistema de control de una turbina para un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Vargas O, Y. [Universidad del Valle de Mexico, Campus Toluca, Av. Las Palmas No. 136, Col. San Jorge Pueblo Nuevo, 52140 Metepec, Estado de Mexico (Mexico); Amador G, R.; Ortiz V, J.; Castillo D, R.; Delfin L, A. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)], e-mail: rodolfo.amador@inin.gob.mx

    2009-10-15

    In this work is presented a design of a control system of a turbine for a nuclear power plant with a BWR like energy source. The model seeks to implement later on at thermal hydraulics code of better estimate RELAP/SCDAPSIM. The model is developed for control and protection of turbine, and the consequent protection to the BWR, considering that the turbine control could be employed for one or several turbines in series. The quality of present designs of control pattern of turbine it is that it considers the parameters more important in the operation of a turbine besides that is has incorporated at control the secondary parameters that will be activated originally as true when the turbine model is substituted by a model more detailed. The development of control model of a turbine will be good in short and medium term to realize analysis about the operation of turbine with different operation conditions, of vapor extraction specific steps of turbine to feed other equipment s, besides analyzing the separate effect and integrated effect. (Author)

  17. El acceso al agua para consumo humano en Colombia

    OpenAIRE

    Martha Yánez Contreras; Karina Acevedo González

    2013-01-01

    El acceso al agua es un derecho humano que se debe garantizar sin ninguna discriminación. Este artículo examina la existencia de inequidades en el ejercicio de este derecho mediante un análisis discriminante que identifica los factores que explican las diferencias en la calidad del agua para consumo humano entre los municipios colombianos en 2009. Los resultados indican que existen inequidades en el acceso al agua potable. En particular, los municipios más pobres registran los niveles de cali...

  18. El acceso al agua para consumo humano en Colombia

    Directory of Open Access Journals (Sweden)

    Martha Yánez Contreras

    2013-12-01

    Full Text Available El acceso al agua es un derecho humano que se debe garantizar sin ninguna discriminación. Este artículo examina la existencia de inequidades en el ejercicio de este derecho mediante un análisis discriminante que identifica los factores que explican las diferencias en la calidad del agua para consumo humano entre los municipios colombianos en 2009. Los resultados indican que existen inequidades en el acceso al agua potable. En particular, los municipios más pobres registran los niveles de calidad más bajos.

  19. Abasto del agua en la frontera norte de Tamaulipas

    Directory of Open Access Journals (Sweden)

    Jesús FRAUSTO ORTEGA

    2016-01-01

    Full Text Available El trabajo ref lexiona sobre el abasto de agua potable en los municipios fronterizos del norte de Tamaulipas, a partir de la perspectiva del derecho humano al agua ( DHA . Se responde la pregunta: ¿cómo se ha desarrollado la cobertura de agua potable en esos municipios? Se revisan estadísticas del Inegi de 1990 a 2010, ejemplares del Periódico o f icial del estado y diversas fuen - tes secundarias. Se encuentra que hay coberturas altas, tanto en agua potable como en drenaje, superiores a los promedios nacional y regional. Sin embargo, aún existe población sin acceso a estos servicios en sus viviendas y que, utilizando el DHA como una herramienta de gestión, puede demandar la dotación de esos servicios.

  20. Agua subterránea, deterioro de calidad y reserva

    OpenAIRE

    Auge, Miguel

    2008-01-01

    El agua en general y la subterránea en particular es un recurso limitado en nuestro planeta, donde más del 97% es salada y se concentra en mares y océanos. Del resto, alrededor del 2% constituye los casquetes polares en forma de hielo. Le sigue en magnitud el agua subterránea, cuya reserva hasta 1.000 m de profundidad se estima en el 0,5% del total, mientras que el volumen instantáneo de agua superficial llega a sólo el 0,02% y entre el agua del suelo y la atmosférica, componen algo más del 0...

  1. Tritium in liquid phase in a BWR-5 like Laguna Verde; Tritio en fase liquida en un BWR-5 como Laguna Verde

    Energy Technology Data Exchange (ETDEWEB)

    Tijerina S, F.; Vargas A, A.; Cardenas J, J., E-mail: francisco.tijerina@cfe.gob.mx [Comision Federal de Electricidad, Central Nucleoelectrica Laguna Verde, Subgerencia de Ingenieria, Carretera Veracruz-Medellin Km 7.5, Veracruz (Mexico)

    2011-11-15

    In boiling water reactors (BWR), the tritium (H{sub 3}) takes place mainly as a result of ternary fissions in the nuclear reactors, of those which 75% are in gaseous form and 25% in liquid form. In the liquid phase, the tritium is transported to the pipes of the primary coolant toward condensed tanks or tanks of drainage excesses of radioactive equipment, located in external areas of a BWR, as well as to the processes of radioactive wastes to be able to be directed to the liquid effluents. For that reason, is necessary to know the possible routes of the transport and processes of the tritium in a BWR to control this radioisotope in the site of the event of leaks in equipment s and buried pipes, avoiding that emigrates toward underground flowing and an impact to the environment and to the people in general. (Author)

  2. Lahar hazards at Agua volcano, Guatemala

    Science.gov (United States)

    Schilling, S.P.; Vallance, J.W.; Matías, O.; Howell, M.M.

    2001-01-01

    At 3760 m, Agua volcano towers more than 3500 m above the Pacific coastal plain to the south and 2000 m above the Guatemalan highlands to the north. The volcano is within 5 to 10 kilometers (km) of Antigua, Guatemala and several other large towns situated on its northern apron. These towns have a combined population of nearly 100,000. It is within about 20 km of Escuintla (population, ca. 100,000) to the south. Though the volcano has not been active in historical time, or about the last 500 years, it has the potential to produce debris flows (watery flows of mud, rock, and debris—also known as lahars when they occur on a volcano) that could inundate these nearby populated areas.

  3. El agua, el TLC y el agro

    Directory of Open Access Journals (Sweden)

    Claudia Sampedro Torres

    2006-11-01

    Full Text Available Este artículo de absoluta actualidad se refiere al tratamiento que el poder ejecutivo viene dando al tema del agro y los recursos de los cuales depende. Ya en prensa el tema de tierras, corrupción y violencia ha sido registrado en relación con el gobierno del presidente Uribe y el Incoder. Ahora se trata de examinar de qué manera el Incoder desmonta el manejo y propiedad de los distritos de adecuación de tierras de los cuales depende la actividad agropecuaria sin que para tal expropiación del recurso agua se requiera acudir a las instancias de un

  4. El mundo yanacona alrededor del agua

    Directory of Open Access Journals (Sweden)

    Sofía Camargo

    2013-09-01

    Full Text Available Este texto procura hacer una breve descripción del pueblo indígena Yanacona, que, a pesar de los atropellos que ha sufrido desde tiempos remotos, logra conservar su historia, y trabaja por el fortalecimiento de su cultura y el rescate de sus formas de vida. Los yanaconas han contrarrestado los distintos sincretismos culturales que representa el medio, conservan algunas características de los pueblos quechuas andinos y el vínculo que une al indígena con la naturaleza y su territorio, -el Macizo Colombiano-, y en particular, con el agua, concebida desde su cosmovisión como fuente de vida y punto de partida de la existencia.

  5. El agua, el TLC y el agro

    Directory of Open Access Journals (Sweden)

    Alfredo Suárez Mejía

    2006-01-01

    Full Text Available Este artículo de absoluta actualidad se re- fiere al tratamiento que el poder ejecutivo viene dando al tema del agro y los recursos de los cuales depende. Ya en prensa el tema de tierras, corrupción y violencia ha sido registrado en relación con el gobierno del presidente Uribe y el Incoder. Ahora se trata de examinar de qué manera el Incoder desmonta el manejo y propiedad de los distritos de adecuación de tierras de los cuales depende la actividad agropecuaria sin que para tal expropiación del recurso agua se requiera acudir a las instancias de un TLC. La hipertrofia de las posiciones contra el TLC ha permitido sin lugar a dudas que desde el derecho interno mientras se negocia se adelanten las normas que permiten las inversiones que interesan al espacio de la “integración comercial”

  6. Pensando al agua como parte del paisaje

    Directory of Open Access Journals (Sweden)

    Lorena Salvatelli

    2009-12-01

    Full Text Available El objetivo de este trabajo es discutir la importancia de los estudios de arqueología terrestre y subacuática como parte de un mismo proceso de interpretación del pasado. Se entiende que el registro arqueológico puede hallarse actualmente en una variedad de ambientes tanto terrestres como subacuáticos a causa de varias razones, como por ejemplo las oscilaciones de los niveles de agua ocurridas entre el Pleistoceno Final y el Holoceno Medio. Por lo tanto, se propone que para su recuperación debe utilizarse una metodología adaptada al medio ambiente en el cual se encuentre. En este sentido, es importante la interpretación integral del paisaje para acceder a la comprensión de la diversidad ambiental en la que se puede emplazar un sitio arqueológico, y en consecuencia poder “bucear” un registro integrado.

  7. New accomplishments of Ambiente & Agua scientific journal

    Directory of Open Access Journals (Sweden)

    Getulio Teixeira Batista

    2009-04-01

    Full Text Available Ambiente & Água – An Interdisciplinary Journal of Applied Science (Ambi-Agua was classified as B2 in the Interdisciplinary Area, the major thematic area of this journal, by CAPES classification system known as "Qualis". Also, the journal was registered in the Digital Object Identifier (DOI® System. Three other facts were accomplished: 1 all published articles since April, 2008 have the submitted and accepted dates stamped; 2 long-term preservation will be now secured in association with DOAJ - Lund University Libraries and the e-Depot of the National Library of the Netherlands (KB; and 3 we entered into an electronic licensing relationship with EBSCO Publishing to have full text of our journal in EBSCO Publishing's databases in the near future.

  8. Repercusiones sanitarias de la calidad del agua: los residuos de medicamentos en el agua

    Directory of Open Access Journals (Sweden)

    Cristina Postigo Rebollo

    2011-12-01

    Full Text Available Este trabajo resume varios estudios de monitorización de fármacos y drogas de abuso llevados a cabo en el medio ambiente acuático de las cuencas de los ríos Llobregat y Ebro con el fin de evaluar la calidad del agua en relación a la presencia de estas substancias y su potencial riesgo para la salud ambiental y pública. La identificación de estos compuestos aguas abajo del punto de vertido de las plantas depuradoras apunta a la descarga de agua residual tratada como la principal fuente de emisión de estos contaminantes en el medio acuático. El perfil de contaminación por fármacos fue bastante similar en ambas cuencas. No obstante, los índices de riesgo (HQ calculados para los fármacos en diferentes niveles tróficos (algas, dáfnidos y peces indican que los compuestos que presentan un mayor riesgo ecotóxico en el Llobregat son el sulfametoxazol (antibiótico sulfamida para las algas, el gemfibrozil (regulador de lípidos para las algas y los peces, el ácido clofíbrico (regulador de lípidos y la eritromicina (antibiótico macrólido para los dáfnidos, y el ibuprofeno (analgésico anti-inflamatorio para todos los eslabones tróficos. En el Ebro, los compuestos más problemáticos son el sulfametoxazol para las algas, y la eritromicina, el ácido clofíbrico y la fluoxetina (antidepresivo para los dáfnidos.Los niveles de drogas de abuso (y sus metabolitos determinados en la cuenca del Ebro son aproximadamente uno y dos órdenes de magnitud más bajos respectivamente que los determinados en las aguas de salida y de entrada a las depuradoras. Sin embargo, debido a la falta de datos sobre su ecotoxicidad, no se han podido calcular índices de riesgo.La presencia de estos compuestos (fármacos y drogas en aguas superficiales y de bebida aun no está regulada y, por lo tanto, no constituyen parámetros de obligado control. Aún es imprescindible seguir investigando para poder evaluar su posible efecto en la salud humana.

  9. Investigation of BWR [boiling water reactor] instability phenomena using RETRAN-03

    International Nuclear Information System (INIS)

    In 1988, LaSalle, a boiling water reactor (BWR)/5, experienced severe flux oscillations following a trip of both recirculation pumps. The flux oscillations were terminated by an automatic scram at 118% of rated neutron flux. As a result of this event, the U.S. Nuclear Regulatory Commission has asked the BWR utilities to develop procedural or hardware changes that will assure protection of all safety limits. The rapid growth of the oscillations at LaSalle, and the fact that previous stability analyses had predicted the plant to be very stable, emphasizes that a better understanding of this phenomenon is needed before the success of the long-term fixes can be assured. The intent of the Electric Power Research Institute's work was to use BWR transient methods to model reactor instabilities and investigate the factors that dominate this phenomenon. The one-dimensional transient code RETRAN-03 (Ref. 1) was used. The following conclusions are drawn: (1) RETRAN has demonstrated the ability to model BWR instability (nonlinear oscillations). (2) The general system behavior predicted by RETRAN in BWR stability analyses matches theoretical prediction and plant data. (3) These one-dimensional, time-domain results have increased the understanding of BWR stability phenomena and have helped optimize the long-term solutions being developed by the utilities

  10. Development of jet pump inspection equipments in BWR

    International Nuclear Information System (INIS)

    This paper describes development of the remotely operated equipments for jet pump ultrasonic testing (UT) in boiling water reactors (BWRs) to enhance the availability of operating nuclear power plants. Stress corrosion cracking (SCC) in the reactor internals has been a major concern in the BWR in recent years. The developed equipments can accomplish the appropriate positioning precision as an application of the Toshiba phased array immersion UT technique and enhance the jet pump inspection performance with a shorter duration and reducing the load for the installation of them. Three types of inspection equipments are developed to cover the outside and inside of the jet pump inlet mixer and the diffuser without disassembling the inlet mixer and the outside of the jet pump riser elbow. Their configurations and specifications are shown in the paper respectively. (author)

  11. Rapid dewatering of Powdex resins at a BWR

    International Nuclear Information System (INIS)

    For most BWR's a large portion of their radioactive waste produced is water demineralization resins, both powdered and bead. In order to minimize the quantities of resins produced, proper demineralizer operation, volume reduction and minimization techniques are relevant to spent resin dewatering and packaging. To meet burial requirements spent resin needs to be dewatered and packaged properly. Methods of dewatering spent resins have included centrifuge separation and pulling water out of the resin with a diaphragm pump. Various vendors are offering systems that provide rapid dewatering and volume reduction using filter/liners in combination with vacuum pumps and air blowers. The various systems required a standardized test program for proper comparison and evaluation. The program is described in this paper

  12. Study of transient turbine shot without bypass in a BWR

    International Nuclear Information System (INIS)

    The study and analysis of operational transients are important for predicting the behavior of a system to short-terms events and the impact that would cause this transition. For the nuclear industry these studies are indispensable due to economic, environmental and social impacts that could result in an accident during the operation of a nuclear reactor. In this paper the preparation, simulation and analysis of results of a turbine shot transient, which is not taken into operation the bypass is presented. The study is realized for a BWR of 2027 MWt, to an intermediate cycle life and using the computer code Simulate-3K a depressurization stage of the vessel is created which shows the response of other security systems and gives a coherent prediction to the event presented type. (Author)

  13. Fault tree analysis on BWR core spray system

    International Nuclear Information System (INIS)

    Fault Trees which describe the failure modes for the Core Spray System function in the Browns Ferry Nuclear Plant (BWR 1065MWe) were developed qualitatively and quantitatively. The unavailability for the Core Spray System was estimated to be 1.2 x 10-3/demand. It was found that the miscalibration of four reactor pressure sensors or the failure to open of the two inboard valves (FCV 75-25 and 75-53) could reduce system reliability significantly. It was recommended that the pressure sensors would be calibrated independently. The introduction of the redundant inboard valves could improve the system reliability. Thus this analysis method was verified useful for system analysis. The detailed test and maintenance manual and the informations on the control logic circuits of each active component are necessary for further analysis. (author)

  14. Recent training technology of BWR operators using full scope simulators

    International Nuclear Information System (INIS)

    Nuclear power plants are being operated at high standards now in Japan. There are far few opportunities for operators to perform in challenging situations. To maintain skill and refinement, the simulator training is indispensable for them. BWR Operator Training Center (BTC) provides training courses according to the grade and duty of the operators. The training force constitutes of personnel from utilities', manufacturers' and also BTC-hired personnel. One of the big features of BTC training is composite team type. In this form of training, men from different plants make a team and help each other study. On the human factor viewpoint, error experience on simulators is one of the important items. Training on recognizing subtle symptom is an example of a recent development. Team training for actual crew is effective from various viewpoints. (author)

  15. Obtention control bars patterns for a BWR using Tabo search

    International Nuclear Information System (INIS)

    The obtained results when implementing the technique of tabu search, for to optimize patterns of control bars in a BWR type reactor, using the CM-PRESTO code are presented. The patterns of control bars were obtained for the designs of fuel reloads obtained in a previous work, using the same technique. The obtained results correspond to a cycle of 18 months using 112 fresh fuels enriched at the 3.53 of U-235. The used technique of tabu search, prohibits recently visited movements, in the position that correspond to the axial positions of the control bars, additionally the tiempotabu matrix is used for to manage a size of variable tabu list and the objective function is punished with the frequency of the forbidden movements. The obtained patterns of control bars improve the longitude of the cycle with regard to the reference values and they complete the restrictions of safety. (Author)

  16. Development of methodology for early detection of BWR instabilities

    International Nuclear Information System (INIS)

    Full text of publication follows: The objective of the work presented in this paper research, which is supported by the US Department of Energy under the NEER program, is to develop an early anomaly detection methodology in order to enhance safety, availability, and operational flexibility of Boiling Water Reactor (BWR) nuclear power plants. The technical approach relies on suppression of potential power oscillations in BWRs by detecting small anomalies at an early stage and taking appropriate prognostic actions based on an anticipated operation schedule. The model of coupled (two-phase) thermal-hydraulic and neutron flux dynamics, based on the US NRC coupled code TRACE/PARCS, is being utilized as a generator of time series data for anomaly detection at an early stage. The concept of the methodology is based on the fact that nonlinear systems show bifurcation, which is a change in the qualitative behavior as the system parameters vary. Some of these parameters may change on their own accord and account for the anomaly, while certain parameters can be altered in a controlled fashion. The non-linear, non-autonomous BWR system model considered in this research exhibits phenomena at two time scales. Anomalies occur at the slow time scale while the observation of the dynamical behavior, based on which inferences are made, takes place at the fast time scale. It is assumed that: (i) the system behavior is stationary at the fast time scale; and (ii) any observable non-stationary behavior is associated with parametric changes evolving at the slow time scale. The goal is to make inferences about evolving anomalies based on the asymptotic behavior derived from the computer simulation. However, only sufficient changes in the slowly varying parameter may lead to detectable difference in the asymptotic behavior. The need to detect such small changes in parameters and hence early detection of an anomaly motivate the utilized stimulus-response approach. In this approach, the model

  17. BWR Full Integral Simulation Test (FIST). Phase I test results

    International Nuclear Information System (INIS)

    A new full height BWR system simulator has been built under the Full-Integral-Simulation-Test (FIST) program to investigate the system responses to various transients. The test program consists of two test phases. This report provides a summary, discussions, highlights and conclusions of the FIST Phase I tests. Eight matrix tests were conducted in the FIST Phase I. These tests have investigated the large break, small break and steamline break LOCA's, as well as natural circulation and power transients. Results and governing phenomena of each test have been evaluated and discussed in detail in this report. One of the FIST program objectives is to assess the TRAC code by comparisons with test data. Two pretest predictions made with TRACB02 are presented and compared with test data in this report

  18. BWR Full Integral Simulation Test (FIST). Phase I test results

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, W S; Alamgir, M; Sutherland, W A

    1984-09-01

    A new full height BWR system simulator has been built under the Full-Integral-Simulation-Test (FIST) program to investigate the system responses to various transients. The test program consists of two test phases. This report provides a summary, discussions, highlights and conclusions of the FIST Phase I tests. Eight matrix tests were conducted in the FIST Phase I. These tests have investigated the large break, small break and steamline break LOCA's, as well as natural circulation and power transients. Results and governing phenomena of each test have been evaluated and discussed in detail in this report. One of the FIST program objectives is to assess the TRAC code by comparisons with test data. Two pretest predictions made with TRACB02 are presented and compared with test data in this report.

  19. TRAB - A transient analysis program for BWR. Part 2

    International Nuclear Information System (INIS)

    TRAB is a transient analysis code for BWRs developed at the Technical Research Centre of Finland. It models the phenomena in the interior of the BWR pressure vessel and in related subsystems. The core model of TRAB can be used separately for LWR modelling. For PWR modelling the core model of TRAB is connected to circuit model SMABRE to form the SMATRA code. This report is a user's manual and documents the structure, contents and preparation of input for TRAB. The structure of TRAB input is very flexible, featuring input groups and subgroups identified with keywords and given in any order as well as data items in free format, freely mixed with explanatory texts. Users interface of the code can be used for modelling within input: through normal input it is possible to create new submodels. These may be functional or tabulated dependencies of the code variables, different types of delays, or ordinary linear differential equations

  20. Política descentralizadora del agua potable

    Directory of Open Access Journals (Sweden)

    María de los Ángeles Cienfuegos Velasco

    2012-01-01

    Full Text Available Hablar de política descentralizadora en relación con la gestión del agua potable implica aclarar el significado de descentralización y su aplicación en México. En este trabajo se ofrecen algunas aportaciones al concepto y se describe el proceso que, de hecho, ha ocurrido en la política de descentralización del agua en el país.

  1. PWR and BWR spent fuel assembly gamma spectra measurements

    Science.gov (United States)

    Vaccaro, S.; Tobin, S. J.; Favalli, A.; Grogan, B.; Jansson, P.; Liljenfeldt, H.; Mozin, V.; Hu, J.; Schwalbach, P.; Sjöland, A.; Trellue, H.; Vo, D.

    2016-10-01

    A project to research the application of nondestructive assay (NDA) to spent fuel assemblies is underway. The research team comprises the European Atomic Energy Community (EURATOM), embodied by the European Commission, DG Energy, Directorate EURATOM Safeguards; the Swedish Nuclear Fuel and Waste Management Company (SKB); two universities; and several United States national laboratories. The Next Generation of Safeguards Initiative-Spent Fuel project team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins, (3) estimate the plutonium mass, (4) estimate the decay heat, and (5) determine the reactivity of spent fuel assemblies. This study focuses on spectrally resolved gamma-ray measurements performed on a diverse set of 50 assemblies [25 pressurized water reactor (PWR) assemblies and 25 boiling water reactor (BWR) assemblies]; these same 50 assemblies will be measured with neutron-based NDA instruments and a full-length calorimeter. Given that encapsulation/repository and dry storage safeguards are the primarily intended applications, the analysis focused on the dominant gamma-ray lines of 137Cs, 154Eu, and 134Cs because these isotopes will be the primary gamma-ray emitters during the time frames of interest to these applications. This study addresses the impact on the measured passive gamma-ray signals due to the following factors: burnup, initial enrichment, cooling time, assembly type (eight different PWR and six different BWR fuel designs), presence of gadolinium rods, and anomalies in operating history. To compare the measured results with theory, a limited number of ORIGEN-ARP simulations were performed.

  2. Spectral effects in cavitation of BWR jet pumps

    International Nuclear Information System (INIS)

    BWR jet-pumps vibrate violently when the recirculation drive flow becomes sufficiently high that cavitation occurs in the throat section at the local temperature of the suction flow. This process occurs rapidly as the fluid flows through the nozzle throat and while mixing of the drive and suction flows is in process. Continued mixing during transit through the throat eventually results in a pressure recovery to the saturation pressure and subsequent collapse of the voids near the entrance to the diffuser. The liquid surrounding a vapor volume, or void, performs work during void collapse. The result is that energy is deposited in the liquid and converted locally to an over-pressure, or sonic wave. The power contained in this wave may be very large, since it is deposited in the relatively short void collapse time. The frequency spectrum of the sonic excitation depends on the temporal nature of the collapse, including multiple events when the void is composed of a swarm of bubbles of various sizes. The frequency spectrum of a single spherical void collapse is calculated from the bubble collapse dynamics as it propagates in an increasing ambient pressure field that is a function of drive flow rate, Qd. It is shown that the void collapse is a tandem process in the time frame of the bubble swarm. These considerations lead to comparisons with strain-gauge data taken in BWR tests with the head off. Averaged micro-strain data is compared with the calculated values at several pump speeds, then fit to the data set. The normalized result is in excellent agreement, indicating that the void collapse mechanism is the most likely source of vibration excitation in the jet pump structure

  3. Spectral effects in cavitation of BWR jet pumps

    Energy Technology Data Exchange (ETDEWEB)

    Terhune, J.H.; Karim-Panahi, K. [GE Nuclear Energy, San Jose, CA (United States)

    1996-12-01

    BWR jet-pumps vibrate violently when the recirculation drive flow becomes sufficiently high that cavitation occurs in the throat section at the local temperature of the suction flow. This process occurs rapidly as the fluid flows through the nozzle throat and while mixing of the drive and suction flows is in process. Continued mixing during transit through the throat eventually results in a pressure recovery to the saturation pressure and subsequent collapse of the voids near the entrance to the diffuser. The liquid surrounding a vapor volume, or void, performs work during void collapse. The result is that energy is deposited in the liquid and converted locally to an over-pressure, or sonic wave. The power contained in this wave may be very large, since it is deposited in the relatively short void collapse time. The frequency spectrum of the sonic excitation depends on the temporal nature of the collapse, including multiple events when the void is composed of a swarm of bubbles of various sizes. The frequency spectrum of a single spherical void collapse is calculated from the bubble collapse dynamics as it propagates in an increasing ambient pressure field that is a function of drive flow rate, Q{sub d}. It is shown that the void collapse is a tandem process in the time frame of the bubble swarm. These considerations lead to comparisons with strain-gauge data taken in BWR tests with the head off. Averaged micro-strain data is compared with the calculated values at several pump speeds, then fit to the data set. The normalized result is in excellent agreement, indicating that the void collapse mechanism is the most likely source of vibration excitation in the jet pump structure.

  4. El régimen jurídico de las aguas para usos agrícolas: aguas subterráneas

    Directory of Open Access Journals (Sweden)

    Fernando Brebbia

    2015-01-01

    Full Text Available Como ha señalado el profesor Adolfo Gelsi Bidart la relación entre tierra yagua es alguno de los aspectos que el derecho agrario debe tener en cuenta y ello importa establecer si la regulación de las aguas compete al derecho agrario, constituye una disciplina autónoma, o bien si su estudio corresponde a diversas ramas del derecho cada una de las cuales debe ocuparse de examinar determinados aspectos, o mejor, de distintas formas de su uso y aprovechamientol (...Contenido: Derecho agrario y derecho de aguas. Algunos datos estadísticos acerca del agua. Los usos del agua. Aguas públicas y aguas privadas. La utilización del agua para la agricultura. El tratamiento legal de las aguas para la agricultura en los países del Mercosur: Argentina, Brasil, Paraguay, Uruguay. Evolución legislativa del régimen de las aguas subterráneas en el derecho agrario comparado. Modernas tendencias sobre el dominio de las aguas subterráneas. Las leyes de aguas de España e Italia

  5. Accumulation of operator workload data by using A-BWR training simulator

    International Nuclear Information System (INIS)

    Human-machine interface (HMI) of A-BWR has been developed in order to improve operational safety, reliability and to reduce workload. A-BWR HMI is fully computerized. JNES (Japan Nuclear Energy Safety Organization) and BTC (BWR Operator Training Center Corporation) have accumulated the operator workload quantitative data, related to the observation and operation at typical transient conditions, in order to evaluate the difference of operational workloads between A-BWR HMI and conventional type HMI. The workload evaluation shows the following results: - The workload density (observation and operation frequencies per unit time) of ABWR just after the plant trip is less than that of BWR-5. - At stable conditions after the transient, the workload density of ABWR becomes higher comparing that of BWR-5. A-BWR alarm system may increase the workload density caused by alarm multi-layer structure, because an operator has to use the flat and/or the CRT display to pursue every alarm. The analysis of shift team training at BTC shows that total workload is reduced at ABWR but alarm confirmation work still remains as burden. These results show some modifications might be needed for future HMI. To grasp the tendency of operator workload difference by the control panel type difference, the operator workload quantitative data have accumulated using ABWR type simulator and conventional type simulator at the same typical transient condition. These data were arranged operation frequency data, number of alarm generating data and number of switching CRT pictures data according to plant behaviour. The ABWR type HMI's characteristic have become clear by these operator workload data and the team characteristic evaluation data which BTC evaluated comparing the team performance difference of HMI type

  6. ATRIUMTM Fuel - Continuous Upgrading for High Duty BWR Plants

    International Nuclear Information System (INIS)

    AREVA NP is a supplier of nuclear fuel assemblies and associated core components to Boiling Water Reactors worldwide, representing today more than 60 000 fuel assemblies. Since first delivered in 1992, ATRIUMTM10 fuel assemblies have now been supplied to a total of 32 BWR plants in the US, Europe, and Asia resulting in an operating experience over 20 000 fuel assemblies. Among them, the latest versions are ATRIUMTM 10XP and ATRIUMTM 10XM fuel assemblies which have been delivered to several utilities worldwide. During six years of operation experience reaching a maximum fuel assembly burnup of 66 MWd/kgU, no fuel failure of ATRIUMTM 10XP/XM occurred. Regular upgrading of the fuel assemblies' reliability and performance has been made possible thanks to AREVA NP's continuous improvement process and the 'Zero tolerance for failure' program. In this frame, the in-core behavior follow-up, manufacturing experience feedback and customer expectations are the bases for setting improvement management objectives. As an example, most fuel rod failures observed in the past years resulted from debris fretting and Pellet Cladding Interaction (PCI) generally caused by Missing Pellet Surface. To address these issues, the development of the Improved FUELGUARDTM debris filter was initiated and completed while implementation of chamfered pellets and Cr doped fuel will address PCI aspects. In the case of fuel channel bow issue, efforts to ensure dimensional stability at high burnup levels and under challenging corrosion environments have been done resulting in material recommendations and process developments. All the described solutions will strongly support the INPO goal of 'Zero fuel failures by 2010'. In a longer perspective, the significant trend in nuclear fuel operation is to increase further the discharge burnup and/or to increase the reactor power output. In the majority of nuclear power plants worldwide, strong efforts in power up-rating were made and are still ongoing. Most

  7. Analysis of the behavior of irradiated BWR fuel rod in storage dry conditions; Analisis del comportamiento de una barra combustible irradiada BWR en condiciones de almacenamiento en seco

    Energy Technology Data Exchange (ETDEWEB)

    Munoz, A.; Montes, D.; Ruiz-Hervias, J.; Munoz-Reja, C.

    2014-07-01

    In order to complete previous studies of creep on PWR sheath material, developed a joint experimental program by CSN, ENRESA and ENUSA about BWR (Zircaloy-2) sheath material. This program consisted in creep tests and then on the material under creep, compression testing diametral obtaining the permissible displacement of the sheath to break. (Author)

  8. The Japanese utilities' requirements for a next century BWR

    International Nuclear Information System (INIS)

    This paper reports on the progress of studies to establish a plant concept for a Boiling Water Reactor (BWR) of the next century. The studies were initiated in 1990 by the Japanese utilities, jointly with NSSS vendors, to investigate evolutionary and long term nuclear power plants. The plant concept is based on the evolution of the ABWR taking advantage of new technology. Fundamental plant philosophies are expressed by the following four desired characteristics: Economical, Benign to human, Simple, Flexible. According to these philosophies, concrete objectives of the plant design are reduction of operating burden and maintenance, increase of safety margin and flexibility to adjust to possible changes in economic circumstances in the years to come. The basic utilities' requirements for the new generation BWR were discussed based on the future social needs and the current operational experiences. Start of operation is to be in the 2010's when the early generation LWRs may need to be replaced. Plant power generation capacity will be about 1500 MWe since this level rating will be achievable by extrapolation of current technology. One important requirement is to achieve power generation costs competitive with other generation methods. An outline of the utilities' requirements follows: Operability; prevent inadvertent reactor scram and engineering safety system actuation due to single failure of normal duty systems or single operator error, achieve same load following capability as ABWR, design for plant availability of up to 90%, achieve plant design life of 60 years, maintain annual inspection period at less than 40 days, reduce maintenance activities in harsh environments, reduce employees' dose to less than that of ABWR, consider 'N+2' design to reduce peak loads during annual inspection. Safety margin; increase grace period for transient and accident events, adopt severe accident countermeasures, keep core damage frequency lower than that of ABWR and conditional

  9. Comparison of heat capacity and thermal time constant between BWR fuel and simulated heater rod

    Energy Technology Data Exchange (ETDEWEB)

    Iguchi, Tadashi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2000-10-01

    It is important to know the thermal characteristics of BWR fuel, i.e. heat capacity and thermal time constant, in order to evaluate the thermal hydraulics at BWR accidents and the events under thermal-hydraulic and neutronic coupling condition. Further, since the heater rod simulating BWR fuel is used in the tests for BWR accidents and for BWR thermal hydraulics coupled with neutronics, it is important to know the thermal characteristics of the heater rod. Therefore, the author investigated the thermal characteristics of BWR fuel and the heater rod by performing experiments and analyzing with J-TRAC code capable to analyze 2-dimensional heat conduction problem. The heat capacity per unit length of BWR fuel cp{rho}A (kJ/mK) was estimated to be 0.34 kJ/mK - 0.36 kJ/mK in 300 deg. C - 800 deg. C. The heat capacity of the heater rod was almost identical with each other regardless of the differences in rods and positions. It was higher with higher temperature. The heat capacity of the heater rod used in the test for BWR accidents was about 0.38 kJ/mK at 600 deg. C, which was about 9% higher than the average (0.35 kJ/mK) of BWR fuel. On the other hand, the heat capacity used in the test for BWR thermal hydraulics coupled with neutronics was about 0.42 kJ/mK at 600 deg. C, which was about 20% higher than the average of BWR fuel. Thermal time constant was affected by surface heat transfer coefficient, thermal diffusivity, and gap conductance. When the surface heat transfer coefficient is small, it controls the heat transfer and thermal time constant depends mainly on the surface heat transfer coefficient. When the surface heat transfer coefficient is large, the heat conduction controls the heat transfer and thermal time constant depends mainly on the thermal diffusivity. In the former case, one point heat transfer model is applicable and the thermal time constant is proportional to the inverse of the surface heat transfer coefficient. In this case, the thermal time

  10. Panama Canal Watershed Experiment- Agua Salud Project

    Science.gov (United States)

    Stallard, Robert F.; Ogden, Fred L.; Elsenbeer, Helmut; Hall, Jefferson S.

    2010-01-01

    The Agua Salud Project utilizes the Panama Canal’s (Canal) central role in world commerce to focus global attention on the ecosystem services provided by tropical forests. The Canal was one of the great engineering projects in the world. Completed in 1914, after almost a decade of concerted effort, its 80 km length greatly shortened the voyage between the Atlantic and Pacific Oceans. An entire class of ships, the Panamax, has been constructed to maximize the amount of cargo that can be carried in a Canal passage. In today’s parlance, the Canal is a “green” operation, powered largely by water (Table 1). The locks, three pairs on each end with a net lift of 27 meters, are gravity fed. For each ton of cargo that is transferred from ocean to ocean, about 13 tons of water (m3) are used. Lake Gatún forms much of the waterway in the Canal transect. Hydroelectricity is generated at the Gatún dam, whenever there is surplus water, and at Madden Dam (completed in 1936) when water is transferred from Lake Alhajuela to Lake Gatún. The Canal watershed is the source of drinking water for Panama City and Colon City, at either end of the Canal, and numerous towns in between.

  11. Advanced BWR core component designs and the implications for SFD analysis

    International Nuclear Information System (INIS)

    Prior to the DF-4 boiling water reactor (BWR) severe fuel damage (SFD) experiment conducted at the Sandia National Laboratories in 1986, no experimental data base existed for guidance in modeling core component behavior under postulated severe accident conditions in commercial BWRs. This paper will present the lessons learned from the DF-4 experiment (and subsequent German CORA BWR SFD tests) and the impact on core models in the current generation of SFD codes. The DF-4 and CORA BWR test assemblies were modeled on the core component designs circa 1985; that is, the 8 x 8 fuel assembly with two water rods and a cruciform control blade constructed of B4C-filled tubelets. Within the past ten years, the state-of-the-art with respect to BWR core component development has out-distanced the current SFD experimental data base and SFD code capabilities. For example, modern BWR control blade design includes hafnium at the tips and top of each control blade wing for longer blade operating lifetimes; also water rods have been replaced by larger water channels for better neutronics economy; and fuel assemblies now contain partial-length fuel rods, again for better neutronics economy. This paper will also discuss the implications of these advanced fuel assembly and core component designs on severe accident progression and on the current SFD code capabilities

  12. An A BWR demonstration simulator for training and developing technical staff

    Energy Technology Data Exchange (ETDEWEB)

    Powers, J. [Toshiba America Nuclear Energy, Charlotte, North Carolina (United States); Yonezawa, H.; Aoyagi, Y.; Kataoka, K., E-mail: jim.powers@toshiba.com [Toshiba Corporation, Kawasaki, Kanagawa (Japan)

    2015-09-15

    The US-Advanced Boiling Water Reactor (A BWR), certified by the US NRC, is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (STP3-4) Combined License Application (Cola). Nuclear Innovation North America (Nina) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. Toshiba has developed a Demonstration Simulator of the A BWR control room that provides a realistic experience for training and education on BWR principles and operations fundamentals. The Demonstration Simulator is located in the Toshiba America Nuclear Energy (Tane) office in Charlotte, North Carolina and is composed of standard office computer equipment set up in a specific arrangement that is representative of the layout of an A BWR control room. The Demonstration Simulator is not intended for licensed operator training, but can provide a framework for encouraging entry level technically oriented nuclear workers to enter the operations field; strengthening the linkage between university energy field curricula and real-life application of theory; and, improving understanding of integrated plant operations for developing station technical staff. This paper describes the A BWR Demonstration Simulator and its applications for training and educating future nuclear workers. (Author)

  13. An A BWR demonstration simulator for training and developing technical staff

    International Nuclear Information System (INIS)

    The US-Advanced Boiling Water Reactor (A BWR), certified by the US NRC, is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (STP3-4) Combined License Application (Cola). Nuclear Innovation North America (Nina) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. Toshiba has developed a Demonstration Simulator of the A BWR control room that provides a realistic experience for training and education on BWR principles and operations fundamentals. The Demonstration Simulator is located in the Toshiba America Nuclear Energy (Tane) office in Charlotte, North Carolina and is composed of standard office computer equipment set up in a specific arrangement that is representative of the layout of an A BWR control room. The Demonstration Simulator is not intended for licensed operator training, but can provide a framework for encouraging entry level technically oriented nuclear workers to enter the operations field; strengthening the linkage between university energy field curricula and real-life application of theory; and, improving understanding of integrated plant operations for developing station technical staff. This paper describes the A BWR Demonstration Simulator and its applications for training and educating future nuclear workers. (Author)

  14. Nonlinear behavior under regional neutron flux oscillations in BWR cores

    International Nuclear Information System (INIS)

    A three-dimensional time-domain core analysis code was applied to numerical simulations for an actual regional neutron flux oscillation observed in a commercial BWR core, in order to investigate potential nonlinear behavior in its coupled neutronic and thermohydraulic system. The present study shows existence of the nonlinear reactivity interaction between the fundamental and first azimuthal spatial harmonics modes of neutron flux distribution under the regional event. The spectrum analysis of the simulated data provides a unique result, that is, temporal harmonics peaks are excited at the even- and odd-order multiples of the characteristic resonance frequency in the fundamental and first spatial harmonics responses, respectively. The numerical simulation also shows that the strong nonlinearity of the coupled neutronic and thermohydraulic dynamics locally appears where the power unstably oscillates with large amplitudes, inducing the power shift and reactivity bias which are shown in the core-wide situation under the global oscillations. This contributes to suppression of the divergence of the local power oscillation, and also to development of the saturated self-limited cycles under the regional oscillations. (author)

  15. A New Methodology for Early Anomaly Detection of BWR Instabilities

    Energy Technology Data Exchange (ETDEWEB)

    Ivanov, K. N.

    2005-11-27

    The objective of the performed research is to develop an early anomaly detection methodology so as to enhance safety, availability, and operational flexibility of Boiling Water Reactor (BWR) nuclear power plants. The technical approach relies on suppression of potential power oscillations in BWRs by detecting small anomalies at an early stage and taking appropriate prognostic actions based on an anticipated operation schedule. The research utilizes a model of coupled (two-phase) thermal-hydraulic and neutron flux dynamics, which is used as a generator of time series data for anomaly detection at an early stage. The model captures critical nonlinear features of coupled thermal-hydraulic and nuclear reactor dynamics and (slow time-scale) evolution of the anomalies as non-stationary parameters. The time series data derived from this nonlinear non-stationary model serves as the source of information for generating the symbolic dynamics for characterization of model parameter changes that quantitatively represent small anomalies. The major focus of the presented research activity was on developing and qualifying algorithms of pattern recognition for power instability based on anomaly detection from time series data, which later can be used to formulate real-time decision and control algorithms for suppression of power oscillations for a variety of anticipated operating conditions. The research being performed in the framework of this project is essential to make significant improvement in the capability of thermal instability analyses for enhancing safety, availability, and operational flexibility of currently operating and next generation BWRs.

  16. BWR Fuel Lattice Design Using an Ant Colony Model

    International Nuclear Information System (INIS)

    This paper deals with one of the steps of the nuclear fuel design: the radial fuel lattice design. It can be seen as a combinatorial optimization problem for determining the optimal 2D fuel rods enrichment and gadolinia distribution. In order to solve this optimization problem, the ant colony system technique is proposed. The main idea of the ant colony approach consists of emulating the real ant colony behaviour in their searching for minimum paths between two given points, usually between the nest and a food source. In this case, the environment where the artificial ants move is the space defined by the discrete possible values of Gd2O3 contents, the U235 enrichment, and the valid locations inside the 10x10 BWR fuel lattice array. In order to assess any candidate fuel lattice in the optimization process, the HELIOS neutronic transport code is used. The results obtained in the application of the implemented model show that the proposed technique is a powerful tool to tackle this step of the fuel design. (authors)

  17. Identification of the reduced order models of a BWR reactor

    International Nuclear Information System (INIS)

    The present work has as objective to analyze the relative stability of a BWR type reactor. It is analyzed that so adaptive it turns out to identify the parameters of a model of reduced order so that this it reproduces a condition of given uncertainty. This will take of a real fact happened in the La Salle plant under certain operation conditions of power and flow of coolant. The parametric identification is carried out by means of an algorithm of recursive least square and an Output Error model (Output Error), measuring the output power of the reactor when the instability is present, and considering that it is produced by a change in the reactivity of the system in the same way that a sign of type step. Also it is carried out an analytic comparison of the relative stability, analyzing two types of answers: the original answer of the uncertainty of the reactor vs. the obtained response identifying the parameters of the model of reduced order, reaching the conclusion that it is very viable to adapt a model of reduced order to study the stability of a reactor, under the only condition to consider that the dynamics of the reactivity is of step type. (Author)

  18. A New Method for Early Anomaly Detection of BWR Instabilities

    International Nuclear Information System (INIS)

    The objective of the performed research is to develop an early anomaly detection methodology so as to enhance safety, availability, and operational flexibility of Boiling Water Reactor (BWR) nuclear power plants. The technical approach relies on suppression of potential power oscillations in BWRs by detecting small anomalies at an early stage and taking appropriate prognostic actions based on an anticipated operation schedule. The research utilizes a model of coupled (two-phase) thermal-hydraulic and neutron flux dynamics, which is used as a generator of time series data for anomaly detection at an early stage. The model captures critical nonlinear features of coupled thermal-hydraulic and nuclear reactor dynamics and (slow time-scale) evolution of the anomalies as non-stationary parameters. The time series data derived from this nonlinear non-stationary model serves as the source of information for generating the symbolic dynamics for characterization of model parameter changes that quantitatively represent small anomalies. The major focus of the presented research activity was on developing and qualifying algorithms of pattern recognition for power instability based on anomaly detection from time series data, which later can be used to formulate real-time decision and control algorithms for suppression of power oscillations for a variety of anticipated operating conditions. The research being performed in the framework of this project is essential to make significant improvement in the capability of thermal instability analyses for enhancing safety, availability, and operational flexibility of currently operating and next generation BWRs.

  19. Standard Technical Specifications, General Electric plants, BWR/4

    International Nuclear Information System (INIS)

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

  20. Standard Technical Specifications, General Electric Plants, BWR/6

    International Nuclear Information System (INIS)

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  1. BWR Fuel Lattice Design Using an Ant Colony Model

    Energy Technology Data Exchange (ETDEWEB)

    Montes, Jose L.; Ortiz, Juan J. [Instituto Nacional de Investigaciones Nucleares, Depto. de Sistemas Nucleares, Carretera Mexico Toluca S/N. La Marquesa Ocoyoacac. 52750, Estado de Mexico (Mexico); Francois, Juan L.; Martin-del-Campo, Cecilia [Depto. de Sistemas Energeticos, Facultad de Ingenieria, Universidad Nacional Autonoma de Mexico Paseo Cuauhnahuac 8532. Jiutepec, Mor. 62550 (Mexico)

    2008-07-01

    This paper deals with one of the steps of the nuclear fuel design: the radial fuel lattice design. It can be seen as a combinatorial optimization problem for determining the optimal 2D fuel rods enrichment and gadolinia distribution. In order to solve this optimization problem, the ant colony system technique is proposed. The main idea of the ant colony approach consists of emulating the real ant colony behaviour in their searching for minimum paths between two given points, usually between the nest and a food source. In this case, the environment where the artificial ants move is the space defined by the discrete possible values of Gd{sub 2}O{sub 3} contents, the U{sup 235} enrichment, and the valid locations inside the 10x10 BWR fuel lattice array. In order to assess any candidate fuel lattice in the optimization process, the HELIOS neutronic transport code is used. The results obtained in the application of the implemented model show that the proposed technique is a powerful tool to tackle this step of the fuel design. (authors)

  2. Validation study of core analysis methods for full MOX BWR

    International Nuclear Information System (INIS)

    JNES has been developing a technical data base used in reviewing validation of core analysis methods of LWRs in the occasions: (1) confirming core safety parameters of the initial core (one-third MOX core) through a full MOX core in Oma Nuclear Power Plant, which is under the construction, (2) licensing high-burnup MOX cores in the future and (3) reviewing topical reports on core analysis codes for safety design and evaluation. Based on the technical data base, JNES will issue a guide of reviewing the core analysis methods used for safety design and evaluation of LWRs. The data base will be also used for validation and improving of core analysis codes developed by JNES. JNES has progressed with the projects (1) measurements of Doppler reactivity in experimental MOX core simulating LWR cores, (2) measurement of isotopic compositions of fission product nuclides on high-burn up BWR UO2 fuels and (3) neutronics analysis of the experimental data that has been obtained in the international joint programs such as FUBILA and REBUS. (author)

  3. Validation study of core analysis methods for full MOX BWR

    International Nuclear Information System (INIS)

    JNES has been developing a technical data base used in reviewing validation of core analysis methods of LWRs in the coming occasions: (1) confirming the core safety parameters of the initial core (one-third MOX core) through a full MOX core in Oma Nuclear Power Plant, which is under the construction, (2) licensing high-burnup MOX cores in the future and (3) reviewing topical reports on core analysis codes for safety design and evaluation. Based on the technical data base, JNES will issue a guide of reviewing the core analysis methods used for safety design and evaluation of LWRs. The data base will be also used for validation and improving of core analysis codes developed by JNES. JNES has progressed with the projects (1) analysis of the measurement data of Doppler reactivity in experimental MOX core simulating LWR cores, (2) measurements of isotopic compositions of fission product nuclides on high-burnup BWR UO2 fuels and the analysis of the measurement data, and (3) neutronics analysis of the experimental data that has been obtained in the international joint programs such as FUBILA and REBUS. (author)

  4. Natural heat transfer augmentation in passive advanced BWR plants

    International Nuclear Information System (INIS)

    In the European Simplified Boiling Water Reactor (ESBWR), the long-term post-accident containment pressure is determined by the combination of non condensable gas pressure and steam pressure in the wet well gas space. Since there are no active systems for heat removal in the wet well, energy transmitted to the wet well gas space, by a variety of means, must be removed by passive heat transfer to the walls and suppression pool (SP). The cold suppression pool located below the hotter gas space provides a stable configuration in which convection currents are suppressed thus limiting heat and mass transfer between the gas space and pool. However, heat transfer to the walls results in natural circulation currents that can augment the heat and mass transfer to the pool surface. Using a simplified model, parametric studies are carried out to show that augmentation of the order of magnitude expected can significantly impact the heat and mass transfer to the pool. Additionally a review of available literature in the area of augmentation and mixed convection of this type is presented and indicates the need for additional experimental work in order to develop adequate models for heat and mass transfer augmentation in the configuration of a BWR suppression pool. (author)

  5. Development of BWR operator training simulator and training support systems

    International Nuclear Information System (INIS)

    This paper describes a BWR operator training simulator and training support systems that have been developed with the aim of providing support throughout operator training. The operator training simulator is needed in order to improve simulation fidelity and enlarge simulation scope. A 3-dimensional reactor core model has been developed in order to improve the understanding of operators respecting neutronics through realistic training. A severe accident model has been developed for training operators and technical support center teams respecting plant operation and for studying various phenomena. The severe accident is simulated by connecting the physical parameters continuously from the conventional model to the severe accident model. An emergency procedure guideline support system is adopted in order to improve efficiency of operation training for emergencies, since the emergency operation procedures are complicated and based on multiple parameter conditions. The operator training support system is also introduced so as to help training instructors to evaluate the operation and to give instructions to operators to improve operational accuracy. An instructor's burden is eased by automatically evaluating the operation errors based on signals of a simulator. The effects of these systems are evaluated and found to be effective in an actual training center and in engineers' examinations. (author)

  6. BWR/5 Pressure-Suppression Pool Response during an SBO

    Directory of Open Access Journals (Sweden)

    Javier Ortiz-Villafuerte

    2013-01-01

    Full Text Available RELAP/SCDAPSIM Mod 3.4 has been used to simulate a station blackout occurring at a BWR/5 power station. Further, a simplified model of a wet well and dry well has been added to the NSSS model to study the response of the primary containment during the evolution of this accident. The initial event leading to severe accident was considered to be a LOOP with simultaneous scram. The results show that RCIC alone can keep the core fully covered, but even in this case about 30% of the original liquid water inventory in the PSP is vaporized. During the SBO, without RCIC, this inventory is reduced about 5% more within six hours. Further, a significant pressure rise occurs in containment at about the time when a sharp increase of heat generation occurs in RPV due to cladding oxidation. Failure temperature of fuel clad is also reached at this point. As the accident progresses, conditions for containment venting can be reached in about nine hours, although there still exists considerable margin before reaching containment design pressure. Detailed information of accident progress in reactor vessel and containment is presented and discussed.

  7. BWR [boiling water reactor] shutdown margin model in SIMULATE-3

    International Nuclear Information System (INIS)

    Boiling water reactor (BWR) technical specifications require that the reactor be kept subcritical (by some prescribed margin) when at room temperature rodded conditions with any one control rod fully withdrawn. The design of an acceptable core loading pattern may require hundreds or thousands of neutronic calculations in order to predict the shutdown margin for each control rod. Direct, full-core, three-dimensional calculations with the SIMULATE-3 two-group advanced nodal code require 3 to 6 CPU min (on a SUN-4 workstation) for each statepoint/control rod that is computed. Such computing and manpower requirements may be burdensome, particularly during the early core design process. These requirements have been significantly reduced by the development of a fast, accurate shutdown margin model in SIMULATE-3. The SIMULATE-3 shutdown margin model achieves a high degree of accuracy and speed without using axial collapsing approximations inherent in many models. The mean difference between SIMULATE-3 one-group and two-group calculations is approximately - 12 pcm with a standard deviation of 35 pcm. The SIMULATE-3 shutdown margin model requires a factor of ∼15 less CPU time than is required for stacked independent two-group SIMULATE-3 calculations

  8. Calibration of the TVO spent BWR reference fuel assembly

    International Nuclear Information System (INIS)

    In 1989 the Support Programmes of Finland (FSP) and Sweden (SSP) initiated a joint task to cross calibrate the burnup of the IAEA spent BWR reference fuel assembly at the TVO AFR storage facility (TVO KPA-STORE) in Finland. The reference assembly, kept separately under the IAEA seal, is used for verification measurements of spent fuel by GBUV method (SG-NDA-38). The cross calibration was performed by establishing a calibration curve, 244Cm neutron rate versus burnup, using passive neutron assay (PNA) measurements. The declared burnup of the reference assembly was compared with the burnup value deduced from the calibration curve. A calibration line was also established by using the GBUV method with the aid of high resolution gamma ray spectrometry (HRGS). Normalization between the two different facilities was performed using sealed neutron and gamma calibration sources. The results of the passive neutron assay show consistency, better than 1 %, between the declared mean burnup of the reference assembly and the burnup deduced from the calibration curve. The corresponding consistency is within +-2 % for the HRGS measurements

  9. Standard Technical Specifications, General Electric plants, BWR/6

    International Nuclear Information System (INIS)

    This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

  10. Impurity hideout/hideout return at the Susquehanna 2 BWR

    International Nuclear Information System (INIS)

    An impurity hideout return study was performed at the Susquehanna 2 BWR to provide an understanding of impurity hideout processes during normal operation and their impact on high temperature solution chemistry in corrosion product deposits on the fuel. Limited hideout return data obtained during shutdowns at 10 BWRs previously had indicated reasonable consistency with expectations based on MULTEQ high temperature solution chemistry modeling of hideout processes. Observations at Susquehanna 2 were consistent with expectations. Cumulative returns of species forming precipitates at low concentration factors above the bulk water concentration, e.g., calcium, magnesium, sulfate and silica were much greater than those of species having a minimal tendency to precipitate, e.g., sodium and chloride. Solutions present in the fuel cladding surface during normal operation were predicted to contain high concentrations (0.1 to 2 molal) of sodium, potassium, chloride, sulfate, silica and nitrate. The predicted solution pH at 300 degrees C was 9.4 (neutral pH = 5.5). The increase in conductivity observed during and after shutdown was shown to be due to solubilization of precipitates with retrograde solubilities rather than chemical/resin intrusion. Variations in reactor water concentrations during reactor water cleanup system isolation and power reductions were consistent with predictions developed from a mass balance around the reactor coolant system

  11. Artificial intelligence applied to fuel management in BWR type reactors

    International Nuclear Information System (INIS)

    In this work two techniques of artificial intelligence, neural networks and genetic algorithms were applied to a practical problem of nuclear fuel management; the determination of the optimal fuel reload for a BWR type reactor. This is an important problem in the design of the operation cycle of the reactor. As a result of the application of these techniques, comparable or even better reloads proposals than those given by expert companies in the subject were obtained. Additionally, two other simpler problems in reactor physics were solved: the determination of the axial power profile and the prediction of the value of some variables of interest at the end of the operation cycle of the reactor. Neural networks and genetic algorithms have been applied to solve many problems of engineering because of their versatility but they have been rarely used in the area of fuel management. The results obtained in this thesis indicates the convenience of undertaking further work on this area and suggest the application of these techniques of artificial intelligence to the solution of other problems in nuclear reactor physics. (Author)

  12. Derivation of general scaling criteria for BWR containment tests

    International Nuclear Information System (INIS)

    General top-down scaling criteria for facilities used to study Boiling Water Reactor (BWR) containments including a pressure suppression system are derived, with particular attention to the recent passive BWRS. The criteria are derived by considering the generic processes in classes of containment subsystems (e.g., containment volumes, pools, pipes, etc.). In reactor containments, the thermodynamic behavior of the system (essentially, its pressure history) is linked to its thermal-hydraulic behavior (the flows of mass and energy between volumes). The case of prototypical fluids under prototypical thermodynamic conditions is treated. The study confirms the validity of the (familiar) scaling of power, volumes, horizontal areas in volumes, mass flow rates, and heat transfer areas with a system scale. Important pressure drops and the corresponding flows are controlled by the submergence depth of vents or by hydrostatic pressure differences in connected vessels. The analysis of these processes justify the choice of 1:1 scaling for the pressure drops, vertical heights, submergence depths and level differences. The importance of certain distortions regarding inertial response and transit times is minor

  13. Sustancias húmicas en aguas para abastecimiento

    Directory of Open Access Journals (Sweden)

    Miller Camargo Valero

    2011-02-01

    Full Text Available Las sustancias húmicas hacen parte de los productos de degradación de la materia orgánica del suelo y se incorporan a las aguas superficiales por la acción de lavado que realizan las aguas de escorrentía. Estas sustancias han sido reconocidas como precursores en la formación de subproductos de la desinfección con cloro libre en plantas de tratamiento de agua potable. Los subproductos de desinfección, compuestos orgánicos halogenados, se han catalogado como sustancias potencialmente cancerígenas en humanos, y por tanto el interés en conocer más sobre las sustancias precursoras, mecanismos de formación de subproductos de desinfección, situación nacional y métodos para disminuir su formación.

  14. Defensa del agua desde la participación comunitaria

    Directory of Open Access Journals (Sweden)

    Martha Muñoz

    2013-09-01

    Full Text Available Las organizaciones comunitarias en Colombia defienden el mantenimiento de los páramos, indispensables para la provisión de agua en zonas rurales y urbanas. Se oponen a la idea del desarrollo económico que concibe al agua como servicio ambiental, vulnerando un derecho fundamental. Un ejemplo de organización es la que se lleva a cabo en el Santuario de Flora y Fauna de Iguaque. Ahí, los veedores saben que si no luchan por el agua perderán un derecho, como sucedió en las veredas de Olivos Alto y Bajo del municipio de Sanjuan de Rioseco, donde el Estado impuso sus políticas.

  15. Los conflictos del agua en España

    Directory of Open Access Journals (Sweden)

    Gaspar Mairal Buil

    2005-04-01

    Full Text Available En este trabajo se analizan los conflictos producidos en España en los últimos años en torno a la construcción de grandes presas, tratando de mostrar cómo los afectados han forjado una noción compartida de riesgo y cómo ha surgido un movimiento social con un discurso proyectado hacia ámbitos más globales. Estos hechos se sitúan en relación con la política del agua de la nueva Directiva Marco del Agua (2000 de la Unión Europea para mostrar una insuficiencia, ya que ésta no toma en cuenta el significado cultural de los usos del agua.

  16. Design guideline to prevent the pipe rupture by combustion of radiolysis gases in BWR steam piping

    International Nuclear Information System (INIS)

    In late 2001, pipe rupture accidents due to fast combustion of radiolysis gas occurred in Japan and elsewhere's BWR power plants. TENPES began to set up the guideline as action to such a new problem to prevent accumulation and combustion of radiolysis gas in BWR steam piping. And then, the first edition of guideline was published in October 2005, and the 2nd edition in March 2007. Afterwards, the experimental study about combustion/detonation of radiolysis gas have been continued. And in March 2010, JANTI published the 3rd edition of the guideline. This is the report of the final edition of that guideline. According to this guideline, it became possible to design BWR's steam piping to prevent pipe rupture accident due to combustion of radiolysis gas. (author)

  17. BWR Water Chemistry Guidelines: 1993 Revision, Normal and hydrogen water chemistry

    International Nuclear Information System (INIS)

    The goal of water chemistry control is to extend the operating life of the reactor and rector coolant system, balance-of-plant components, and turbines while simultaneously controlling costs to safeguard the continued economic viability of the nuclear power generation investment. To further this goal an industry committee of chemistry personnel prepared guidelines to identify the benefits, risks, and costs associated with water chemistry in BWRs and to provide a template for an optimized water chemistry program. This document replaces the BWR Normal Water Chemistry Guidelines - 1986 Revision and the BWR Hydrogen Water Chemistry Guidelines -- 1987 Revision. It expands on the previous guidelines documents by covering the economic implications of BWR water chemistry control

  18. Effect of Control Blade History, and Axial Coolant Density and Burnup Profiles on BWR Burnup Credit

    Energy Technology Data Exchange (ETDEWEB)

    Marshall, William BJ J [ORNL

    2016-01-01

    A technical basis for peak reactivity boiling water reactor (BWR) burnup credit (BUC) methods was recently generated, and the technical basis for extended BWR BUC is now being developed. In this paper, a number of effects related to extended BWR BUC are analyzed, including three major operational effects in BWRs: the coolant density axial distribution, the use of control blades during operation, and the axial burnup profile. Specifically, uniform axial moderator density profiles are analyzed and compared to previous results and an additional temporal fidelity study combing moderator density profiles for three different fuel assemblies is presented. Realistic control blade histories and cask criticality results are compared to previously generated constructed control blade histories. Finally, a preliminary study of the axial burnup profile is provided.

  19. Key Parameters for Operator Diagnosis of BWR Plant Condition during a Severe Accident

    Energy Technology Data Exchange (ETDEWEB)

    Clayton, Dwight A [ORNL; Poore III, Willis P [ORNL

    2015-01-01

    The objective of this research is to examine the key information needed from nuclear power plant instrumentation to guide severe accident management and mitigation for boiling water reactor (BWR) designs (specifically, a BWR/4-Mark I), estimate environmental conditions that the instrumentation will experience during a severe accident, and identify potential gaps in existing instrumentation that may require further research and development. This report notes the key parameters that instrumentation needs to measure to help operators respond to severe accidents. A follow-up report will assess severe accident environmental conditions as estimated by severe accident simulation model analysis for a specific US BWR/4-Mark I plant for those instrumentation systems considered most important for accident management purposes.

  20. Report on the BWR owners group radiation protection/ALARA Committee

    International Nuclear Information System (INIS)

    Radiation protection programs at U.S. boiling water reactor (BWR) stations have evolved during the 1980s and early 1990s from a regulatory adherence-based endeavor to a proactive, risk-based radiation protection and prevention mission. The objectives are no longer to merely monitor and document exposure to radiation and radioactive materials. The focus of the current programs is the optimization of radiation protection of occupational workers consistent with the purpose of producing cost-effective electric power. The newly revised 10 CFR 20 defines the term ALARA (as low as reasonably achievable) to take into account the state of technology, the economics of improvements in relation to the state of the technology, and the benefits to the public health and safety. The BWR Owners Group (BWROG) initially formed the Radiation Protection/ALARA Committee in January 1990 to evaluate methods of reducing occupational radiation exposure during refueling outages. Currently, twenty U.S. BWR owner/operators (representing 36 of the operational 37 domestic BWR units), as well as three foreign BWR operators (associate members), have broadened the scope to promote information exchange between BWR radiation protection professionals and develop good practices which will affect optimization of their radiation protection programs. In search of excellence and the challenge of becoming open-quotes World Classclose quotes performers in radiation protection, the BWROG Radiation Protection/ALARA Committee has recently accepted a role in assisting the member utilities in improving radiation protection performance in a cost-effective manner. This paper will summarize the recent activities of this Committee undertaken to execute their role of exchanging information in pursuit of optimizing the improvement of their collective radiation protection performance

  1. Validation of SCALE (SAS2H) Isotopic Predictions for BWR Spent Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Hermann, O.W.

    1998-01-01

    Thirty spent fuel samples obtained from boiling-water-reactor (BWR) fuel pins have been modeled at Oak Ridge National Laboratory using the SAS2H sequence of the SCALE code system. The SAS2H sequence uses transport methods combined with the depletion and decay capabilities of the ORIGEN-S code to estimate the isotopic composition of fuel as a function of its burnup history. Results of these calculations are compared with chemical assay measurements of spent fuel inventories for each sample. Results show reasonable agreement between measured and predicted isotopic concentrations for important actinides; however, little data are available for most fission products considered to be important for spent fuel concerns (e.g., burnup credit, shielding, source-term calculations, etc.). This work is a follow-up to earlier works that studied the ability to predict spent fuel compositions in pressurized-water-reactor (PWR) fuel pins. Biases and uncertainties associated with BWR isotopic predictions are found to be larger than those of PWR calculations. Such behavior is expected, as the operation of a BWR is significantly more complex than that of a PWR plant, and in general the design of a BWR has a more heterogeneous configuration than that of a PWR. Nevertheless, this work shows that the simple models employed using SAS2H to represent such complexities result in agreement to within 5% (and often less than 1%) or less for most nuclides important for spent fuel applications. On the other hand, however, the set of fuel samples analyzed represent a small subset of the BWR fuel population, and results reported herein may not be representative of the full population of BWR spent fuel.

  2. Validation of SCALE (SAS2H) isotopic predictions for BWR spent fuel

    Energy Technology Data Exchange (ETDEWEB)

    Hermann, O.W.; DeHart, M.D.

    1998-09-01

    Thirty spent fuel samples obtained from boiling-water-reactor (BWR) fuel pins have been modeled at Oak Ridge National Laboratory using the SAS2H sequence of the SCALE code system. The SAS2H sequence uses transport methods combined with the depletion and decay capabilities of the ORIGEN-S code to estimate the isotopic composition of fuel as a function of its burnup history. Results of these calculations are compared with chemical assay measurements of spent fuel inventories for each sample. Results show reasonable agreement between measured and predicted isotopic concentrations for important actinides; however, little data are available for most fission products considered to be important for spent fuel concerns (e.g., burnup credit, shielding, source-term calculations, etc.). This work is a follow-up to earlier works that studied the ability to predict spent fuel compositions in pressurized-water-reactor (PWR) fuel pins. Biases and uncertainties associated with BWR isotopic predictions are found to be larger than those of PWR calculations. Such behavior is expected, as the operation of a BWR is significantly more complex than that of a PWR plant, and in general the design of a BWR has a more heterogeneous configuration than that of a PWR. Nevertheless, this work shows that the simple models employed using SAS2H to represent such complexities result in agreement to within 5% (and often less than 1%) or less for most nuclides important for spent fuel applications. On the other hand, however, the set of fuel samples analyzed represent a small subset of the BWR fuel population, and results reported herein may not be representative of the full population of BWR spent fuel.

  3. IMPACTO DEL USO DE AGUA RESIDUAL EN LA AGRICULTURA

    Directory of Open Access Journals (Sweden)

    María E. Guadarrama-Brito

    2015-07-01

    Full Text Available La escasez de agua para uso urbano y la dependencia del riego para la producción agrícola en zonas de rápido crecimiento demográfico, han contribuido a que a nivel internacional aumente el interés en el reuso del agua. Existen riesgos para la salud debido a la presencia de microorganismos y contaminantes como los metales pesados y mutagénicos; los primeros impactan a corto plazo, debido a la contaminación de alimentos que pueden provocar, y los segundos impactan a largo plazo, contribuyendo a la salinización de suelos, lo que detrimenta la productividad para eventualmente derivar en el abandono de terrenos. El reuso del agua residual en la agricultura se ha convertido en una necesidad, la cual debe ser considerada como una alternativa, aunque no ha sido evaluada en los aspectos de contenido y migración de contaminantes, en particular de metales pesados. Algunos de los metales pesados pueden forman parte natural del suelo en cantidades que no resultan tóxicas para los seres vivos; sin embargo, la industrialización ha provocado un aumento de la presencia de estos en las aguas residuales que se utilizan para riego, con el consecuente riesgo para la salud humana y ambiental. El proceso de migración y fijación de contaminantes dentro de un sistema cerrado, dependerá de la capacidad de absorción por parte de los subsistemas agua-suelo-planta, aplicación de tasas de riego (concentración del contaminante, y de la persistencia y toxicidad de los contaminantes. El estudio aquí presentado, evalúa las tasas de migración de metales pesados presentes en un agua de riego, a través del sistema agua-suelo-planta; la evaluación se realizó con material del distrito de riego 028-Tulancingo que recibe aguas residuales de origen industrial, con presencia de Cobre, Manganeso y Zinc para diferentes grados de impacto.

  4. Calidad del agua en marinas pequeñas

    OpenAIRE

    Fuentes Mariles, Óscar Arturo; Osnaya Romero, Javier; Magaña Melgoza, Pedro A.

    1997-01-01

    Se describe un método para calcular la concentración de un contaminante o bien la concentración de oxígeno disuelto (OD) y la demanda bioquímica de oxígeno (DBO) para una marina donde existe un mezclado completo de las sustancias en sus aguas. Los resultados del método permiten analizar la calidad del agua, revisar el tamaño de la marina, evaluar las consecuencias de la descarga de un contaminante, estimar la magnitud de bombeos para reducir la concentración de contaminantes, etc. También se ...

  5. El estado actual de los ambientes del agua

    OpenAIRE

    Mateu Bellés, Joan F.; Camarasa Belmonte, Ana María

    2008-01-01

    Los ambientes del agua –recursos singulares por sus funciones en la naturaleza y por sus prestaciones y connotaciones para los grupos humanos- son un valioso patrimonio. En concreto, los lagos, los ríos y las masas marinas y subterráneas constituyen bienes territoriales que aportan diversidad ecológica, estructuran paisajes y, a menudo, son utilizados por los humanos para el desarrollo de sus actividades (Martín Montalvo, 1996). A lo largo del tiempo, los ambientes del agua no son estables e...

  6. MARCAS DE AGUA ROBUSTAS A ATAQUES GEOMÉTRICOS

    OpenAIRE

    Bravo Solorio, Sergio

    2012-01-01

    Los avances tecnológicos ofrecen formas más económicas y rápidas para copiar y distribuir datos multimedia con gran calidad. Consecuentemente, se han propuesto técnicas de marcas de agua para evitar y detectar violaciones a los derechos de autor, falsificaciones, etc. Sin embargo, como cualquier otra señal digital, las imágenes pueden sufrir un enorme conjunto de distorsiones que pueden da ̃ar seriamente, e incluso eliminar, las marcas de agua insertadas. Las distorsiones geométricas usual...

  7. Servicios ambientales, agua y economía

    OpenAIRE

    Juan Pablo Ruiz Soto

    2007-01-01

    Los servicios ambientales (SA) asociados a los ecosistemas naturales están seriamente amenazados por acciones locales y por el calentamiento global. El SA asociado al agua y su efecto sobre calidad y cantidad en cuencas hidrográficas aportantes a acueductos y sistemas de riego, son de gran importancia económica y social. Para Bogotá-Colombia el SA de los páramos y bosque nublado en la cuenca de Chingaza representa US$18,2 millones anuales. Para el abastecimiento de agua a la ciudad de Quito-E...

  8. Sensor perfeccionado para la medida de la toxicidad del agua

    OpenAIRE

    Campo García, Francisco Javier del; Mas Gordi, Jordi

    2009-01-01

    La invención se basa en un sensor de medida para la toxidad del agua y consiste en una red de micro-electrodos recubiertos de una membrana y de un biofilm. La red de micro-electrodos puede ser estándar, y es posible su funcionamiento con un único electrodo, aunque ello acarrearía una perdida de sensibilidad. La membrana se usa para evitar la pasivación del electrodo por las bacterias presentes en el agua, y se utilizará en una de las realizaciones posibles "Nafion", aunque también es posible ...

  9. Design of a redundant meteorological station for a BWR reactor; Diseno de una estacion meteorologica redundante para un reactor BWR

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez S, R.; Celis del Angel, L.; Bucio, F.; Rivero, T.; Palacios, J. [ININ, 52750 La Marquesa, Estado de Mexico (Mexico)]. e-mail: ramses@nuclear.inin.mx

    2008-07-01

    In this work the design of a meteorological station for a reactor type BWR is proposed. Two independent channels of data acquisition that allow him to have a bigger readiness is exposed. It is incorporate sensors without mobile parts to measure speed, wind direction and pluvial precipitation. It also counts, with sensors of global solar radiation, net radiation, barometric pressure, relative humidity and ambient temperature; with them they are possible to be calculated, moreover, other variables as temperature differential, dew point and atmospheric stability. The sensors are placed on a tower to different heights and send their information (each second) to a local registration system, the one which in turn, it remits the data to the monitoring office so that a computer is linked with the system, display and management the information in real time and automatic way. The redundant structure allows that in the event of maintenance the data acquisition is not interrupted, even if the information is transferred to another place. In all the station sections it is used protocols of standard communication to allow that a great quantity of devices can be connected without major problem. The above-mentioned would allow to the operators in the control room to have reliable information during the whole time of the reactor operation. (Author)

  10. Identification of the reduced order models of a BWR reactor; Identificacion de modelos de orden reducido de un reactor BWR

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez S, A. [UNAM, Laboratorio de Analisis de Ingenieria de Reactores Nucleares, DEPFI, Campus Morelos, en IMTA Jiutepec, Morelos (Mexico)]. e-mail: augusto@correo.unam.mx

    2004-07-01

    The present work has as objective to analyze the relative stability of a BWR type reactor. It is analyzed that so adaptive it turns out to identify the parameters of a model of reduced order so that this it reproduces a condition of given uncertainty. This will take of a real fact happened in the La Salle plant under certain operation conditions of power and flow of coolant. The parametric identification is carried out by means of an algorithm of recursive least square and an Output Error model (Output Error), measuring the output power of the reactor when the instability is present, and considering that it is produced by a change in the reactivity of the system in the same way that a sign of type step. Also it is carried out an analytic comparison of the relative stability, analyzing two types of answers: the original answer of the uncertainty of the reactor vs. the obtained response identifying the parameters of the model of reduced order, reaching the conclusion that it is very viable to adapt a model of reduced order to study the stability of a reactor, under the only condition to consider that the dynamics of the reactivity is of step type. (Author)

  11. Desalinización de aguas salobres mediante el uso de flujos capilares

    OpenAIRE

    García Murillo, Alfonso

    2015-01-01

    El agua dulce del planeta es del 3%, es cual es obtenido principalmente por evaporación solar del agua salada de los océanos, de la precipitación del agua evaporada por condensación se forman los glaciares, ríos, lagos, El agua dulce es empleada por el ser humano en los diferentes procesos industriales y alimenticios, después de su uso resulta por lo general contaminada por lo que es necesario realizar tratamientos para su limpieza. En la actualidad se obtiene una cantidad infima de agua dul...

  12. Tratamiento de agua residual con elevado contenido de nitratos utilizando reactores biomembrana aireados

    OpenAIRE

    Lolmede, Ph.; Jácome, Alfredo; Vidart, T.; Tejero, I.

    2000-01-01

    Se describe la eliminación conjunta de carbono y nitrógeno de un agua residual, llevada a cabo en reactores biomembrana de laboratorio. El agua residual sintética tuvo una composición similar a la que resultaría de la mezcla, en determinadas proporciones, de agua residual urbana con agua de acuífero rica en nitratos. Se utilizaron dos reactores en paralelo, con igual superficie de soporte pero distinto volumen. Aunque se insufló aire a la biopelícula a través del soporte, el seno del agua ...

  13. Reuso de aguas residuales domésticas en agricultura. una revisión

    OpenAIRE

    Silva, Jorge; Torres, Patricia; Madera, Carlos

    2010-01-01

    Las aguas residuales son una importante fuente adicional para satisfacer la demanda del recurso, a causa de la disponibilidad limitada de agua potable para cubrir los requerimientos de las poblaciones, los bajos costos, los beneficios para los suelos agrícolas y la disminución del impacto sobre el ambiente. Sin embargo, el predominio del uso de aguas residuales crudas o diluidas con aguas superficiales y el bajo porcentaje de aguas residuales tratadas en Colombia y en los países de Amé...

  14. Determinación de la absorbancia Uv del agua sucusionada

    OpenAIRE

    Delgado Umaña, Mauricio

    2011-01-01

    Experimento donde se compara el efecto de las sucusiones sobre el agua midiendo la absorbancia Uv a 240, 300, 360 nm. Se encontraron diferencias estadísticamente significativas entre el agua sucusionada y el agua sin sucusionar. Los resultados contradicen los parámetros clásicos de la espectrofotometría al documentar absorbancias negativas. Se plantea que en el proceso de sucusionar el agua se establece una nueva fase del agua. / Abstract. Experiment which compares the effect of succussions o...

  15. Control Rod Pattern Planning of a BWR using Enhanced Nelder-Mead Method

    International Nuclear Information System (INIS)

    We propose a new optimization algorithm for the short-term planning of control rod patterns in an operating BWR. This algorithm is based on the enhanced Nelder-Mead simplex method in which convergence ability is improved for constrained problems in several ways. The main characteristic of this approach is it uses continuous values for the axial positions of control rods. Through calculations in an actual BWR plant, we showed that the new algorithm is effective for automation of short-term planning and reduction of the engineer's workload. (authors)

  16. AREVA solutions to licensing challenges in PWR and BWR reload and safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Curca-Tivig, Florin [AREVA GmbH, Erlangen (Germany)

    2016-05-15

    Regulatory requirements for reload and safety analyses are evolving: new safety criteria, request for enlarged qualification databases, statistical applications, uncertainty propagation.. In order to address these challenges and access more predictable licensing processes, AVERA is implementing consistent code and methodology suites for PWR and BWR core design and safety analysis, based on first principles modeling and extremely broad verification and validation data base. Thanks to the high computational power increase in the last decades methods' development and application now include new capabilities. An overview of the main AREVA codes and methods developments is given covering PWR and BWR applications in different licensing environments.

  17. Generic safety evaluation report regarding integrity of BWR scram system piping

    International Nuclear Information System (INIS)

    Safety concerns associated with postulated pipe breaks in the boiling water reactor (BWR) scram system were identified during the staff's continuing investigation of the Browns Ferry Unit 3 control rod partial insertion failure on June 28, 1980. This report includes an evaluation of the licensing basis for the BWR scram discharge volume (SDV) piping and an assessment of the potential for the SDV piping to fail while in service. A discussion of the means available for mitigation an unlikely SDV system failure is provided. Generic recommendations are made to improve mitigation capability and ensure that system integrity is maintained in service

  18. La gestión del agua y la nueva Ley de Aguas

    Directory of Open Access Journals (Sweden)

    Pablo Lloret

    2013-09-01

    Full Text Available La intención de este artículo, al contrario de lo que se esperaría en estos días, no es el de realizar una crítica a los borradores de la nueva “Ley Orgánica de Recursos Hídricos, Uso y Aprovechamiento de las Aguas” o al Nuevo Código Ambiental propuesto, es más bien la de sensibilizar y alertar a quienes estamos involucrados con la gestión de los recursos hídricos, es un llamado a trabajar, de manera corresponsable, en la construcción de una nueva Ley de Aguas que tenga como base la Constitución, la participación, la técnica, lo público, lo privado, en definitiva, pensar en el bien colectivo y en el futuro de nuestros hijos.

  19. Estudio de la calidad del agua de las fuentes de agua subterránea del Alto Palancia

    OpenAIRE

    RAMOS HERNÁNDEZ, RAQUEL

    2014-01-01

    En los últimos tiempos, la calidad del agua se está modificando debido a diferentes sustancias y acciones que la contaminan, y muchas de ellas son responsabilidad de la acción humana, principalmente a través de los vertidos incontrolados de la industria e incluso los municipales y procedentes de actividades como las agrícolas y ganaderas. Como objetivo prioritario para la salud pública está el control sanitario de agua para el consumo humano. Un enfoque integral de evaluación y...

  20. Numerical simulation of boron injection in a BWR

    Energy Technology Data Exchange (ETDEWEB)

    Tinoco, Hernan, E-mail: htb@forsmark.vattenfall.s [Forsmarks Kraftgrupp AB, SE-742 03 Osthammar (Sweden); Buchwald, Przemyslaw [Reactor Technology, Royal Institute of Technology, SE-100 44 Stockholm (Sweden); Frid, Wiktor, E-mail: wiktor@reactor.sci.kth.s [Reactor Technology, Royal Institute of Technology, SE-100 44 Stockholm (Sweden)

    2010-02-15

    The present study constitutes a first step to understand the process of boron injection, transport and mixing in a BWR. It consists of transient CFD simulations of boron injection in a model of the downcomer of Forsmark's Unit 3 containing about 6 million elements. The two cases studied are unintentional start of boron injection under normal operation and loss of offsite power with partial ATWS leaving 10% of the core power uncontrolled. The flow conditions of the second case are defined by means of an analysis with RELAP5, assuming boron injection start directly after the first ECCS injection. Recent publications show that meaningful conservative results may be obtained for boron or thermal mixing in PWRs with grids as coarse as that utilized here, provided that higher order discretization schemes are used to minimize numerical diffusion. The obtained results indicate an apparently strong influence of the scenario in the behavior of the injection process. The normal operation simulation shows that virtually all boron solution flows down to the Main Recirculation Pump inlet located directly below the boron inlet nozzle. The loss of offsite power simulation shows initially a spread of the boron solution over the entire sectional area of the lower part of the downcomer filled with colder water. This remaining effect of the ECCS injection lasts until all this water has left the downcomer. Above this region, the boron injection jet develops in a vertical streak, eventually resembling the injection of the normal operation scenario. Due to the initial spread, this boron injection will probably cause larger temporal and spatial concentration variations in the core. In both cases, these variations may cause reactivity transients and fuel damage due to local power escalation. To settle this issue, an analysis using an extended model containing the downcomer, the MRPs and the Lower Plenum will be carried out. Also, the simulation time will be extended to a scale of

  1. Liquid films and droplet deposition in a BWR fuel element

    International Nuclear Information System (INIS)

    In the upper part of boiling water reactors (BWR) the flow regime is dominated by a steam-water droplet flow with liquid films on the nuclear fuel rod, the so called (wispy) annular flow regime. The film thickness and liquid flow rate distribution around the fuel rod play an important role especially in regard to so called dryout, which is the main phenomenon limiting the thermal power of a fuel assembly. The deposition of droplets in the liquid film is important, because this process sustains the liquid film and delays dryout. Functional spacers with different vane shapes have been used in recent decades to enhance droplet deposition and thus create more favorable conditions for heat removal. In this thesis the behavior of liquid films and droplet deposition in the annular flow regime in BWR bundles is addressed by experiments in an adiabatic flow at nearly ambient pressure. The experimental setup consists of a vertical channel with the cross-section resembling a pair of neighboring subchannels of a fuel rod bundle. Within this double subchannel an annular flow is established with a gas-water mixture. The impact of functional spacers on the annular flow behavior is studied closely. Parameter variations comprise gas and liquid flow rates, gas density and spacer shape. The setup is instrumented with a newly developed liquid film sensor that measures the electrical conductance between electrodes flush to the wall with high temporal and spatial resolution. Advanced post-processing methods are used to investigate the dynamic behavior of liquid films and droplet deposition. The topic is also assessed numerically by means of single-phase Reynolds-Averaged-Navier-Stokes CFD simulations of the flow in the gas core. For this the commercial code STAR-CCM+ is used coupled with additional models for the liquid film distribution and droplet motion. The results of the experiments show that the liquid film is quite evenly distributed around the circumference of the fuel rods. The

  2. Uso Eficiente y Sustentable del agua. Implicancias y Condicionantes

    Directory of Open Access Journals (Sweden)

    Miguel Mathus Escorihuela

    2013-12-01

    Full Text Available El agua no es un recurso natural más, es un recurso vital que permite explicar integralmente los ciclos de la naturaleza y las interacciones entre las especies y el medio en que habitan en virtud del ciclo hidrológico. Pero el agua resiste al hombre, por lo que su aprovechamiento exige acciones concretas, que deben ser racionales y servir al bienestar de la sociedad, para poder alcanzar lo que hoy se llama calidad de vida en un ambiente sano. Para ello, el agua requiere de la Política Hídrica donde se determinan los fines; de la Planificación Hídrica racional y coherente que se encuentre volcada en Planes, Etapas y Programas; de la Legislación, que brinde el marco normativo, de la Administración que lleve a cabo la Política de la Gestión que es el ámbito neurálgico vinculado al uso eficiente del agua

  3. Contaminantes en los cuerpos de agua del sur de Sonora

    Directory of Open Access Journals (Sweden)

    López-Ríos Olga

    2001-01-01

    Full Text Available Objetivo. Ahondar en el conocimiento sobre la incidencia de las actividades productivas del hombre en su medio, y el riesgo potencial que representa el deterioro ambiental para su propia salud y la sobrevivencia de especies animales. Material y métodos. Se utilizó el paquete informático Decision Support System for Industrial Pollution Control DSS (IPC, desarrollado por el Banco Mundial, la Organización Panamericana de la Salud (OPS y la Organización Mundial de la Salud (OMS, que se aplicó a un estudio de caso sobre los cuerpos de agua del sur de Sonora, durante 1996. Resultados. Estos sugieren que existen al menos tres factores que han contribuido a la desaparición de criaderos naturales de pescado y camarón en el municipio de Huatabampo: a la filtración de fertilizantes y pesticidas en las aguas de los drenes; b el asolvamiento producido por el depósito continuo, en el pasado, de agua de cola de la industria, c y la descarga inapropiada de aguas negras en los drenes. El texto completo en inglés de este artículo está disponible en: http://www.insp.mx/salud/index.html

  4. Necesidades de agua en explotaciones de vacuno lechero.

    OpenAIRE

    Callejo Ramos, Antonio

    2014-01-01

    Uno de los principales factores a considerar en el bienestar del ganado lechero es un adecuado acceso al agua como elemento imprescindible para la vida, además de ser necesario para el correcto estado sanitario de los animales y, por tanto, para lograr un adecuado nivel de producción.

  5. Hydraulic modeling and simulation of a System Division of Essential Service Water in a BWR plant with Flow master; Modelo hidraulico y simulacion de una division del Sistema de Agua de Servicio Esencial de una central BWR con Flowmaster

    Energy Technology Data Exchange (ETDEWEB)

    Vegazo Juzgado, L.; Rodriguez Garcia, G. M.; Mota Coloma, M.

    2012-07-01

    At the conclusion of the project can say that Flow master is a simulation tool that allows you to create your model from a library of components and obtain useful results from the point of view of the operation, engineering and maintenance. Compared to previous software from the point of view of use, can comment that Flow master is a tool which has an intuitive and user-friendly interaction between the user and the program thus facilitating the modeling of the system and definition of the components of same.

  6. Radioactivity in drinking water Radiactividad en aguas de consumo

    Directory of Open Access Journals (Sweden)

    Enrique Estrada Vélez

    2011-12-01

    Full Text Available The European Directive on the quality of drinking water in 2003 establishing limits on the values of the radioactive parameters concerning the quality of drinking waters was translated to the Spanish legislation on 2003. These parameters are the gross alpha and beta indexes, tritium content and total indicative dose. The corresponding Spanish Royal Decree came into force in 2008. Not only tap drinking water is subjected to control of radioactivity but also commercial drinking water. Different estudies have been carried out all over the world in both cases. There is a wide range of techniques for the measurement of radioactivity in water. This article describes these techniques and shows when they must be applied. Finally the most important results obtained after analysis in tap water and commercial water are shown both in Spanish and non-Spanish waters. The results show that limits are overtaken in some cases and special care must be taken in order to reduce the levels of radioactivity in drinking water as much as possible.La directiva europea sobre calidad en el agua potable del año 2003 estableció los límites para los valores de los parámetros radiactivos. Esta directiva europea fue incorporada a la legislación 2003. Los parámetros a analizar son los índices alfa y beta total, el contenido en tritio y la dosis indicativa total. El correspondiente real decreto, en el caso de España, se comenzó a aplicar en el año 2008. No solamente el agua potable procedente de captaciones públicas está sujeta a control, sino que también se deben controlar las aguas comerciales. En ambos casos se han llevado a cabo estudios en todo el mundo. Existe un rango amplio de técnicas para la medida de la radiactividad en el agua de consumo. Este artículo describe tales técnicas e indica cuando se debe aplicar cada una de ellas. Por último, se muestran los resultados más importantes obtenidos tras el análisis de aguas potables y comerciales, tanto en

  7. Analysis CFD for the hydrogen transport in the primary containment of a BWR; Analisis CFD para el transporte de hidrogeno en la contencion primaria de un reactor BWR

    Energy Technology Data Exchange (ETDEWEB)

    Jimenez P, D. A.; Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Edificio 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico); Gomez T, A. M., E-mail: guerreroazteca_69@hotmail.com [ININ, Departamento de Sistemas Nucleares, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2014-10-15

    This study presents a qualitative and quantitative comparison among the CFD GASFLOW and OpenFOAM codes which are related with the phenomenon of hydrogen transport and other gases in the primary containment of a Boiling Water Reactor (BWR). GASFLOW is a commercial license code that is well validated and that was developed in Germany for the analysis of the gases transport in containments of nuclear reactors. On the other hand, OpenFOAM is an open source code that offers several evaluation solvers for different types of phenomena; in this case, the solver reacting-Foam is used to analyze the hydrogen transport inside the primary containment of the BWR. The results that offer the solver reacting-Foam of OpenFOAM are evaluated in the hydrogen transport calculation and the results are compared with those of the program of commercial license GASFLOW to see if is viable the use of the open source code in the case of the hydrogen transport in the primary containment of a BWR. Of the obtained results so much quantitative as qualitative some differences were identified between both codes, the differences (with a percentage of maximum error of 4%) in the quantitative results are small and they are considered acceptable for this analysis type, also, these differences are attributed mainly to the used transport models, considering that OpenFOAM uses a homogeneous model and GASFLOW uses a heterogeneous model. (Author)

  8. Coupled field effects in BWR stability simulations using SIMULATE-3K

    International Nuclear Information System (INIS)

    The SIMULATE-3K code is the transient analysis version of the Studsvik advanced nodal reactor analysis code, SIMULATE-3. Recent developments have focused on further broadening the range of transient applications by refinement of core thermal-hydraulic models and on comparison with boiling water reactor (BWR) stability measurements performed at Ringhals unit 1, during the startups of cycles 14 through 17

  9. Predictions by the proper orthogonal decomposition reduced order methodology regarding non-linear BWR stability

    International Nuclear Information System (INIS)

    Unexpected non-linear boiling water reactor (BWR) instability events in various plants, e.g. LaSalle II in 1988 and Oskarshamn II in 1990 amongst others, emphasize the major safety relevance and the existence of parameter regions with unstable behavior. A detailed description of the complete dynamical non-linear behavior is of paramount importance for BWR operation. An extension of state-of-the-art methodology towards a more general stability description, also applicable in the non-linear region, could lead to a deeper understanding of non-linear BWR stability phenomena. With the intention of a full non-linear stability analysis of the two-phase BWR system, the present paper aims at a general non-linear methodology capable to achieve reliable and numerical stable reduced order models (ROMs), representing the dynamical behavior of an original system based on a small number of transients. Model-specific options and aspects of the proposed methodology are focused on and illustrated by means of a strongly non-linear dynamical system showing complex oscillating behavior. Prediction capability of the proposed methodology is also addressed. (orig.)

  10. Identification of dose-reduction techniques for BWR and PWR repetitive high-dose jobs

    International Nuclear Information System (INIS)

    As a result of concern about the apparent increase in collective radiation dose to workers at nuclear power plants, this project will provide information to industry in preplanning for radiation protection during maintenance operations. This study identifies Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR) repetitive jobs, and respective collective dose trends and dose reduction techniques. 3 references, 2 tables

  11. Development and Testing of CTF to Support Modeling of BWR Operating Conditions

    Energy Technology Data Exchange (ETDEWEB)

    Salko, Robert K. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wysocki, Aaron [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Collins, Benjamin S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Godfrey, Andrew T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gosdin, Chris [Pennsylvania State Univ., University Park, PA (United States); Avramova, Maria [North Carolina State Univ., Raleigh, NC (United States)

    2016-01-29

    This milestone supports developing and assessing COBRA-TF (CTF) for the modeling of boiling water reactors (BWRs). This is achieved in three stages. First, a new preprocessor utility that is capable of handling BWR-specic design elements (e.g., channel boxes and large water rods) is developed. A previous milestone (L3:PHI.CTF.P12.01) led to the development of this preprocessor capability for single assembly models. This current milestone expands this utility so that it is applicable to multi-assembly BWR models that can be modeled in either serial or parallel. The second stage involves making necessary modications to CTF so that it can execute these new models. Specically, this means implementing an outer-iteration loop, specic to BWR models, that equalizes the pressure loss over all assemblies in the core (which are not connected due to the channel boxes) by adjusting inlet mass ow rate. A third stage involves assessing the standard convergence metrics that are used by CTF to determine when a simulation is steady-state. The nal stage has resulted in the implementation of new metrics in the code that give a better indication of how steady the solution is at convergence. This report summarizes these eorts and provides a demonstration of CTF's BWR-modeling capabilities. CASL-U-2016-1030-000

  12. Plutonium and Minor Actinides Recycling in Standard BWR using Equilibrium Burnup Model

    Directory of Open Access Journals (Sweden)

    Abdul Waris

    2008-03-01

    Full Text Available Plutonium (Pu and minor actinides (MA recycling in standard BWR with equilibrium burnup model has been studied. We considered the equilibrium burnup model as a simple time independent burnup method, which can manage all possible produced nuclides in any nuclear system. The equilibrium burnup code was bundled with a SRAC cell-calculation code to become a coupled cell-burnup calculation code system. The results show that the uranium enrichment for the criticality of the reactor, the amount of loaded fuel and the required natural uranium supply per year decrease for the Pu recycling and even much lower for the Pu & MA recycling case compared to those of the standard once-through BWR case. The neutron spectra become harder with the increasing number of recycled heavy nuclides in the reactor core. The total fissile rises from 4.77% of the total nuclides number density in the reactor core for the standard once-through BWR case to 6.64% and 6.72% for the Plutonium recycling case and the Pu & MA recycling case, respectively. The two later data may become the main basis why the required uranium enrichment declines and consequently diminishes the annual loaded fuel and the required natural uranium supply. All these facts demonstrate the advantage of plutonium and minor actinides recycling in BWR.

  13. The development of emergency core cooling systems in the PWR, BWR, and HWR Candu type of nuclear power plants

    International Nuclear Information System (INIS)

    Emergency core cooling systems in the PWR, BWR, and HWR-Candu type of nuclear power plant are reviewed. In PWR and BWR the emergency cooling can be catagorized as active high pressure, active low pressure, and a passive one. The PWR uses components of the shutdown cooling system: whereas the BWR uses components of pressure suppression contaiment. HWR Candu also uses the shutdown cooling system similar to the PWR except some details coming out from moderator coolant separation and expensive cost of heavy water. (author)

  14. Flex concept for US-A BWR extended loss of AC power events

    Energy Technology Data Exchange (ETDEWEB)

    Powers, J. [Toshiba America Nuclear Energy, Charlotte, North Carolina (United States); Aoyagi, Y.; Kataoka, K. [Toshiba Corporation, Kawasaki, Kanagawa (Japan); Thomas, S.; Mookhoek, B., E-mail: jim.powers@toshiba.com [Nuclear Innovation North America, Lake Jackson, Texas (United States)

    2015-09-15

    The US-Advanced Boiling Water Reactor (US-A BWR), certified by the US NRC, is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (Stp 3 and 4) Combined License Application (Cola) and incorporates numerous design and technology enhancements for improved safety performance. Nuclear Innovation North America (NINA) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. The Stp 3 and 4 project has finished the US NRC technical review of the Cola, and the final safety evaluation report (FSER) is scheduled to be issued by the US NRC in 2015. Following the accident at the Fukushima Dai-ichi plant, the US-A BWR was reviewed for Beyond Design Basis Event (BDBE) safety using industry and regulatory guidance for US NRC Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation of Beyond Design Basis External Events (BDBEE). By virtue of the design approach, the US-A BWR is capable of providing an indefinite coping period for a station blackout. The use of installed systems with extended coping times is a significant advantage of the US-A BWR compared to most of the plants currently operating in the U.S. In addition, the Stp 3 and 4 design incorporates enhancements consistent with the current US industry Diverse and Flexible Coping Strategies (Flex) initiative. The final technical topic requiring review by the US NRC Advisory Committee on Reactor Safeguards was the Flex Integrated Plan submitted by NINA, and this review was successfully completed. This paper summarizes the progress of the US-A BWR in licensing the Flex Integrated Plan for the project, and describes the technology and features of the US-A BWR design that contribute to safety post-Fukushima. It also provides an informational comparison of the design capabilities of the US-A BWR for extreme external events, and relates these capabilities to re

  15. Assessment of the Prony's method for BWR stability analysis

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz-Villafuerte, Javier, E-mail: javier.ortiz@inin.gob.m [Gerencia de Ciencias Aplicadas, Instituto Nacional de Investigaciones Nucleares, Carr. Mexico-Toluca S/N, La Marquesa, Ocoyoacac, Edo. Mexico 52750 (Mexico); Castillo-Duran, Rogelio, E-mail: rogelio.castillo@inin.gob.m [Gerencia de Ciencias Aplicadas, Instituto Nacional de Investigaciones Nucleares, Carr. Mexico-Toluca S/N, La Marquesa, Ocoyoacac, Edo. Mexico 52750 (Mexico); Palacios-Hernandez, Javier C., E-mail: javier.palacios@inin.gob.m [Gerencia de Ciencias Aplicadas, Instituto Nacional de Investigaciones Nucleares, Carr. Mexico-Toluca S/N, La Marquesa, Ocoyoacac, Edo. Mexico 52750 (Mexico)

    2011-05-15

    Highlights: This paper describes a method to determine the degree of stability of a BWR. Performance comparison between Prony's and common AR techniques is presented. Benchmark data and actual BWR transient data are used for comparison. DR and f results are presented and discussed. The Prony's method is shown to be a robust technique for BWR stability. - Abstract: It is known that Boiling Water Reactors are susceptible to present power oscillations in regions of high power and low coolant flow, in the power-flow operational map. It is possible to fall in one of such instability regions during reactor startup, since both power and coolant flow are being increased but not proportionally. One other possibility for falling into those areas is the occurrence of a trip of recirculation pumps. Stability monitoring in such cases can be difficult, because the amount or quality of power signal data required for calculation of the stability key parameters may not be enough to provide reliable results in an adequate time range. In this work, the Prony's Method is presented as one complementary alternative to determine the degree of stability of a BWR, through time series data. This analysis method can provide information about decay ratio and oscillation frequency from power signals obtained during transient events. However, so far not many applications in Boiling Water Reactors operation have been reported and supported to establish the scope of using such analysis for actual transient events. This work presents first a comparison of decay ratio and frequency oscillation results obtained by Prony's method and those results obtained by the participants of the Forsmark 1 and 2 Boiling Water Reactor Stability Benchmark using diverse techniques. Then, a comparison of decay ratio and frequency oscillation results is performed for four real BWR transient event data, using Prony's method and two other techniques based on an autoregressive modeling. The four

  16. Flex concept for US-A BWR extended loss of AC power events

    International Nuclear Information System (INIS)

    The US-Advanced Boiling Water Reactor (US-A BWR), certified by the US NRC, is a third generation, evolutionary boiling water reactor design which is the reference for the South Texas Project Units 3 and 4 (Stp 3 and 4) Combined License Application (Cola) and incorporates numerous design and technology enhancements for improved safety performance. Nuclear Innovation North America (NINA) is the License Applicant for this new build project, and Toshiba is the selected primary technology contractor. The Stp 3 and 4 project has finished the US NRC technical review of the Cola, and the final safety evaluation report (FSER) is scheduled to be issued by the US NRC in 2015. Following the accident at the Fukushima Dai-ichi plant, the US-A BWR was reviewed for Beyond Design Basis Event (BDBE) safety using industry and regulatory guidance for US NRC Order EA-12-049 Order Modifying Licenses with Regard to Requirements for Mitigation of Beyond Design Basis External Events (BDBEE). By virtue of the design approach, the US-A BWR is capable of providing an indefinite coping period for a station blackout. The use of installed systems with extended coping times is a significant advantage of the US-A BWR compared to most of the plants currently operating in the U.S. In addition, the Stp 3 and 4 design incorporates enhancements consistent with the current US industry Diverse and Flexible Coping Strategies (Flex) initiative. The final technical topic requiring review by the US NRC Advisory Committee on Reactor Safeguards was the Flex Integrated Plan submitted by NINA, and this review was successfully completed. This paper summarizes the progress of the US-A BWR in licensing the Flex Integrated Plan for the project, and describes the technology and features of the US-A BWR design that contribute to safety post-Fukushima. It also provides an informational comparison of the design capabilities of the US-A BWR for extreme external events, and relates these capabilities to re

  17. High burnup (41 - 61 GWd/tU) BWR fuel behavior under reactivity initiated accident conditions

    Energy Technology Data Exchange (ETDEWEB)

    Nakamura, Takehiko; Kusagaya, Kazuyuki; Yoshinaga, Makio; Uetsuka, Hiroshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-12-01

    High burnup boiling water reactor (BWR) fuel was pulse irradiated in the Nuclear Safety Research Reactor (NSRR) to investigate fuel behavior under cold startup reactivity initiated accident (RIA) conditions. Temperature, deformation, failure, and fission gas release behavior under the simulated RIA condition was studied in the tests. Fuel failure due to pellet-cladding mechanical interaction (PCMI) did not occur in the tests with typical domestic BWR fuel at burnups up to 56 GWd/tU, because they had limited cladding embrittlement due to hydrogen absorption of about 100 ppm or less. However, the cladding failure occurred in tests with fuel at a burnup of 61 GWd/tU, in which the peak hydrogen content in the cladding was above 150 ppm. This type of failure was observed for the first time in BWR fuels. The cladding failure occurred at fuel enthalpies of 260 to 360 J/g (62 to 86 cal/g), which were higher than the PCMI failure thresholds decided by the Japanese Nuclear Safety Commission. From post-test examinations of the failed fuel, it was found that the crack in the BWR cladding progressed in a manner different from the one in PWR cladding failed in earlier tests, owing to its more randomly oriented hydride distribution. Because of these differences, the BWR fuel was judged to have failed at hydrogen contents lower than those of the PWR fuel. Comparison of the test results with code calculations revealed that the PCMI failure was caused by thermal expansion of pellets, rather than by the fission gas expansion in the pellets. The gas expansion, however, was found to cause large cladding hoop deformation later after the cladding temperature escalated. (author)

  18. Behavior of small-sized BWR fuel under reactivity initiated accident conditions

    International Nuclear Information System (INIS)

    The present work was performed on this small-sized BWR fuel, where Zr liner and rod prepressurization were taken as experimental parameters. Experiment was done under simulated reactivity initiated accident (RIA) conditions at Nuclear Safety Research Reactor (NSRR) belonged to Japan Atomic Energy Research Institute (JAERI). Major remarks obtained are as follows: (1) Three different types of the fuel rods consisted of (a) Zr lined/pressurized (0.65MPa), (b) Zr lined/non-pressurized and (c) non-Zr lined/pressurized (o.65MPa) were used, respectively. Failure thresholds of these were not less than that (260 cal/g·fuel) described in Japanese RIA Licensing Guideline. Small-sized BWR and conventional 8 x 8 BWR fuels were considered to be in almost the same level in failure threshold. Failure modes of the three were (a) cladding melt/brittle, (b) cladding melt/brittle and (c) rupture by large ballooning, respectively. (2) The magnitude of pressure pulse at fuel fragmentation was also studied by lined/pressurized and non-lined/pressurized fuels. Above the energy deposition of 370 cal/g·fuel, mechanical energy (or pressure) was found to be released from these fragmented fuels. No measurable difference was, however, observed between the tested fuels and NSRR standard (and conventional 8 x 8 BWR) fuels. (3) It is worthy of mentioning that Zr liner tended to prevent the cladding from large ballooning. Non-lined/pressurized fuel tended to cause wrinkle deformation at cladding. Hence, cladding external was notched much by the wrinkles. (4) Time to fuel failure measured from the tested BWR fuels (pressurization < 0.6MPA) was longer than that measured from PWR fuels (pressurization < 3.2MPa). The magnitude of the former was of the order of 3 ∼ 6s, while that of the latter was < 1s. (J.P.N.)

  19. Study of the Utilization BWR Type Nuclear Power Reactor for Desalination Process

    International Nuclear Information System (INIS)

    The needs of fresh water increased by rapid population growth and industrials expansion, but these demands can not be prepared naturally. Following this case, seawater desalination becomes the primer option which can fulfill the need through the nuclear desalination technology. The coupled nuclear power reactor enables to supply thermal energy for auxiliary equipment and pumps operation. The utilization study of power reactor type BWR coupled with desalination process has been performed. The goal of study is to obtain characteristic data of desalted water specification which desalination system coupling with nuclear power plant produced energy for desalination process. The study is carried out by browsing data and information, and comprehensive review of thermal energy correlation between NPP with desalination process installation. According to reviewing are found that the thermal energy and electric power utilization from the nuclear power reactor are enable to remove the seawater to produce desalted water and also to operate auxiliary equipments. The assessment results is VK-300 reactor prototype, BWR type 250 MW(e) power are cogeneration unit can supplied hot steam temperature 285 °C to the extraction turbine to empower 150 MW electric power, and a part of hot steam 130 °C is use to operate desalination process and remind heat is distribute to the municipal and offices at that region. The coupled of VK-300 reactor power type BWR with desalination installation of MED type enable to produce desalted water with high quality distillate. Based on the economic calculation that the VK-300 reactor power of BWR type produced water distillate capacity is 300.000 m3/hour with cost US$ 0.58/m3. The coupling VK-300 reactor power type BWR with MED desalination plant is competitive economically. (author)

  20. Mobile crud and transportation of radioactivity in BWR

    Energy Technology Data Exchange (ETDEWEB)

    Hermansson, H-P. [Studsvik Nuclear AB, Nykoping (Sweden); LTU, Div. of Chemical Engineering, Lulea (Sweden); Hagg, J. [Ringhals AB, Varobacka (Sweden)

    2010-07-01

    Mobile crud is here referred to as a generic term for all types of particles that occur in the reactor water in BWRs and that are able to carry radioactivity. Previous results in this on-going series of studies in Swedish BWRs suggest that there are particles of different origins and function. A share may come from fuel crud and others may come from detachment, precipitation and dissolution processes in different parts of the BWR primary system, as well as from other system parts, such as the turbine/condenser. In addition, crud particles in this sense may come from purely mechanical processes such as degradation of graphite containing parts of the control rod drives. Therefore, the overall aim was to evaluate which particles are responsible for the transportation and distribution of radioactivity and also to clarify the chemical conditions under which they are formed. Furthermore the aim was to draw conclusions about how the chemistry would be like in order to avoid or at least minimize the formation of radioactivity distributing particles. A specific objective has also been to look into the importance of particle size for spreading of radioactivity in the primary system. Different types of crud particles are likely to have different characteristics in terms of function associated with transportation of radioactivity. The fuel crud is radioactive from the source and other types of crud can via surface processes, co-precipitation and other chemical and mechanical processes potentially affect the distribution of radioactivity in the primary system. In order to predict how operating parameters (e.g. stable, full power operation and scram) and chemical parameters (NWC/HWC/Zn, etc.) will affect the activity build-up on the system surfaces, it is important to know how the different types of crud are affected by these and related parameters. Fuel crud fixed on cladding ring samples, as well as mobile crud from the reactor water captured on filters, were examined by

  1. Radial optimization of a BWR fuel cell using genetic algorithms

    International Nuclear Information System (INIS)

    The development of the application of the Genetic Algorithms (GA) to the optimization of the radial distribution of enrichment in a cell of fuel of a BWR (Boiling Water Reactor) is presented. The optimization process it was ties to the HELIOS simulator, which is a transport code of neutron simulation of fuel cells that has been validated for the calculation of nuclear banks for BWRs. With heterogeneous radial designs can improve the radial distribution of the power, for what the radial design of fuel has a strong influence in the global design of fuel recharges. The optimum radial distribution of fuel bars is looked for with different enrichments of U235 and contents of consumable poison. For it is necessary to define the representation of the solution, the objective function and the implementation of the specific optimization process to the solution of the problem. The optimization process it was coded in 'C' language, it was automated the creation of the entrances to the simulator, the execution of the simulator and the extraction, in the exit of the simulator, of the parameters that intervene in the objective function. The objective function includes four parameters: average enrichment of the cell, average gadolinia concentration of the cell, peak factor of radial power and k-infinite multiplication factor. To be able to calculate the parameters that intervene in the objective function, the one evaluation process of GA was ties to the HELIOS code executed in a Compaq Alpha workstation. It was applied to the design of a fuel cell of 10 x 10 that it can be employee in the fuel assemble designs that are used at the moment in the Laguna Verde Nucleo electric Central. Its were considered 10 different fuel compositions which four contain gadolinia. Three heuristic rules that consist in prohibiting the placement of bars with gadolinia in the ends of the cell, to place the compositions with the smallest enrichment in the corners of the cell and to fix the placement of

  2. Axial profiles of burned and fraction of holes for calculations of criticality with credit for BWR fuel burning; Perfiles axiales de quemado y fraccion de huecos para calculos de criticidad con credito al quemado para combustible BWR

    Energy Technology Data Exchange (ETDEWEB)

    Casado Sanchez, C.; Rubio Oviedo, P.

    2014-07-01

    This paper presents a method to define surround profiles of burning and fraction of holes suited for use in applications of credit to burning of BWR fuel from results obtained with the module STARBUCS of SCALE. (Author)

  3. Agua y abastecimiento: gestión de cuerpos de agua en la ciudad de San Luis Potosí (México, 1831-1887

    Directory of Open Access Journals (Sweden)

    Yuritzi Hernández Fuentes

    2015-07-01

    Full Text Available Este trabajo plantea una aproximación sobre la gestión de cuerpos de agua y de los sistemas hidráulicos en la ciudad de San Luis Potosí (México, durante el período 1831-1887, a partir de las medidas que tomó el gobierno municipal para atender las necesidades de abastecimiento de agua. El texto analiza dos proyectos importantes en el manejo del agua: el acueducto La Cañada del Lobo y las acciones sobre las derivaciones de aguas a través de La Corriente. Los dos proyectos enfrentaron diversos problemas, entre ellos, el brote de enfermedades asociadas a los cuerpos de agua y la escasez del flujo de líquido a través del acueducto de La Cañada del Lobo

  4. Agua y abastecimiento: gestión de cuerpos de agua en la ciudad de San Luis Potosí (México, 1831-1887

    Directory of Open Access Journals (Sweden)

    Yuritzi Hernández Fuentes

    2015-01-01

    Full Text Available Este trabajo plantea una aproximación sobre la gestión de cuerpos de agua y de los sistemas hidráulicos en la ciudad de San Luis Potosí (México, durante el período 1831-1887, a partir de las medidas que tomó el gobierno municipal para atender las necesidades de abastecimiento de agua. El texto analiza dos proyectos importantes en el manejo del agua: el acueducto La Cañada del Lobo y las acciones sobre las derivaciones de aguas a través de La Corriente. Los dos proyectos enfrentaron diversos problemas, entre ellos, el brote de enfermedades asociadas a los cuerpos de agua y la escasez del flujo de líquido a través del acueducto de La Cañada del Lobo.

  5. Detección de mutacarcinógenos y genotoxicidad en aguas residuales que surten dos plantas de tratamiento de agua de consumo

    Directory of Open Access Journals (Sweden)

    Naranjo LC.

    2001-06-01

    Full Text Available Las aguas residuales están cargadas de gran variedad de mutacarcinógenos entre ellos Hidro-carburos Policíclicos aromáticos, nitrosaminas y aminas Heterocíclicas todos ellos formadosdurante la combustión de material orgánico y en alimentos proteicos cocidos a altas tempe-raturas. Dichos mutacarcinógenos llegan a las aguas residuales especialmente a través de laorina y heces. Las aguas residuales procedentes de la población del Retiro son vertidas al ríoPantanillo después de ser tratadas en una planta a base de lodos activados. Este río surte repre-sas que alimentan las plantas de tratamiento de agua de consumo la Ayurá y Rionegro quedistribuyen agua potable a más de 2’000.000 de habitantes.

  6. Phenomenology of severe accidents in BWR type reactors. First part; Fenomenologia de accidentes severos en reactores nucleares de agua en ebullicion. Primera parte

    Energy Technology Data Exchange (ETDEWEB)

    Sandoval V, S. [Instituto de Investigaciones Electricas, Gerencia de Energia Nuclear, Av. Reforma 113, Col. Palmira, 62490 Cuernavaca, Morelos (Mexico)

    2003-07-01

    A Severe Accident in a nuclear power plant is a deviation from its normal operating conditions, resulting in substantial damage to the core and, potentially, the release of fission products. Although the occurrence of a Severe Accident on a nuclear power plant is a low probability event, due to the multiple safety systems and strict safety regulations applied since plant design and during operation, Severe Accident Analysis is performed as a safety proactive activity. Nuclear Power Plant Severe Accident Analysis is of great benefit for safety studies, training and accident management, among other applications. This work describes and summarizes some of the most important phenomena in Severe Accident field and briefly illustrates its potential use based on the results of two generic simulations. Equally important and abundant as those here presented, fission product transport and retention phenomena are deferred to a complementary work. (Author)

  7. Gestión y cultura del agua en Nuevo Laredo, Tamaulipas

    Directory of Open Access Journals (Sweden)

    Jesús FRAUSTO ORTEGA

    2015-01-01

    Full Text Available Este trabajo ref l exiona sobre la relación entre la gestión del agua urbana y la cultura del agua, bajo el supuesto de que hay una contradicción entre estos dos aspectos. Se enfoca en el servicio de agua potable de Nuevo Laredo. La metodología contempla la revisión de indi - cadores de gestión del servicio, consulta de fuentes bibliográf i cas sobre la cultura del agua y entrevistas a actores locales sobre la concientización de la gente en el cuidado del recurso. El trabajo encuentra prácticas inef i cientes de manejo del agua que contradicen los objetivos de la política de la cultura del agua.

  8. Design and axial optimization of nuclear fuel for BWR reactors; Diseno y optimizacion axial de combustible nuclear para reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Garcia V, M.A

    2006-07-01

    In the present thesis, the modifications made to the axial optimization system based on Tabu Search (BT) for the axial design of BWR fuel type are presented, developed previously in the Nuclear Engineering Group of the UNAM Engineering Faculty. With the modifications what is mainly looked is to consider the particular characteristics of the mechanical design of the GE12 fuel type, used at the moment in the Laguna Verde Nucleo electric Central (CNLV) and that it considers the fuel bars of partial longitude. The information obtained in this thesis will allow to plan nuclear fuel reloads with the best conditions to operate in a certain cycle guaranteeing a better yield and use in the fuel burnt, additionally people in charge in the reload planning will be favored with the changes carried out to the system for the design and axial optimization of nuclear fuel, which facilitate their handling and it reduces their execution time. This thesis this developed in five chapters that are understood in the following way in general: Chapter 1: It approaches the basic concepts of the nuclear energy, it describes the physical and chemical composition of the atoms as well as that of the uranium isotopes, the handling of the uranium isotope by means of the nuclear fission until arriving to the operation of the nuclear reactors. Chapter 2: The nuclear fuel cycle is described, the methods for its extraction, its conversion and its enrichment to arrive to the stages of the nuclear fuel management used in the reactors are described. Beginning by the radial design, the axial design and the core design of the nuclear reactor related with the fuel assemblies design. Chapter 3: the optimization methods of nuclear fuel previously used are exposed among those that are: the genetic algorithms method, the search methods based on heuristic rules and the application of the tabu search method, which was used for the development of this thesis. Chapter 4: In this part the used methodology to the

  9. Tratamiento de aguas industriales mediante reactor biológico de membranas

    OpenAIRE

    Aznar Jiménez, Antonio

    2008-01-01

    El Laboratorio de Ingeniería para el Tratamiento de Aguas de la Universidad Carlos III de Madrid, de investigación y servicios en el tratamiento de aguas residuales, optimiza el diseño y puesta a punto de reactores biológicos de membranas (MBR), indicados para obtener agua depurada de alta calidad y/o aumentar la capacidad de tratamiento.

  10. Current and anticipated use of thermal-hydraulic codes for BWR transient and accident analyses in Japan

    Energy Technology Data Exchange (ETDEWEB)

    Arai, Kenji; Ebata, Shigeo [Toshiba Corp., Yokohama (Japan)

    1997-07-01

    This paper summarizes the current and anticipated use of the thermal-hydraulic and neutronic codes for the BWR transient and accident analyses in Japan. The codes may be categorized into the licensing codes and the best estimate codes for the BWR transient and accident analyses. Most of the licensing codes have been originally developed by General Electric. Some codes have been updated based on the technical knowledge obtained in the thermal hydraulic study in Japan, and according to the BWR design changes. The best estimates codes have been used to support the licensing calculations and to obtain the phenomenological understanding of the thermal hydraulic phenomena during a BWR transient or accident. The best estimate codes can be also applied to a design study for a next generation BWR to which the current licensing model may not be directly applied. In order to rationalize the margin included in the current BWR design and develop a next generation reactor with appropriate design margin, it will be required to improve the accuracy of the thermal-hydraulic and neutronic model. In addition, regarding the current best estimate codes, the improvement in the user interface and the numerics will be needed.

  11. Proyecto de abastecimiento de agua a Herrera de Ibio

    OpenAIRE

    Baldó García, Ignacio

    2015-01-01

    El Trabajo de Fin de Grado realizado es un proyecto del abastecimiento de agua a la población de Herrera de Ibio, municipio de Mazcuerras en la Comunidad Autónoma de Cantabria, España. Se desarrollan todas las partes que componen un abastecimiento de agua: • Captación • Red de tuberías • Depósito La captación se realiza de un manantial de montaña a una cota de a 277 m. Desde ese punto parte la tubería en presión que une la captación con el depósito y tiene una longitud de 1.048 metros. El inf...

  12. DEMANDA DE AGUA PARA USO RESIDENCIAL Y COMERCIAL

    OpenAIRE

    Sandra Gabriela Gómez-Ugalde; Ramón Valdivia-Alcalá; José Alberto García-Salazar; José Saturnino Mora-Flores

    2012-01-01

    La escasez de agua y la sobreexplotación de los mantos acuíferos es un problema de índole ambiental y económico que afecta a la población de Texcoco, Estado de México. Con el objetivo de cuantificar la demanda de agua en el sector doméstico y comercial y las variables que la determinan, ante la problemática de sobreexplotación de los mantos acuíferos de Texcoco, se plantearon dos modelos econométricos de regresión múltiple para determinar si una política de precios es adecuada para la adminis...

  13. Coolant Density and Control Blade History Effects in Extended BWR Burnup Credit

    Energy Technology Data Exchange (ETDEWEB)

    Ade, Brian J [ORNL; Marshall, William BJ J [ORNL; Bowman, Stephen M [ORNL; Gauld, Ian C [ORNL; Ilas, Germina [ORNL; Martinez-Gonzalez, Jesus S [ORNL

    2015-01-01

    Oak Ridge National Laboratory and the US Nuclear Regulatory Commission have initiated a multiyear project to investigate the application of burnup credit (BUC) for boiling water reactor (BWR) fuel in storage and transportation casks. This project includes two phases. The first phase investigates the applicability of peak reactivity methods currently used for spent fuel pools to spent fuel storage and transportation casks and the validation of reactivity (keff) calculations and predicted spent fuel compositions. The second phase focuses on extending BUC beyond peak reactivity. This paper documents work performed to date investigating some aspects of extended BUC. (The technical basis for application of peak reactivity methods to BWR fuel in storage and transportation systems is presented in a companion paper.) Two reactor operating parameters are being evaluated to establish an adequate basis for extended BWR BUC: (1) the effect of axial void profile and (2) the effect of control blade utilization during operation. A detailed analysis of core simulator data for one cycle of a modern operating BWR plant was performed to determine the range of void profiles and the variability of the profile experienced during irradiation. Although a single cycle does not provide complete data, the data obtained are sufficient to determine the primary effects and to identify conservative modeling approaches. These data were used in a study of the effect of axial void profile. The first stage of the study was determination of the necessary moderator density temporal fidelity in depletion modeling. After the required temporal fidelity was established, multiple void profiles were used to examine the effect on cask reactivity. The results of these studies are being used to develop recommendations for conservatively modeling the void profile effects for BWR depletion calculations. The second operational parameter studied was control blade history. Control blades are inserted in

  14. Comentarios sobre el comercio y mercados del agua subterránea en Canarias

    OpenAIRE

    Custodio Gimena, Emilio

    2011-01-01

    Los mercados del agua subterránea son una interesante posibilidad para la gestión del agua subterránea. Estos mercados han existido desde hace muchas décadas en las islas principales del Archipiélago Canario y han contribuido en parte al importante proceso de desarrollo del último medio siglo. Con variantes de isla a isla y de un lugar a otro, los mercados de agua subterránea son la superposición de tres elementos, el de propiedad del agua a modo de participaciones y acciones que se compran y...

  15. Parámetros de control de los procesos de regeneración del agua

    OpenAIRE

    Gómez López, Marc

    2008-01-01

    El agua regenerada es aquella agua proveniente de un proceso de depuración a la cual se le aplica un tratamiento adicional (llamado de regeneración) que permite devolverle, parcial o totalmente, el nivel de calidad que tenía antes de ser utilizada. Para que estas aguas constituyan un recurso hídrico a tener en cuenta, es necesario realizar una reutilización planificada que consiste en establecer unas normas de calidad en función del uso final del agua regenerada así como un cor...

  16. Diseño, monitorización y control para un tanque de agua potable

    OpenAIRE

    Fernández Varo, José Antonio

    2005-01-01

    Este proyecto trata de resolver la problemática que existe en la planta de tratamiento de agua de la Central Térmica de Ciclos Combinados (CTCC) de San Adrián del Besós. Debido al poco cloro en el suministro de agua de red, existe la posibilidad de que se produzcan brotes de legionela en el tanque de agua potable. Por este motivo y por la normativa vigente (DOGC núm. 3652/02, RD 140/03), se obliga a tener un control sobre el agua almacenada. A partir de este hecho, se han realizado estudio...

  17. El agua virtual: una oportunidad para la Argentina en el contexto internacional actual

    OpenAIRE

    Jaime, Ana María

    2013-01-01

    En forma recurrente, se considera que el agua desempeñará en el siglo XXI, el rol que tuvo el petróleo en el siglo XX. La diferencia fundamental entre ambos recursos es que el agua es un “recurso finito, vulnerable y esencial para mantener la vida, el desarrollo y el medio ambiente”, según la definición de la Conferencia Internacional sobre el Agua y el Medio Ambiente realizada en la ciudad de Dublin en el año 1992. El agotamiento y la creciente escasez de agua en el mundo, el cambio climátic...

  18. Desarrollo de catalizadores para la eliminación de nitratos en agua de consumo humano

    OpenAIRE

    Jaworski, María

    2012-01-01

    Es bien sabido que la contaminación de las aguas puede proceder de fuentes naturales o de actividades humanas. En la actualidad la más importante, sin duda, es la provocada por el hombre: el desarrollo y la industrialización supone un mayor uso de agua. Así, las actividades de agricultura y ganadería, producen vertidos de pesticidas, fertilizantes y restos orgánicos de animales y plantas que contaminan de una forma difusa, pero muy notable las aguas, en particular las subterráneas. Las aguas ...

  19. Relaciones agua-solutos-matriz insoluble en algunos sistemas alimentarios.

    OpenAIRE

    Chenoll Cuadros, Maria De La Creu

    2008-01-01

    Una gran parte de los alimentos estructurados pueden considerarse, de forma simplificada, constituidos por tres componentes: una matriz insoluble (que puede ser, por ejemplo, proteica, o compuesta por carbohidratos), agua y una serie de sólidos solubles (añadidos o no). Las relaciones de estos componentes entre sí, sus interacciones, y el modo en que varían durante determinados procesos industriales son factores que condicionan sus propiedades, tales como nutricionales y de calidad sensorial ...

  20. BWR Spent Nuclear Fuel Interfacial Bonding Efficiency Study

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Jy-An John [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Jiang, Hao [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-04-30

    The objective of this project is to perform a systematic study of spent nuclear fuel (SNF, also known as “used nuclear fuel” [UNF]) integrity under simulated transportation environments using the Cyclic Integrated Reversible-Bending Fatigue Tester (CIRFT) hot-cell testing technology developed at Oak Ridge National Laboratory (ORNL) in August 2013. Under Nuclear Regulatory Commission (NRC) sponsorship, ORNL completed four benchmark tests, four static tests, and twelve dynamic or cycle tests on H. B. Robinson (HBR) high burn-up (HBU) fuel. The clad of the HBR fuels was made of Zircaloy-4. Testing was continued in fiscal year (FY) 2014 using Department of Energy (DOE) funds. Additional CIRFT testing was conducted on three HBR rods; two specimens failed, and one specimen was tested to over 2.23 × 107 cycles without failing. The data analysis on all the HBR SNF rods demonstrated that it is necessary to characterize the fatigue life of the SNF rods in terms of (1) the curvature amplitude and (2) the maximum absolute of curvature extremes. The maximum extremes are significant because they signify the maximum tensile stress for the outer fiber of the bending rod. CIRFT testing has also addressed a large variation in hydrogen content on the HBR rods. While the load amplitude is the dominant factor that controls the fatigue life of bending rods, the hydrogen content also has an important effect on the lifetime attained at each load range tested. In FY 15, eleven SNF rod segments from the Limerick BWR were tested using the ORNL CIRFT equipment; one test under static conditions and ten tests under dynamic loading conditions. Under static unidirectional loading, a moment of 85 N·m was obtained at a maximum curvature of 4.0 m-1. The specimen did not show any sign of failure during three repeated loading cycles to a similar maximum curvature. Ten cyclic tests were conducted with amplitudes varying from 15.2 to 7.1 N·m. Failure was observed in nine of

  1. Tratamiento de aguas residuales textiles mediante un biorreactor de membrana

    Directory of Open Access Journals (Sweden)

    Lorena Salazar Gámez

    2009-01-01

    Full Text Available En la actualidad, los investigadores dedicados al tratamiento de agua residual se han esforzado por obtener mejores rendimientos de depuración, reducción de costos de operación y mantenimiento en la generación de procesos que posean una elevada flexibilidad para soportar las variaciones en el afluente, que generen una mínima producción de lodos y que sean diseñados en condiciones mínimas de área. En este trabajo se expone una nueva tecnología en el tratamiento de agua residual, la de los Biorreactores de Membrana (BRM, que nace como respuesta de estas exigencias, ya que combina el sistema de fangos activados (FA convencional y la filtración por membrana. Así mismo evalúa comparativamente el proceso de fangos activados y Biorreactor de Membrana a escala piloto en aguas de difícil tratamiento como son los efluentes textiles. Los resultados indican que el proceso de BRM reduce un 82 - 92% de la materia orgánica (DQO, un 95% de los sólidos en suspensión totales (SST, mientras que el proceso de fangos activados reduce un 54- 70% de la materia orgánica (DQO y un 32- 43% de SST.

  2. MICROCONTAMINANTES EMERGENTES EN AGUAS: TIPOS Y SISTEMAS DE TRATAMIENTO

    Directory of Open Access Journals (Sweden)

    Yolanda Patiño

    2014-01-01

    Full Text Available En el presente artículo se revisan las distintas clases de contaminantes emergentes, su origen y uso, y su presencia en las cuencas españolas, tanto en aguas superficiales como subterráneas. Los microcontaminantes emergentes son compuestos de distinto origen y naturaleza que hasta ahora habían pasado inadvertidos debido a su baja concentración (en el orden de las ppb y sobre los que no hay regulación específica. Están divididos en seis grandes grupos y muchos de ellos se comportan como disruptores endocrinos, provocando efectos negativos sobre la salud humana y el medio ambiente. Se encuentran presentes en las aguas ya que las plantas de tratamiento de aguas residuales no están diseñadas para su eliminación, por lo que están siendo vertidos. Se discuten las distintas alternativas para su eliminación – tratamiento físico-químicos, biológicos y tecnologías híbridas - , destacando dentro de los procesos físico-químicos el empleo de procesos avanzados de oxidación (AOPs que están resultando muy prometedores.

  3. Calderón y las aguas revueltas de Guárdate del agua mansa

    Directory of Open Access Journals (Sweden)

    García Santo-Tomás, Enrique

    2004-04-01

    Full Text Available Guárdate del agua mansa es una de las piezas calderonianas de mayor actualidad. La comedia desarrolla el tema de las apariencias tratado desde una óptica bastante original, en donde el «agua mansa» alude a todas aquellas jóvenes que parecen no tener capacidad de acción, pero que al final son con quienes hay que estar más precavido. Sin embargo, la pieza también nos habla de un fascinante Madrid que seduce a la juventud ya desde el mismo inicio de la pieza, un Madrid visual que entra por los ojos y que conquista al instante.…

  4. Microorganismos indicadores de la calidad del agua potable en cuba

    Directory of Open Access Journals (Sweden)

    Marlen Robert Pullés

    2014-01-01

    Full Text Available Los agentes patógenos transmitidos por el agua constituyen un problema mundial que demanda un urgente control. Las bacterias, virus y parásitos causan enfermedades que varían en severidad. La determinación de microorganismos en el agua de consumo y su concentración proporcionan herramientas de control, indispensables para la toma de decisiones. Los controles rutinarios de todos los microorganismos, potencialmente riesgosos para la salud, resultan difíciles de llevar a cabo, debido a que ello representa, varios días de análisis y costos elevados. Para hacer una evaluación sencilla, económica y fiable de la presencia de patógenos, la vigilancia de la calidad del agua se efectúa mediante indicadores de contaminación, aplicando diferentes enfoques técnicos, cada uno con sus cualidades, defectos y limitaciones. El objetivo de esta revisión fue analizar el enfoque actual existente a nivel nacional e internacional, en relación con los indicadores microbiológicos empleados para la evaluación del agua potable, como elementos clave, y a partir de estos, proponer un esquema de monitoreo en Cuba. Los resultados reflejaron, la alternativa de considerar, la aplicación de un esquema para monitoreo complementario en Cuba, que incluya como indicadores de contaminación del agua potable además de las bacterias, algunos agentes biológicos no considerados en la norma, como los virus y los parásitos. Asimismo indicaron la necesidad de establecer un valor de referencia y definir los microorganismos a emplear en los monitoreos de validación, operativo o verificación. Esta propuesta aportaría importante información para la actualización de la norma cubana sobre la base del conocimiento de los estándares internacionales más reconocidos.

  5. Effect of Control Blade History, and Axial Coolant Density and Burnup Profiles on BWR Burnup Credit

    Energy Technology Data Exchange (ETDEWEB)

    Ade, Brian J [ORNL; Marshall, William BJ J [ORNL; Martinez-Gonzalez, Jesus S [ORNL

    2015-05-01

    Oak Ridge National Laboratory (ORNL) and the US Nuclear Regulatory Commission (NRC) have initiated a multiyear project to investigate the application of burnup credit (BUC) for boiling water reactor (BWR) fuel in storage and transportation systems (often referred to as casks) and spent fuel pools (SFPs). This work is divided into two main phases. The first phase investigated the applicability of peak reactivity methods currently used in SFPs to transportation and storage casks and the validation of reactivity calculations and spent fuel compositions within these methods. The second phase focuses on extending BUC beyond peak reactivity. This paper documents the analysis of the effects of control blade insertion history, and moderator density and burnup axial profiles for extended BWR BUC.

  6. Droplet entrainment and deposition rate models for determination of boiling transition in BWR fuel assembly

    International Nuclear Information System (INIS)

    Droplet entrainment and deposition rates are of vital importance for mechanistic determination of critical power and location of boiling transition in a BWR fuel assembly. Data from high-pressure, high-temperature steam-water adiabatic experiments conducted in very tall test sections are used to develop a combination of equilibrium entrainment-deposition rate. Application of this combination to the heated tests conducted in a shorter test section of typical height of a BWR fuel assembly shows that correct split of total liquid in form of the film and droplets at the onset of annular-mist flow regime is also important to obtain good prediction of film flow rates/entrainment fraction. The improved model is then applied to simulate critical power tests in annulus and rod bundles. (author)

  7. Discussion on 'Electrochemical potential measurements under simulated BWR water chemistry conditions'

    International Nuclear Information System (INIS)

    In the above-referenced paper, Lin et al. report measurements of the corrosion potentials (the electrochemical potential or ECP) of types 304 and 316 SS in simulated boiling water reactor (BWR) heat transport environments at 270 C. There are four reasons for this discussion: to demonstrate that their theoretical explanation for the variation of ECP with oxygen concentration is inadequate; to show that their flow velocity/ECP results for oxygenated and hydrogenated systems are experimentally inconclusive because of experimental problems and, in any case, are inconsistent with electrochemical expectations; to cite previous work on the origin of the ECP of stainless steels in BWR environments that was not referenced in the paper but provides a basis for interpreting their data; and to identify previous work on the effect of Cu2+ on the ECP of type 304 SS, which was also not referenced in the paper

  8. Investigation of distorted geometry simulation of pool dynamics in horizontal-vent BWR containments

    International Nuclear Information System (INIS)

    Experiments were conducted to investigate the accuracy of distorted geometry testing of pool dynamics in horizontal-vent BWR containments. Distorted-geometry testing implies testing in systems where the flow-wise dimensions are full scale, but all dimensions transverse to the flow are reduced in the same proportion. The assumption is that flow velocities, pressures and other thermodynamic properties will be the same in the distorted-geometry system as in its correctly proportioned counterpart. The experiments, which were done at small scale using the established scaling laws, showed that the geometric distortions can have a significant effect on the pool swell under conditions which are roughly representative of horizontal-vent BWR containment systems during a LOCA. Breakthrough occurred later, the water ligament was thicker, and pool velocity lower in a system where the cross-sectional areas were reduced by a factor of three. Some reasons for the differences are discussed

  9. Aggressive chemical decontamination tests on small valves from the Garigliano BWR

    International Nuclear Information System (INIS)

    In order to check the effectiveness of direct chemical decontamination on small and complex components, usually considered for storage without decontamination because of the small amount, some tests were performed on the DECO experimental loop. Four small stainless steel valves from the primary system of the Garigliano BWR were decontaminated using mainly aggressive chemicals such as HC1, HF, HNO3 and their mixtures. On two valves, before the treatment with aggressive chemicals, a step with soft chemical (oxalic and citric acid mixture) was performed in order to see whether a softening action enhances the following aggressive decontamination. Moreover, in order to increase as much as possible the decontamination effectiveness, a decontamination process using ultrasounds jointly with aggressive chemicals was investigated. After an intensive laboratory testing programme, two smaller stainless steel valves from the primary system of the Garigliano BWR were decontaminated using ultrasounds in aggressive chemical solutions

  10. Detección de mutacarcinógenos y genotoxicidad en aguas residuales que surten dos plantas de tratamiento de agua de consumo

    OpenAIRE

    Naranjo LC.; Zuleta M.; López C.; Orozco LY.

    2001-01-01

    Las aguas residuales están cargadas de gran variedad de mutacarcinógenos entre ellos Hidro-carburos Policíclicos aromáticos, nitrosaminas y aminas Heterocíclicas todos ellos formadosdurante la combustión de material orgánico y en alimentos proteicos cocidos a altas tempe-raturas. Dichos mutacarcinógenos llegan a las aguas residuales especialmente a través de laorina y heces. Las aguas residuales procedentes de la población del Retiro son vertidas al ríoPantanillo después de ser tratadas en un...

  11. SIMULATE-3K simulation of the Ringhals 1 BWR stability measurements

    International Nuclear Information System (INIS)

    SIMULATE-3K is the transient analysis version of the SIMULATE-3 advanced nodal reactor analysis code. The transient form of the 3-D QPANDA nodal neutronics model has been coupled to a 3-D channel thermal-hydraulics model and a 1-D transient excore peripheral systems model. This paper presents comparisons of SIMULATE-3K calculations and measured BWR stability data from Ringhals Unit 1, Cycles 14-17, as formulated by the OECD/NEACRP. (author)

  12. A Deterministic/probalistic analysis of Ex-Vessel melt risk in a BWR

    OpenAIRE

    Abal López, Javier

    2006-01-01

    The present study is concerned with deterministic and probabilistic analysis of ex-vessel melt risks in a Swedish designed BWR plant. The focus is placed on a station blackout (SBO) scenario, with immediate SCRAM and subsequent activation of the main steam valve isolation (at 52 s). Four sequences were examined in detail to study the effect of two valves systems related to the operation of ADS (Automatic Depressurization System), and cavity flooding by water from suppression po...

  13. Transient boiling and void formation during postulated reactivity-initiated accident in BWR: Experimental simulation

    International Nuclear Information System (INIS)

    The current safety analysis of the postulated reactivity initiated accident (RIA) in the boiling water reactor (BWR) neglects the favorable effect of voids because of the difficulties in predicting void formation in transient boiling. This paper presents experimental results on the transient void formation in response to a step heating of a surface facing to low-pressure subcooled water. The void fractions are measured by measuring optically the water surface movement or water velocity induced by the void formation. (author)

  14. Proving test on thermal-hydraulic performance of BWR fuel assemblies

    International Nuclear Information System (INIS)

    Nuclear Power Engineering Corporation (NUPEC) has conducted a proving test for thermal-hydraulic performance of BWR fuel (high-burnup 8 x 8, 9 x 9) assemblies entrusted by the Ministry of Economy, Trade and Industry (NUPEC-TH-B Project). The high-burnup 8 x 8 fuel (average fuel assembly discharge burnup: about 39.5 GWd/t), has been utilized from 1991. And the 9 x 9 fuel (average fuel assembly discharge burnup: about 45 GWd/t), has started to be used since 1999. There are two types (A-type and B-type) of fuel design in 9 x 9 fuel assembly. Using an electrically heated test assembly which simulated a BWR fuel bundle on full scale, flow induced vibration, pressure drop, critical power under steady state condition and post-boiling transition (post-BT) tests were carried out in an out-of pile test facility that can simulate the high pressure and high temperature conditions of BWRs. This paper completed the results of 9 x 9 fuel combined with the previously reported results of high-burnup 8 x 8 fuel. As a result of NUPEC-TH-B Project, the validity of the current BWR thermal-hydraulic design method was confirmed and the reliability of BWR thermo-hydraulic fuel performance was demonstrated. Based on the test data, a new correlation of the estimation of fuel rod vibration amplitude, new post-BT heat transfer and rewet correlations for the estimation of fuel rod surface temperature were developed. (author)

  15. Single pin BWR benchmark problem for coupled Monte Carlo - Thermal hydraulics analysis

    Energy Technology Data Exchange (ETDEWEB)

    Ivanov, A.; Sanchez, V. [Karlsruhe Inst. of Technology, Inst. for Neutron Physics and Reactor Technology, Herman-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Hoogenboom, J. E. [Delft Univ. of Technology, Faculty of Applied Sciences, Mekelweg 15, 2629 JB Delft (Netherlands)

    2012-07-01

    As part of the European NURISP research project, a single pin BWR benchmark problem was defined. The aim of this initiative is to test the coupling strategies between Monte Carlo and subchannel codes developed by different project participants. In this paper the results obtained by the Delft Univ. of Technology and Karlsruhe Inst. of Technology will be presented. The benchmark problem was simulated with the following coupled codes: TRIPOLI-SUBCHANFLOW, MCNP-FLICA, MCNP-SUBCHANFLOW, and KENO-SUBCHANFLOW. (authors)

  16. Status report: Intergranular stress corrosion cracking of BWR core shrouds and other internal components

    International Nuclear Information System (INIS)

    On July 25, 1994, the US Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 94-03 to obtain information needed to assess compliance with regulatory requirements regarding the structural integrity of core shrouds in domestic boiling water reactors (BWRs). This report begins with a brief description of the safety significance of intergranular stress corrosion cracking (IGSCC) as it relates to the design and function of BWR core shrouds and other internal components. It then presents a brief history of shroud cracking events both in the US and abroad, followed by an indepth summary of the industry actions to address the issue of IGSCC in BWR core shrouds and other internal components. This report summarizes the staff's basis for issuing GL 94-03, as well as the staff's assessment of plant-specific responses to GL 94-03. The staff is continually evaluating the licensee inspection programs and the results from examinations of BWR core shrouds and other internal components. This report is representative of submittals to and evaluations by the staff as of September 30, 1995. An update of this report will be issued at a later date

  17. Status report: Intergranular stress corrosion cracking of BWR core shrouds and other internal components

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    On July 25, 1994, the US Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 94-03 to obtain information needed to assess compliance with regulatory requirements regarding the structural integrity of core shrouds in domestic boiling water reactors (BWRs). This report begins with a brief description of the safety significance of intergranular stress corrosion cracking (IGSCC) as it relates to the design and function of BWR core shrouds and other internal components. It then presents a brief history of shroud cracking events both in the US and abroad, followed by an indepth summary of the industry actions to address the issue of IGSCC in BWR core shrouds and other internal components. This report summarizes the staff`s basis for issuing GL 94-03, as well as the staff`s assessment of plant-specific responses to GL 94-03. The staff is continually evaluating the licensee inspection programs and the results from examinations of BWR core shrouds and other internal components. This report is representative of submittals to and evaluations by the staff as of September 30, 1995. An update of this report will be issued at a later date.

  18. Analysis CFD for the hydrogen transport in the primary containment of a BWR

    International Nuclear Information System (INIS)

    This study presents a qualitative and quantitative comparison among the CFD GASFLOW and OpenFOAM codes which are related with the phenomenon of hydrogen transport and other gases in the primary containment of a Boiling Water Reactor (BWR). GASFLOW is a commercial license code that is well validated and that was developed in Germany for the analysis of the gases transport in containments of nuclear reactors. On the other hand, OpenFOAM is an open source code that offers several evaluation solvers for different types of phenomena; in this case, the solver reacting-Foam is used to analyze the hydrogen transport inside the primary containment of the BWR. The results that offer the solver reacting-Foam of OpenFOAM are evaluated in the hydrogen transport calculation and the results are compared with those of the program of commercial license GASFLOW to see if is viable the use of the open source code in the case of the hydrogen transport in the primary containment of a BWR. Of the obtained results so much quantitative as qualitative some differences were identified between both codes, the differences (with a percentage of maximum error of 4%) in the quantitative results are small and they are considered acceptable for this analysis type, also, these differences are attributed mainly to the used transport models, considering that OpenFOAM uses a homogeneous model and GASFLOW uses a heterogeneous model. (Author)

  19. Characterization of corrosion layers on irradiated and non-irradiated surfaces in BWR conditions

    Energy Technology Data Exchange (ETDEWEB)

    Kysela, J.; Balek, V.; Zmitko, M.; Brozova, A.; Burda, J. [Nuclear Research Inst., Rez (Czech Republic); Hoffmann, H.; Ruehle, W. [VGB Essen (Germany); Bezdicka, P. [Institute of Inorganic Chemistry, ASCR, Rez (Czech Republic)

    2002-07-01

    Stress corrosion cracking of low-alloyed steel 22NiMoCr37 is evaluated with the goal to determine crack growth rate in irradiated steel under conditions simulating closely conditions of BWR RPV under operation. For the experiment, in pile BWR experimental loop has been built at Nuclear Research Institute, Rez. During the experiment, specimens are loaded by cyclic and constant load. Crack growth is monitored by means of potential drop measurement and COD. Corrosion layers formed on specimens in reactor water loop exposed to BWR primary water chemistry and radiation were studied. Two sets of specimens were placed in loop channels. One set of specimens was situated in reactor conditions and the second set out of reactor, other parameters like water chemistry (e.g. concentration of hydrogen, oxygen and conductivity), temperature and flow rate were identical. By means of this an effect of radiation could be studied. The differences in chemical composition, structure and microstructure of corrosion products were characterized by SEM and X-ray powder diffractometry. The differences in microstructure of corrosion layer formed under different conditions were observed. (authors)

  20. Effect of thermal-hydraulic feedback on the BWR rod drop accident

    International Nuclear Information System (INIS)

    An important design-basis accident for boiling water reactors (BWR's) is the rod drop accident (RDA). This accident is defined to be a rapid reactor transient caused by an accidental drop (out of the core) of the highest-worth control rod at various conditions ranging from cold start-up to about 10% of rated power. For most BWR designs the highest worth rod is normally situated at the center of the core. Despite the fact that the chance of a RDA in extremely unlikely, the consequence of the RDA is of concern because of the potential for damage to fuel rods. Neglecting moderator feedback during the RDA is a poor assumption because energy is deposited in the fuel over a 3 to 4 second time period and hence there is time for heat to be conducted to the coolant. This may tend to ameliorate the accident considerably. Evaluation of the thermal-hydraulic feedback effect on the RDS in a BWR has been scarce in the literature. The object of this paper is to demonstrate the beneficial effect of thermal-hydraulic feedback in the RDA

  1. Aging and service wear of control rod drive mechanisms for BWR nuclear plants

    International Nuclear Information System (INIS)

    This Phase I Nuclear Plant Aging Research (NPAR) study examines the aging phenomena associated with BWR control rod drive mechanisms (CRDMs) and assesses the merits of various methods of ''managing'' this aging. Information for this study was acquired from (1) the results of a special CRDM aging questionnaire distributed to each US BWR utility, (2) a first-of-its-kind workshop held to discuss CRDM aging and maintenance concerns, (3) an analysis of the Nuclear Plant Reliability Data System (NPRDS) failure cases attributed to the control rod drive (CRD) system, and (4) personal information exchange with nuclear industry CRDM maintenance experts. Nearly 23% of the NPRDS CRD system component failure reports were attributed to the CRDM. The CRDM components most often requiring replacement due to normal wear and aging are the Graphiter seals. The predominant causes of aging for these seals are mechanical wear and thermally induced embrittlement More than 59% of the NPRDS CRD system failure reports were attributed to components that comprise the hydraulic control unit (HCU). The predominant HCU components experiencing the effects of service wear and aging are valve seals, discs, seats, stems, packing, and diaphragms. Since CRDM changeout and rebuilding is one of the highest dose, most physically challenging, and complicated maintenance activities routinely accomplished by BWR utilities, this report also highlights recent innovations in CRDM handling equipment and rebuilding tools that have resulted in significant dose reductions to the maintenance crews using them

  2. Damage by radiation in structural materials of BWR reactor vessels; Dano por radiacion en materiales estructurales de vasijas de reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Robles, E.; Balcazar, M.; Alpizar, A.M.; Calderon, B.E. [Departamento de Sintesis y Caracterizacion de Materiales, Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2002-07-01

    The structural materials which are manufactured the pressure vessels of the BWR reactors undergo degradation in their mechanical properties mainly due to the damage produced by the fast neutrons (E> 1 MeV) coming from the reactor core. The mechanisms of neutron damage in this type of materials are experimentally studied, through the irradiation of vessel steel in experimental reactors for a quickly ageing. Alternately the neutron damage through steel irradiation with heavy ions is simulated. In this work the first results of the damage induced by irradiation of a similar steel to the vessel of a BWR reactor are shown. The irradiation was performed with fast neutrons (E> 1 MeV, fluence of 1.45 x 10{sup 18} n/cm{sup 2}) in the TRIGA Mark III Salazar reactor and separately with Ni{sup +3} ions in a Tandetrom accelerator (E= 4.8 MeV and an ion flux rank of 0.1 to 53 ions/A{sup 2}). (Author)

  3. Logical model for the control of a BWR turbine;Modelo logico para el control de una turbina de un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Vargas O, Y. [Universidad del Valle de Mexico, Campus Toluca, Av. Las Palmas No. 136, Col. San Jorge Pueblo Nuevo, 52140 Metepec, Estado de Mexico (Mexico); Amador G, R.; Ortiz V, J.; Castillo D, R., E-mail: yonaeton@hotmail.co [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2009-07-01

    In this work a design of a logical model is presented for the turbine control of a nuclear power plant with a BWR like energy source. The model is sought to implement later on inside the thermal hydraulics code of better estimate RELAP/SCDAPSIM. The logical model is developed for the control and protection of the turbine, and the consequent protection to the BWR, considering that the turbine control will be been able to use for one or several turbines in series. The quality of the present design of the logical model of the turbine control is that it considers the most important parameters in the operation of a turbine, besides that they have incorporated to the logical model the secondary parameters that will be activated originally as true when the turbine model is substituted by a detailed model. The development of the logical model of a turbine will be of utility in the short and medium term to carry out analysis on the turbine operation with different operation conditions, of vapor extraction, specific steps of the turbine to feed other equipment s, in addition to analyze the separate and the integrated effect. (Author)

  4. 75 FR 21034 - Notice of Availability of Record of Decision for the Agua Fria National Monument and Bradshaw...

    Science.gov (United States)

    2010-04-22

    ... Bureau of Land Management Notice of Availability of Record of Decision for the Agua Fria National... Agua Fria National Monument and Bradshaw-Harquahala Planning Area, located in central Arizona. The... occupied or used portions of the planning area during prehistoric or historic times. The Agua Fria...

  5. Calidad de las aguas superficiales en la Cuenca del Ebro. Tendencias de salinidad, nitrato y fosfato

    OpenAIRE

    Quílez Sáez de Viteri, Dolores

    2011-01-01

    Objetivo General: Caracterización de la calidad de las aguas superficiales de la Cuenca del Ebro y de sus tendencias. Redes de Control de Calidad de Aguas de CHE: - 497 estaciones de control - Datos instantáneos con frecuencias variables - Se han seleccionado 31 estaciones - Relevancia dentro de la Cuenca del Ebro - Predominio del regadío - Disponibilidad de datos

  6. Entrainment and deposition modeling of liquid films with applications for BWR fuel rod dryout

    Science.gov (United States)

    Ratnayake, Ruwan Kumara

    While best estimate computer codes provide the licensing basis for nuclear power facilities, they also serve as analytical tools in overall plant and component design procedures. An ideal best estimate code would comprise of universally applicable mechanistic models for all its components. However, due to the limited understanding in these specific areas, many of the models and correlations used in these codes reflect high levels of empiricism. As a result, the use of such models is strictly limited to the range of parameters within which the experiments have been conducted. Disagreements between best estimate code predictions and experimental results are often explained by the mechanistic inadequacies of embedded models. Significant mismatches between calculated and experimental critical power values are common observations in the analyses of Boiling Water Reactors (BWR). Based on experimental observations and calculations, these mismatches are attributed to the additional entrainment and deposition caused by spacer grids in BWR fuel assemblies. In COBRA-TF (Coolant Boiling in Rod Arrays-Two Fluid); a state of the art industrial best estimate code, these disagreements are hypothesized to occur due the absence of an appropriate spacer grid model. In this thesis, development of a suitably detailed spacer grid model and integrating it to COBRA-TF is documented. The new spacer grid model is highly mechanistic so that the applicability of it is not seriously affected by geometric variations in different spacer grid designs. COBRA-TF (original version) simulations performed on single tube tests and BWR rod bundles with spacer grids showed that single tube predictions were more accurate than those of the rod bundles. This observation is understood to arise from the non-availability of a suitable spacer grid model in COBRA-TF. Air water entrainment experiments were conducted in a test section simulating two adjacent BWR sub channels to visualize the flow behavior at

  7. CFD predictions of standby liquid control system mixing in lower plenum of a BWR

    Energy Technology Data Exchange (ETDEWEB)

    Boyd, Christopher, E-mail: christopher.boyd@nrc.gov; Skarda, Raymond, E-mail: Raymond.skarda@nrc.gov

    2014-11-15

    Highlights: • Computational fluid dynamics analysis of BWR lower plenum. • Mixing and stratification of the standby liquid control system injection. • Scoping study highlights the expected flow paths and limitations of experiments. - Abstract: During an anticipated transient without scram (ATWS) scenario in certain boiling water reactor (BWR) systems, a standby liquid control system (SLCS) is used to inject a sodium pentaborate solution into the reactor system in order to quickly shut down (scram) the reactor without the use of the control rods. Some BWR designs utilize a SLCS that injects through a set of nozzles on a vertical pipe in the peripheral region of the lower plenum of the reactor vessel. During the scenario, system water levels are reduced and natural circulation flow rates down through the jet pump nozzles and up into the core are a small fraction of the rated system flow. It is during this period that the SLCS flows are considered. This work outlines some initial scoping studies completed by the staff at the Nuclear Regulatory Commission (NRC). An attempt at benchmarking the computational fluid dynamics (CFD) approach using a set of available test data from a small facility is outlined. Due to our lack of information related to specific details of the facility geometry along with the limited data available from the test, the benchmark exercise produced only a qualitative basis for selecting turbulence models and mesh density. A CFD model simulating a full-scale reactor system is developed for the lower plenum of a representative BWR/4 design and SLCS flows and mixing are studied under a range of flow conditions. The full-scale BWR simulation builds upon the lessons learned from the benchmark exercise. One challenge for this work is the large size of the domain and the relatively small size of the geometric details such as flow passages and gaps. The geometry is simplified to make meshing feasible by eliminating some of the small features. The

  8. LOCALIZACIÓN Y AFECTACIÓN DE COSTES MEDIOAMBIENTALES Y NO MEDIOAMBIENTALES EN LAS EMPRESAS DE AGUAS: EL COSTE DEL AGUA DESALADA

    Directory of Open Access Journals (Sweden)

    Jerónimo Pérez Alemán

    2005-12-01

    Full Text Available La Directiva 2000/60/EC del Parlamento Europeo y del Consejo establece un marco de acción comunitaria en el ámbito de la política de aguas. Esta norma indica, en su artículo 9, que los miembros de los Estados tendrán en cuenta el principio de recuperación de los costes de los servicios de aguas, incluidos los medioambientales. Así pues, las empresas de tratamiento y abastecimiento urbano de aguas tienen la necesidad de generar información sobre los costes en general, y sobre los costes (y otras magnitudes medioambientales en particular. En el presente trabajo centramos nuestra atención en el coste de uno de los outputs de tales empresas: el agua desalada.

  9. Acuaporinas: proteínas mediadoras del transporte de agua.

    Directory of Open Access Journals (Sweden)

    Julio César Sánchez

    2009-11-01

    Full Text Available Introducción. Todos los organismos vivos están compuestos en su mayoría por agua, siendo ésta fundamental para la homeostasis celular a todo nivel. Por esta razón su transporte a través de las membranas biológicas ha sido siempre un campo de gran interés en la fisiología. La investigación acerca de este tópico se ha incrementado notablemente en los últimos años a partir del descubrimiento de las acuaporinas, las cuales han permitido comprender mejor los mecanismos que la célula utiliza para el control de los flujos de agua a través de la membrana y por ende, la regulación de su osmolaridad interna. Tema general. Hasta el momento se han descrito 11 subtipos de acuaporinas (AQP0-10, las cuales comparten similitudes estructurales y se han relacionado con una gran diversidad de enfermedades en diversos sistemas, desde cataratas hasta diabetes insípida. Objetivo. Se presenta una visión del estado actual del conocimiento acerca de estas importantes proteínas y su relación con diversos procesos fisiológicos y patológicos. Conclusiones. Las acuaporinas son proteínas mediadoras del transporte de agua y las alteraciones en su funcionamiento pueden conducir a una gran diversidad de enfermedades, por lo cual deben ser un objeto prioritario de investigación en el futuro próximo para ayudar a comprender mejor su fisiopatología.

  10. La fundamentalidad del derecho al agua en Colombia

    Directory of Open Access Journals (Sweden)

    Mies Sutorius

    2015-12-01

    Full Text Available El agua es un recurso natural finito de vital importancia para el ser humano, lo que explica que con el paso del tiempo se busque con mayor fuerza su protección, no solo en el ámbito internacional sino también en el orden jurídico interno. De ahí el interés en realizar una revisión normativa y especialmente jurisprudencial que permita evidenciar la evolución del derecho al agua, los matices y las diversas formas de protección del mismo, profundizando en su dimensión personal. La Constitución Política colombiana omite enunciar el derecho al agua como derecho individual, razón por la cual se procede a estudiar la jurisprudencia constitucional, seleccionándose algunas sentencias en donde existen sujetos de especial protección, en tanto al reconocerse a estos la vulneración y garantía de derechos se prevé la protección de los derechos del resto de la población; así como algunos casos en donde existen condiciones particulares, a partir de la suspensión del servicio por falta de pago a la empresa encargada del suministro, conexión fraudulenta y reconexión ilegal; para concluir que se han presentado dos tendencias en el amparo de este derecho, que ha pasado de ser protegido por vía de la “teoría de la conexidad” a ser catalogado como fundamental con una tutela restringida a la cantidad mínima necesaria para sobrevivir.

  11. Estudio del mecanismo de falla de terraplenes debido a la infiltración de aguas lluvias mediante el monitoreo de presiones de poros y contenidos de agua

    Directory of Open Access Journals (Sweden)

    EDWIN GARCÍA

    2007-01-01

    Full Text Available El presente artículo muestra experimentos realizados utilizando modelos a escala para estudiar el proceso de infiltración en terraplenes sometidos a aguas lluvias. Varios modelos a escala fueron construidos usando un suelo arenoso con alto contenido de finos; para aplicar la lluvia artificial y observar el proceso de infiltración del agua se utilizó un tubo de irrigación. Para monitorear los cambios en succión ocasionados por los ciclos de humedecimiento y secado se instalaron dentro del suelo varios sensores de presión de poros, contenido de agua y de desplazamiento en diferentes puntos. El cambio de la presión de poros en el tiempo, el contenido de agua y las relaciones entre las mediciones de presión de poros y desplazamientos del suelo son presentados. Este estudio muestra que el movimiento del suelo en un talud está directamente relacionado con el contenido de agua del suelo y las presiones de poros existentes en él, sugiriendo que por medio del monitoreo de estos dos parámetros es posible predecir fallas locales inducidas por infiltración de aguas lluvias en los taludes.

  12. Uso de plantas acuáticas en el tratamiento de agua y aguas residuales en la Universidad de Matanzas "Camilo Cienfuegos"

    Directory of Open Access Journals (Sweden)

    Damarys Santana Diaz

    2011-05-01

    Full Text Available En el presente trabajo  se analiza el uso de las plantas acuáticas para purificar el agua que se utiliza con fines ornamentales en el Parque de La Juventud de la Universidad de Matanzas "Camilo Cienfuegos", así como para el tratamiento de aguas residuales de dicha instalación. El estudio se realiza a escala de laboratorio y en ambos casos la efectividad del tratamiento se valora a partir de la determinación de parámetros como: demanda química de oxígeno, conductividad, pH, dureza total, dureza de calcio, dureza de magnesio, sólidos totales, fijos y volátiles y coliformes totales y fecales. Se comprobó que las plantas acuáticas pueden disminuir los valores de parámetros indicadores de la calidad del agua a niveles que permitan disminuir la frecuencia con que se cambia el agua de los espejos. Los resultados evidencian que el uso de la planta acuática Nymphaea ampla constituye una alternativa para tratar las aguas y mejorar su calidad con un efecto económico considerable por concepto de ahorro de agua potable.

  13. Gente de agua: Comunidades negras en el Bajo Atrato

    Directory of Open Access Journals (Sweden)

    Daniel Ruíz Serna

    2010-05-01

    Full Text Available “Gente de agua” es un conjunto de imágenes sobre el universo social de las comunidades negras del Bajo Atrato chocoano. Ilustra de forma sensible el sistema de texturas de la vida negra en el río. Desde las pieles brillantes bajo el sol, pasando por todos los colores del agua, hasta la ignominiosa condena del racismo y la exclusión son objeto del lente del etnógrafo que ha encontrado en las imágenes una opción para hacer antropología.

  14. Matemáticas para la industria del agua

    OpenAIRE

    Izquierdo Sebastián, Joaquín; Pérez, Rafael; Vicente S. Fuertes; Iglesias, Pedro L.; López, Amparo

    2004-01-01

    En el campo del agua existe una enorme diversidad de actividades e intereses y, por tanto, de áreas de trabajo. Los problemas que se plantean en estas áreas son auténticos problemas de ingeniería y, como consecuencia, las ayudas que ciertas técnicas de Matemática Aplicada pueden prestar son realmente importantes. Por un lado, es preciso disponer de herramientas de análisis que permitan realizar simulaciones fiables de los distintos modelos que se plantean analizando diversas configuraciones, ...

  15. Hormigón en aguas y terrenos agresivos

    Directory of Open Access Journals (Sweden)

    García de Paredes y Gaibrois, Pablo

    1962-09-01

    Full Text Available Not availableEl Dr. Ingeniero H. J. Wierig, del Laboratorio de la Industria del Cemento de Westfalia, ha publicado, en la revista «Bau und Bauindustrie» (núm. 6 de 1961, un interesante artículo acerca de la Preparación del hormigón en aguas y suelos agresivos, de~ cual entresacamos las siguientes notas con la complacencia que supone encontrar totalmente coincidentes, las opiniones del Dr. Wierig con el contenido de las «Recomendaciones» publicadas en la Instrucción sobre hormigón armado H. A. 61 de este Instituto.

  16. La electrolisis salina para el tratamiento de aguas de lastre

    OpenAIRE

    Mesa Salvany, Daniel

    2014-01-01

    El objetivo principal del proyecto, es el desarrollo de equipos electrolíticos para el tratamiento de aguas de lastre, acorde con los requerimientos de la normativa, y los del sector. Para ello, los objetivos específicos, son:  Definición de los requerimientos de la tecnología, teniendo en consideración todas las normativas navales que afecten al proyecto.  Definición de los requerimientos de la tecnología, teniendo en consideración todas las especificaciones técnicas y comerciales qu...

  17. Desplazamiento de aceite por agua en medios porosos fracturados vugulares

    Directory of Open Access Journals (Sweden)

    Juana Cruz

    2001-01-01

    Full Text Available Se presentan experimentos llevados a cabo con una celda bidimensional de acrílico, que presenta un medio poroso fracturado vugular. Esta celda tiene seis vúgulos conectados con fracturas, un pozo de inyección y uno de producción. Los primeros resultados indican que el modelo explica de manera confiable los mecanismos que están presentes en los procesos de inyección de agua en yacimientos naturalmente fracturados, en presencia de vúgulos.

  18. Thorium mobilization in groundwaters from Aguas da Prata, Sao Paulo state; Mobilizacao de torio em aguas subterraneas de Aguas da Prata, estado de Sao Paulo

    Energy Technology Data Exchange (ETDEWEB)

    Tonetto, Erica Martini [Universidade Estadual Paulista (UNESP), Rio Claro, SP (Brazil). Area de Concentracao Geociencias e Meio Ambiente. Pos-Graduacao em Geociencias]. E-mail: etonetto@rc.unesp.br; Bonotto, Daniel Marcos [Universidade Estadual Paulista (UNESP), Rio Claro, SP (Brazil). Dept. de Petrologia e Metalogenia]. E-mail: dbonotto@rc.unesp.br

    2002-09-15

    The paper describes and discusses results of the determination, by alpha spectrometry, of the natural thorium isotopes in groundwaters associated with different rock types in Aguas da Prata spa, state of Sao Paulo. The dissolved Thorium is relatively low (0.003 to 1.72 mg.L{sup -1} for {sup 232}Th), while the {sup 22}'8Th/{sup 232}Th isotopic ratios for dissolved thorium were higher than unity (1.8 to 34). The thorium concentration in suspended solids of these waters ranged between 183 up and 3445 mug.g{sup -1} and indicates that significant thorium transport occurs under this condition. The obtained results allowed to calculate the factor for preferential mobilization of thorium in particulate matter relative to the liquid phase, an important parameter for understanding the geochemical behaviour of this element in hydrosphere. (author)

  19. CALIDAD BIOLÓGICA DE AGUAS RESIDUALES UTILIZADAS PARA RIEGO DE CULTIVOS FORRAJEROS EN TULANCINGO, HIDALGO, MÉXICO

    OpenAIRE

    Evangelina E. Quiñones-Aguilar; David Cristóbal-Acevedo; Elizabeth Hernández-Acosta; Juan E. Rubiños-Panta

    2014-01-01

    El uso de aguas residuales para el riego de cultivos forrajeros es una práctica que aumenta día a día en áreas donde el agua, para este fin, es escasa. Sin embargo, los usuarios, al estar en contacto directo con las aguas residuales, padecen enfermedades gastrointestinales a causa de coliformes y parásitos (helmintos). En el presente estudio se evaluaron coliformes fecales (en aguas residuales, suelo y plantas) y helmintos (en aguas residuales) en el módulo II del Distrito de Riego 028, Tulan...

  20. Planificación y gestión del agua subterránea: aspectos generales y retos

    OpenAIRE

    Custodio Gimena, Emilio

    2011-01-01

    El agua subterránea, además de ser esencial para el medio ambiente, es un importante recurso y reserva de agua para satisfacer las necesidades humanas. Por ello es susceptible de extracción intensiva, cosa que ya sucede en numerosos acuíferos a nivel mundial. La extracción de agua subterránea modifica el ciclo natural del agua, lo que puede originar importantes cambios en la Naturaleza y alterar las relaciones con las otras fases del ciclo hidrológico. La explotación del agua subterránea p...

  1. Recursos de agua no convencionales en España: estado de la cuestión, 2010

    OpenAIRE

    Olcina Cantos, Jorge; Moltó Mantero, Enrique

    2010-01-01

    Los recursos de agua no convencionales han experimentado un notable desarrollo durante la primera década del presente siglo. El cumplimiento de la Directiva 91/271 de depuración de aguas residuales urbanas y la puesta en marcha del programa AGUA han resultado decisivos para el impulso de la depuración y desalación de aguas en España. Por el contrario, la reutilización de aguas residuales depuradas, aunque cuenta con actuaciones significativas (agricultura, usos recreativos), sigue siendo una ...

  2. BWR [boiling water reactor] core criticality versus water level during an ATWS [anticipated transient without scram] event

    International Nuclear Information System (INIS)

    The BWR [boiling water reactor] emergency procedures guidelines recommend management of core water level to reduce the power generated during an anticipated transient without scram (ATWS) event. BWR power level variation has traditionally been calculated in the system codes using a 1-D [one-dimensional] 2-group neutron kinetics model to determine criticality. This methodology used also for calculating criticality of the partially covered BWR cores has, however, never been validated against data. In this paper, the power level versus water level issues in an ATWS severe accident are introduced and the accuracy of the traditional methodology is investigated by comparing with measured data. It is found that the 1-D 2-group treatment is not adequate for accurate predictions of criticality and therefore the system power level for the water level variations that may be encountered in a prototypical ATWS severe accident. It is believed that the current predictions for power level may be too high

  3. El cultivo de alfalfa utilizando agua de perforación, agua residual urbana y precipitaciones The cultivation of alfalfa using artesian well water, urban wastewater and rainfall

    Directory of Open Access Journals (Sweden)

    José O. Plevich

    2012-12-01

    Full Text Available El objetivo de este trabajo fue analizar la producción de biomasa aérea, la eficiencia del uso de agua y el valor nutritivo de alfalfa cultivada aplicando riego con agua residual urbana, agua de perforación y un testigo (precipitaciones, en el Campus de la Universidad Nacional de Rio Cuarto (Córdoba-Argentina. Los tratamientos de riego tuvieron un efecto positivo sobre la producción de biomasa aérea obteniéndose un 24% más de producción de biomasa que en la situación de secano (precipitaciones. Entre los tratamientos con riego también se manifestaron diferencias estadísticamente significativas. La alfalfa regada con aguas residuales urbana supero en un 19% a la cultivada con agua de perforación. La eficiencia del uso del agua por parte del cultivo se incrementó cuando el riego se realizó con aguas residuales urbanas. Además, se determinó que la alfalfa regada con agua residual, supera los valores nutritivos del cultivo que crece en condiciones sin riego; encontrándose 39% más de proteínas, 14% más de digestibilidad e igual porcentaje de energía metabólica. Se puede concluir que el agua residual urbana representa otra posible fuente de agua, factible de ingresar al suelo y estar a disposición para el cultivo de alfalfa.The objective of this study was to analyse the production of alfalfa biomass, the efficiency of water use and the nutritional value of forage, inside an irrigation structure of an experimental facility that uses treated urban wastewater, artesian well water and rainfall, at the campus of the Universidad National de Rio Cuarto (Córdoba-Argentina. The irrigation treatment had a positive effect on the production of biomass of alfalfa. On an average 24% increase in production was observed when compared to dry-land farming. Regarding the quality of the irrigation water, statistical differences in production were observed, the irrigation with urban wastewater produced 19% more than that of well water. The

  4. El agua en Segobriga (Saelices, Hispania Citerior: Las fistulae plumbeae

    Directory of Open Access Journals (Sweden)

    Cebrián, Rosario

    2014-12-01

    Full Text Available In the present article the lead pipes found in the archaeological site of Segobriga and in its surroundings are presented. Some of these fistulae are related to the siphon aqueduct that brought drinking water from Fuente la Mar in Saelices, while others correspond to the internal water supply in the city. Both epigraphic references containing the abbreviated name of the municipality, r(es p(ublica S(egobrigensis vel Segobrigensium, identified on a fistula and in a lead cover, show the public property of the Segobriga hydraulic network.En este artículo presentamos las tuberías de plomo halladas en el yacimiento arqueológico de Segobriga y su entorno. Algunas de estas fistulae están relacionadas con el sifón del acueducto que condujo el agua potable desde la Fuente de la Mar en Saelices, mientras que otras corresponden a la red de distribución del agua en el interior de la ciudad. Las dos menciones epigráficas con el nombre abreviado del municipio, r(es p(ublica S(egobrigensis vel Segobrigensium, documentadas en una fistula y en la tapa de un registro ponen de manifiesto la propiedad pública del sistema hidráulico de Segobriga.

  5. EFECTOS REDISTRIBUTIVOS DE LAS TARIFAS DE AGUA POTABLE

    Directory of Open Access Journals (Sweden)

    VÉLEZ GOMEZ LUIS DIEGO

    2010-05-01

    Full Text Available Aunque para Colombia la situación no es tan dramática, se avizora un problema de cobertura y escasez de agua potable para los niveles más desprotegidos de la población, en razón de su incapacidad de pago. La consecuencia inmediata es una acentuación de los índices de pobreza y de su manifestación más clara: el hambre. Este trabajo pretende mostrar que los niveles de pobreza son muy sensibles al precio de los servicios públicos domiciliarios, entre ellos, del agua, y atribuye a las fallas de inclusión y exclusión de los subsidios parte del grueso número de personas que hoy están por debajo de la línea de pobreza, aunque ésta no sea la única causa. Dada, entonces, la prominencia de las empresas de servicios públicos en la economía, los gobiernos tienen la obligación de resolver parte del difícil problema de equidad a través de las tarifas, sin dejar de garantizar la sostenibilidad económica de los proveedores del recurso.

  6. Regulation of the alpha-glucuronidase-encoding gene ( aguA) from Aspergillus niger.

    Science.gov (United States)

    de Vries, R P; van de Vondervoort, P J I; Hendriks, L; van de Belt, M; Visser, J

    2002-09-01

    The alpha-glucuronidase gene aguA from Aspergillus niger was cloned and characterised. Analysis of the promoter region of aguA revealed the presence of four putative binding sites for the major carbon catabolite repressor protein CREA and one putative binding site for the transcriptional activator XLNR. In addition, a sequence motif was detected which differed only in the last nucleotide from the XLNR consensus site. A construct in which part of the aguA coding region was deleted still resulted in production of a stable mRNA upon transformation of A. niger. The putative XLNR binding sites and two of the putative CREA binding sites were mutated individually in this construct and the effects on expression were examined in A. niger transformants. Northern analysis of the transformants revealed that the consensus XLNR site is not actually functional in the aguA promoter, whereas the sequence that diverges from the consensus at a single position is functional. This indicates that XLNR is also able to bind to the sequence GGCTAG, and the XLNR binding site consensus should therefore be changed to GGCTAR. Both CREA sites are functional, indicating that CREA has a strong influence on aguA expression. A detailed expression analysis of aguA in four genetic backgrounds revealed a second regulatory system involved in activation of aguA gene expression. This system responds to the presence of glucuronic and galacturonic acids, and is not dependent on XLNR.

  7. Obtention control bars patterns for a BWR using Tabo search; Obtencion de patrones de barras de control para un BWR usando busqueda Tabu

    Energy Technology Data Exchange (ETDEWEB)

    Castillo, A.; Ortiz, J.J.; Alonso, G. [Instituto Nacional de Investigaciones Nucleares, Km. 36.5 Carretera Mexico-Toluca, Ocoyoacac, Estado de Mexico 52045 (Mexico); Morales, L.B. [UNAM, IIMAS, Ciudad Universitaria, D. F. 04510 (Mexico); Valle, E. del [IPN, ESFM, Unidad Profesional ' Adolfo Lopez Mateos' , Col. Lindavista 07738, D. F. (Mexico)]. e-mail: jacm@nuclear.inin.mx

    2004-07-01

    The obtained results when implementing the technique of tabu search, for to optimize patterns of control bars in a BWR type reactor, using the CM-PRESTO code are presented. The patterns of control bars were obtained for the designs of fuel reloads obtained in a previous work, using the same technique. The obtained results correspond to a cycle of 18 months using 112 fresh fuels enriched at the 3.53 of U-235. The used technique of tabu search, prohibits recently visited movements, in the position that correspond to the axial positions of the control bars, additionally the tiempo{sub t}abu matrix is used for to manage a size of variable tabu list and the objective function is punished with the frequency of the forbidden movements. The obtained patterns of control bars improve the longitude of the cycle with regard to the reference values and they complete the restrictions of safety. (Author)

  8. Optimization of fuel reloads for a BWR using the ant colony system; Optimizacion de recargas de combustible para un BWR usando el sistema de colonia de hormigas

    Energy Technology Data Exchange (ETDEWEB)

    Esquivel E, J. [Universidad Autonoma del Estado de Mexico, Facultad de Ingenieria, Cerro de Coatepec s/n, Ciudad Universitaria, 50110 Toluca, Estado de Mexico (Mexico); Ortiz S, J. J. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)], e-mail: jaime.es.jaime@gmail.com

    2009-10-15

    In this work some results obtained during the development of optimization systems are presented, which are employees for the fuel reload design in a BWR. The systems use the ant colony optimization technique. As first instance, a system is developed that was adapted at travel salesman problem applied for the 32 state capitals of Mexican Republic. The purpose of this implementation is that a similarity exists with the design of fuel reload, since the two problems are of combinatorial optimization with decision variables that have similarity between both. The system was coupled to simulator SIMULATE-3, obtaining good results when being applied to an operation cycle in equilibrium for reactors of nuclear power plant of Laguna Verde. (Author)

  9. Study of transient rod extraction failure without RBM in a BWR; Estudio del transitorio error de extraccion de barra sin RBM en un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Vallejo Q, J. A.; Martin del Campo M, C.; Fuentes M, L.; Francois L, J. L., E-mail: amhed_jvq@hotmail.com [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico)

    2015-09-15

    The study and analysis of the operational transients are important for predicting the behavior of a system to short-term events and the impact that would cause this transient. For the nuclear industry these studies are indispensable due to economic, environmental and social impacts that could cause an accident during the operation of a nuclear reactor. In this paper the preparation, simulation and analysis results of the transient rod extraction failure in which not taken into operation the RBM is presented. The study was conducted for a BWR of 2027 MWt, in an intermediate cycle of its useful life and using the computer code Simulate-3K a scenario of anomalies was created in the core reactivity which gave a coherent prediction to the type of presented event. (Author)

  10. Study of transient turbine shot without bypass in a BWR; Estudio del transitorio disparo de turbina sin bypass en un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Vallejo Q, J. A.; Martin del Campo M, C.; Fuentes M, L.; Francois L, J. L., E-mail: amhed_jvq@hotmail.com [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico)

    2015-09-15

    The study and analysis of operational transients are important for predicting the behavior of a system to short-terms events and the impact that would cause this transition. For the nuclear industry these studies are indispensable due to economic, environmental and social impacts that could result in an accident during the operation of a nuclear reactor. In this paper the preparation, simulation and analysis of results of a turbine shot transient, which is not taken into operation the bypass is presented. The study is realized for a BWR of 2027 MWt, to an intermediate cycle life and using the computer code Simulate-3K a depressurization stage of the vessel is created which shows the response of other security systems and gives a coherent prediction to the event presented type. (Author)

  11. Thermal hydraulics characterization of the core and the reactor vessel type BWR; Caracterizacion termohidraulica del nucleo y de la vasija de un reactor tipo BWR

    Energy Technology Data Exchange (ETDEWEB)

    Zapata Y, M.; Lopez H, L.E. [CFE, Carretera Cardel-Nautla Km. 42.5, Municipio Alto Lucero, Veracruz (Mexico)]. e-mail: marxlenin.zapata@cfe.gob.mx

    2008-07-01

    The thermal hydraulics design of a reactor type BWR 5 as the employees in the nuclear power plant of Laguna Verde involves the coupling of at least six control volumes: Pumps jet region, Stratification region, Core region, Vapor dryer region, Humidity separator region and Reactor region. Except by the regions of the core and reactor, these control volumes only are used for design considerations and their importance as operative data source is limited. It is for that is fundamental to complement the thermal hydraulics relations to obtain major data that allow to determine the efficiency of internal components, such as pumps jet, humidity separator and vapor dryer. Like example of the previous thing, calculations are realized on the humidity of the principal vapor during starting, comparing it with the values at the moment incorporated in the data banks of the computers of process of both units. (Author)

  12. Analysis of assemblies exchange in the core of a reactor BWR; Analisis del intercambio de ensambles en el nucleo de un reactor BWR

    Energy Technology Data Exchange (ETDEWEB)

    Kauil U, J. S. [Universidad Autonoma de Yucatan, Facultad de Ingenieria, Av. Industrias no contaminantes por Anillo Periferico Norte s/n, Apdo. Postal 150 Cordemex, Merida, Yucatan (Mexico); Fuentes M, L.; Castillo M, J. A.; Ortiz S, J. J.; Perusquia del Cueto, R., E-mail: san_dino@hotmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2012-10-15

    The performance of the core of a boiling water reactor (BWR) was evaluated when two assemblies are exchanged during the fuel reload in erroneous way. All with the purpose of analyzing the value of the neutrons effective multiplication factor and the thermal limits for an exchange of assemblies. In their realization the mentioned study was based in a transition cycle of the Unit 1 of the nuclear power plant of Laguna Verde. The obtained results demonstrate that when carrying out an exchange between two fuel assemblies in erroneous way, with regard to the original reload, the changes in the neutrons effective multiplication factor do not present a serious problem, unless the exchange has been carried out among a very burnt assembly with one fresh, where this last is taken to the periphery. (Author)

  13. Actitudes y comportamiento para el uso sostenible del agua en pobladores de Huancayo

    Directory of Open Access Journals (Sweden)

    Luis Yarlequé Chocas

    2013-06-01

    Full Text Available Objetivos: Establecer si el Programa de Gestión Sostenible del Agua (PROGESA mejora el comportamiento y las actitudes de estudiantes del nivel inicial y padres de familia para el uso sostenible del agua en seis instituciones educativas de Huancayo. Métodos: Se empleó el diseño cuasi experimental de grupos no equivalentes con pre y posprueba. El tamaño muestral fue de 160 estudiantes y 160 padres. Los instrumentos utilizados fueron cuestionarios estructurados, listas de cotejo y guías de entrevista para identificar las principales conductas y mecanismos de pérdida del agua y de actitudes hacia su cuidado. Resultados: El 98% de la población infantil tiene actitudes de rechazo hacia el uso sostenible del agua sin la influencia de PROGESA ni del área de Ciencia y Ambiente; el 79,7% de los adultos acepta el uso sostenible del agua. Los principales mecanismos de pérdida de agua en hogares e instituciones educativas de Huancayo son los inodoros y caños malogrados y mal cerrados. Conclusiones: PROGESA sí hace posible el desarrollo de actitudes y el comportamiento hacia el uso sostenible del agua en los niños y a través de ellos en sus padres; el área de Ciencia y Ambiente tiene también un efecto positivo al respecto, pero menor que el de PROGESA; los adultos saben qué se debería hacer, pero no siempre lo hacen; los inodoros y caños malogrados son las principales fuentes de pérdida del agua; en las instituciones y en los hogares no se reusa ni cosecha agua.

  14. El abastecimiento de agua en las ciudades del Mediterráneo

    Directory of Open Access Journals (Sweden)

    Pulido Bosch, Antonio

    1999-10-01

    Full Text Available Not available.En las ciudades costeras, como en las no costeras, una buena parte del agua captada se pierde en las redes de distribución; además, el usuario no es siempre consciente de la necesidad de ahorrar al máximo este recurso. Hay que tener en cuenta igualmente que el agua residual, una vez depurada, puede constituir un buen recurso que permite satisfacer parte de la demanda y a la vez reducir los problemas planteados por la eliminación de las aguas usadas directamente en el mar. Las soluciones a los problemas de la escasez de agua deben pasar por el ahorro de agua, la reducción de las pérdidas en las redes de distribución, la reutilización y, a veces, la importación de agua de lugares excedentarios, sin olvidar la desalación de las aguas saladas o salobres. El desarrollo sostenible exige una planificación partiendo de la demanda máxima admisible, compatible con el respeto a los equilibrios ambientales; esto puede exigir la limitación del crecimiento de las ciudades, lo que no es siempre aceptado. Por último, se comentan dos ejemplos, uno representativo de una ciudad donde no existe gran competencia por el agua entre la demanda agrícola y la demanda urbana (Almería; y el otro relativo a una ciudad donde el turismo de verano aumenta casi diez veces la población, con una agricultura para la que la demanda de agua alcanza en verano también su máximo (Almuñécar, Granada.

  15. Hilbert-Huang analysis of BWR neutron detector signals: application to DR calculation and to corrupted signal analysis

    International Nuclear Information System (INIS)

    In this paper, we present an application of the empirical mode decomposition method [Proc. R. Soc. Lond. A 454 (1998) 903], to the stability analysis of BWR. The methodology developed in this paper decomposes the original time series data in intrinsic oscillation modes or IMFs. Then we compute for each IMF, its Hilbert amplitude spectrum and its Hilbert marginal spectrum. From the intrinsic mode related to BWR stability we have obtained by ordinary autoregressive methods the decay ratio value and the oscillation frequency. Also we have proven that the original signal can be reconstructed with seven IMFs and that this modes are mutually orthogonals

  16. Simulation of the injection system of cooling water to low pressure (Lpci) for a boiling water reactor (BWR) based on RELAP; Simulacion del sistema de inyeccion de agua de refrigeracion a baja presion (LPCI) para un reactor de agua en ebullicion (BWR) basado en RELAP

    Energy Technology Data Exchange (ETDEWEB)

    Delgado C, R. A.; Lopez S, E.; Chavez M, C., E-mail: renedelgado2015@hotmail.com [UNAM, Facultad de Ingenieria, Circuito Interior, Ciudad Universitaria, 04510 Mexico D. F. (Mexico)

    2012-10-15

    The present article describes the modeling and simulation of the Injection System of Cooling Water to Low Pressure (Lpci) for the nuclear power plant of Laguna Verde. Is very important to be able to predict the behavior of the nuclear plant in the case of an emergency stop, and while nearer to the reality are the results of a simulation, better is the safety protocol that can be devised. In the Engineering Faculty of the UNAM at the present is had logical models of the safety systems, but due to the nature of the same, these simulations do not provide of the quantity of enough information to be able to reproduce with more accuracy the behavior of the Lpci in the case of a severe accident. For this reason, the RELAP code was used for the flows modeling, components and structures of heat transfers in relation to the system Lpci. The modeling of the components is carried out with base on technical information of the nuclear plant and the results will be corroborated with information in reference documents as the Rasp (the Reactor analysis support package) and the Fsar (Final safety analysis report) for the nuclear power plant of Laguna Verde. (Author)

  17. Interpretation of the results of the CORA-33 dry core BWR test

    International Nuclear Information System (INIS)

    All BWR degraded core experiments performed prior to CORA-33 were conducted under ''wet'' core degradation conditions for which water remains within the core and continuous steaming feeds metal/steam oxidation reactions on the in-core metallic surfaces. However, one dominant set of accident scenarios would occur with reduced metal oxidation under ''dry'' core degradation conditions and, prior to CORA-33, this set had been neglected experimentally. The CORA-33 experiment was designed specifically to address this dominant set of BWR ''dry'' core severe accident scenarios and to partially resolve phenomenological uncertainties concerning the behavior of relocating metallic melts draining into the lower regions of a ''dry'' BWR core. CORA-33 was conducted on October 1, 1992, in the CORA tests facility at KfK. Review of the CORA-33 data indicates that the test objectives were achieved; that is, core degradation occurred at a core heatup rate and a test section axial temperature profile that are prototypic of full-core nuclear power plant (NPP) simulations at ''dry'' core conditions. Simulations of the CORA-33 test at ORNL have required modification of existing control blade/canister materials interaction models to include the eutectic melting of the stainless steel/Zircaloy interaction products and the heat of mixing of stainless steel and Zircaloy. The timing and location of canister failure and melt intrusion into the fuel assembly appear to be adequately simulated by the ORNL models. This paper will present the results of the posttest analyses carried out at ORNL based upon the experimental data and the posttest examination of the test bundle at KfK. The implications of these results with respect to degraded core modeling and the associated safety issues are also discussed

  18. Crack growth rate in core shroud horizontal welds using two models for a BWR

    Energy Technology Data Exchange (ETDEWEB)

    Arganis Juárez, C.R., E-mail: carlos.arganis@inin.gob.mx; Hernández Callejas, R.; Medina Almazán, A.L.

    2015-05-15

    Highlights: • Two models were used to predict SCC growth rate in a core shroud of a BWR. • A weld residual stress distribution with 30% stress relaxation by neutron was used. • Agreement is shown between the measurements of SCC growth rate and the predictions. • Slip–oxidation model is better at low fluences and empirical model at high fluences. - Abstract: An empirical crack growth rate correlation model and a predictive model based on the slip–oxidation mechanism for Stress Corrosion Cracking (SCC) were used to calculate the crack growth rate in a BWR core shroud. In this study, the crack growth rate was calculated by accounting for the environmental factors related to aqueous environment, neutron irradiation to high fluence and the complex residual stress conditions resulting from welding. In estimating the SCC behavior the crack growth measurements data from a Boiling Water Reactor (BWR) plant are referred to, and the stress intensity factor vs crack depth throughout thickness is calculated using a generic weld residual stress distribution for a core shroud, with a 30% stress relaxation induced by neutron irradiation. Quantitative agreement is shown between the measurements of SCC growth rate and the predictions of the slip–oxidation mechanism model for relatively low fluences (5 × 10{sup 24} n/m{sup 2}), and the empirical model predicted better the SCC growth rate than the slip–oxidation model for high fluences (>1 × 10{sup 25} n/m{sup 2}). The relevance of the models predictions for SCC growth rate behavior depends on knowing the model parameters.

  19. Compuestos orgánicos presentes en aguas de escombreras de carbón.

    OpenAIRE

    Llamas Borrajo, Juan F.; Canoira López, Laureano; García-Martínez, Mª Jesús; Ortega Romero, Marcelo; Llamas Lois, Alberto; Diaz Bautista, Maria Aranzazu

    2008-01-01

    Se ha realizado un estudio de la influencia de las aguas acidas de mina en la movilización de los hidrocarburos policidicos aromáticos (PAHs) presentes en las escombreras de carbón. Se observa como dichas aguas acidas disuelven preferentemente a los PAHs de menor peso molecular. También se ha realizado un análisis de riesgos que indica que existe un riesgo real por uso y consumo, en el interior de las viviendas, del agua subterránea. Por último, se han establecido las bases para una técnica p...

  20. Opciones de valorización de lodos de distintas estaciones depuradoras de aguas residuales

    OpenAIRE

    Colomer Mendoza, Francisco José; GALLARDO IZQUIERDO, ANTONIO; Fabián ROBLES MARTÍNEZ; Bovea Edo, María Dolores

    2010-01-01

    La legislación actual en la Unión Europea recomienda que los lodos de depuradora de aguas residuales se utilicen como fertilizante. Sin embargo, la presencia de metales pesados puede limitar esta aplicación, lo cual es más probable en caso de lodos de aguas residuales industriales. Por lo tanto, una segunda opción es la recuperación energética de los lodos. En el presente trabajo, se han analizado lodos digeridos procedentes de siete distintas depuradoras de aguas residuales españ...

  1. USO DE AGUA, POTENCIAL HÍDRICO Y RENDIMIENTO DE CHILE HABANERO (CAPSICUM CHINENSE JACQ.)

    OpenAIRE

    Wendy C. Quintal Ortiz; Alfonzo Pérez-Gutiérrez; Luis Latournerie Moreno; Cesar May-Lara; Esaú Ruiz Sánchez; Armando J. Martínez Chacón

    2012-01-01

    En las plantas el agua constituye típicamente de 80 a 95 % de la masa de los tejidos en crecimiento, donde desempeña funciones esenciales. La baja disponibilidad de agua en el suelo provoca el estrés abiótico de mayor incidencia en el crecimiento vegetal que en los sistemas agrícolas representa en pérdidas económicas. Es importante entonces estimar los requerimientos hídricos de los cultivos para mejorar su potencial productivo y el uso del agua. En este estudio se evaluó el efecto de cinco n...

  2. Análisis comparativo de indicadores de la calidad de agua superficial

    OpenAIRE

    Jiménez Jaramillo, Mario Alberto; Vélez Otálvaro, María Victoria

    2009-01-01

    En este trabajo se hace un análisis comparativo de indicadores de calidad de agua como un acercamiento a la caracterización general de la calidad de las aguas superficiales de la cuenca de la quebrada Doña María localizada en jurisdicción del Área Metropolitana del Valle de Aburrá (AMVA) y de la Corporación Autónoma Regional del Centro de Antioquia (CORANTIOQUIA). Para ello se ha empleado el índice de calidad de agua, WQINSF, propuesto por la National Sanitation Foundation (NS...

  3. Biomateriales sorbentes para la limpieza de derrames de hidrocarburos en suelos y cuerpos de agua

    OpenAIRE

    Ortíz González, Diana Paola; Fonseca, Fabio Andrade; Rodríguez Niño, Gerardo; Montenegro Ruiz, Luis Carlos

    2010-01-01

    Este estudio esta encaminado a identificar y evaluar materiales orgánicos naturales que puedan ser utilizados como sorbentes en las operaciones de limpieza de derrames de hidrocarburos tanto en suelos como en cuerpos de agua. Se evaluó la capacidad de sorción de tres materiales: fibra de caña, fibra de coco y buchón de agua, con tres hidrocarburos: 35, 30 y 25°API, y dos tipos de agua: destilada y marina artificial, adaptando la norma ASTM F-726 y siguiendo la metodología sugerida por el pr...

  4. Parametrización oceanográfica en índices de calidad del agua

    OpenAIRE

    de Armas Tápanes, J.; Rodríguez Romero, R.; Zayas Suárez, D.; Fernández Vila, L.J.; López García, D.

    2010-01-01

    En el trabajo se discute la polémica situación actual de la utilización de Índices de Calidad del Agua para ecosistemas marinos, sobre la base del análisis de 20 Índices de Calidad del Agua (ICA) basados en variantes de la magnitud media, ya sea aritmética simple, ponderada o geométrica: seis norteamericanos, siete colombianos, un mexicano, cuatro holandeses y dos cubanos, y la utilización en ellos, de 31 parámetros físico-químicos (28 en agua y tres en sedimentos). Se evidenció, ...

  5. ELIMINACIÓN CATALÍTICA DE NITRATOS EN CONTINUO EN AGUAS NATURALES

    OpenAIRE

    Franch Martí, Cristina

    2011-01-01

    La contaminación por nitratos de las aguas naturales es un problema que afecta a gran parte de zonas agrícolas y ganaderas. Para reducir los nitratos presentes en dichas aguas se han propuesto varias técnicas, la mejor de las cuales podría ser desde un punto de vista medioambiental la reducción catalítica de nitratos a nitrógeno. En este sentido, en esta tesis se ha utilizado la técnica antes nombrada para eliminar nitratos de aguas naturales utilizando un reactor en continuo. Para ello, s...

  6. Caracterización de las aguas residuales de la planta refinadora de aceites comestibles ERASOL

    OpenAIRE

    Arelis Abalos; Alina Marañón; José Manuel Fernández; Isabel Aguilera; María Fernanda Despaigne

    2007-01-01

    La contaminación de las aguas superficiales y cuerpos receptores es un grave problema ambiental en la actualidad. La bahía de Santiago de Cuba, segunda en importancia económica del país, recibe diariamente el impacto ambiental de 27 focos contaminantes; siendo la industria alimentaria un sector socioeconómico con alta incidencia en la contaminación de sus aguas debido a la descarga sin tratamiento de grandes volúmenes de aguas residuales generadas en diferentes procesos de esta industria. La ...

  7. ECOFICCIONES E IMAGINARIOS DEL AGUA Y SU IMPORTANCIA PARA LA MEMORIA CULTURAL Y LA SOSTENIBILIDAD

    OpenAIRE

    Eloy Martos Núñez; Alberto Martos García

    2013-01-01

    La cultura del agua debe ser vinculada de forma especial a las manifestaciones del patrimonio cultural intangible de los pueblos, como las tradiciones orales o escritas, la simbología o los rituales, que conforman lo que llamamos los Imaginarios del Agua. Estos deben ser analizados y deconstruidos a la luz de los nuevos paradigmas, como la hermenéutica y la ecocrítica. De este modo, la mitografía ayuda a perfilar el significado profundo de la cultura del agua ante las nuevas demandas medioamb...

  8. Development of a dynamic model of a BWR nuclear power plant

    International Nuclear Information System (INIS)

    A dynamic model of a nuclear power plant, including a boiling water reactor, high- and low-pressure turbines, moisture separator, reheater, condenser, feedwater heaters and feedwater pump, was developed. The model is one-dimensional except for the nuclear part of the reactor, which is based on the point kinetics equation, and the condenser model and feedwater pump model. It has been used to study different transients occuring during normal operating conditions and for evaluating the control systems of a BWR nuclear power plant. Particular emphasis was laid on the reactor pressure control system and the recirculation flow control system. (author)

  9. Electrical equipment performance under severe accident conditions (BWR/Mark 1 plant analysis): Summary report

    International Nuclear Information System (INIS)

    The purpose of the Performance Evaluation of Electrical Equipment during Severe Accident States Program is to determine the performance of electrical equipment, important to safety, under severe accident conditions. In FY85, a method was devised to identify important electrical equipment and the severe accident environments in which the equipment was likely to fail. This method was used to evaluate the equipment and severe accident environments for Browns Ferry Unit 1, a BWR/Mark I. Following this work, a test plan was written in FY86 to experimentally determine the performance of one selected component to two severe accident environments

  10. TRACE code validation for BWR spray cooling injection based on GOTA facility experiments

    Energy Technology Data Exchange (ETDEWEB)

    Racca, S. [San Piero a Grado Nuclear Research Group (GRNSPG), Pisa (Italy); Kozlowski, T. [Royal Inst. of Tech., Stockholm (Sweden)

    2011-07-01

    Best estimate codes have been used in the past thirty years for the design, licensing and safety of NPP. Nevertheless, large efforts are necessary for the qualification and the assessment of such codes. The aim of this work is to study the main phenomena involved in the emergency spray cooling injection in a Swedish designed BWR. For this purpose, data from the Swedish separate effect test facility GOTA have been simulated using TRACE version 5.0 Patch 2. Furthermore, uncertainty calculations have been performed with the propagation of input errors method and the identification of the input parameters that mostly influence the peak cladding temperature has been performed. (author)

  11. Use of the TRAC/BF1 code in BWR reactors instability studies

    International Nuclear Information System (INIS)

    The RETRAN and TRAC codes are examples of temporary codes that are used to analyze the stability of B.W.R. Although, in many cases, this codes present good results and predict the expected behaviour, they are very sensitive to the variations of core modeling, like for example, variations in the number of cells. This can question seriously the reliability and obviously the acceptability of the analysis done with this temporary codes. In this paper we present a work using the TRAC-BF1 code to simulate the in-phase and out-of-phase oscillations, and the influence of the chose of some parameters. (author)

  12. A theoretical and numerical investigation of turbulent steam jets in BWR steam blowdown

    International Nuclear Information System (INIS)

    The preliminary results of PHOENICS and RELAP5 show that the current numerical models are adequate in predicting steam flow and stratification patterns in the upper Drywell of a BWR containment subsequent to a blow-down event. However, additional modeling is required in order to study detailed local phenomena such as condensation with non-condensables, natural convection, and stratification effects. Analytically, the intermittence modified similarity solutions show great promise. Once γ is accounted for, the jet's turbulent shear stress can be determined with excellent accuracy

  13. The design and use of proficiency based BWR reactor maintenance and refuelling training mockups

    International Nuclear Information System (INIS)

    The purpose of this paper is to describe the ABB experience with the design and use of boiling water reactor training facilities. The training programs were developed and implemented in cooperation with the nuclear utilities. ABB operates two facilities, the ABB ATOM Light Water Reactor Service Center located in Vasteras, Sweden, and the ABB Combustion Engineering Nuclear Operations BWR Training Center located in Chattanooga, Tennessee, USA. The focus of the training centers are reactor maintenance and refueling activities plus the capability to develop and qualify tools, procedures and repair techniques

  14. A fatigue analysis including environmental effects for a pipe system in a Swedish BWR

    International Nuclear Information System (INIS)

    A BWR feed water piping system (austenitic steel) has been analyzed with two different fatigue curves and environmental factors. Original fatigue curve from ASME is compared to a new fatigue curve; ANL. The influence of environmental correction factors (Fen) is studied further for the piping system. It is noted that the results apply for this particular system, and general conclusions should be cautiously drawn. Typical for this system is that all dominant loads are within the low-cycle regime. This implies that the change of fatigue curve only leads to limited increases in usage factors. Larger changes can occur if larger number of cycles is within the high-cycle regime

  15. Revaluation on measured burnup values of fuel assemblies by post-irradiation experiments at BWR plants

    International Nuclear Information System (INIS)

    Fuel composition data for 8x8 UO2, Tsuruga MOX and 9x9-A type UO2 fuel assemblies irradiated in BWR plants were measured. Burnup values for measured fuels based on Nd-148 method were revaluated. In this report, Nd-148 fission yield and energy per fission obtained by burnup analyses for measured fuels were applied and fuel composition data for the measured fuel assemblies were revised. Furthermore, the adequacies of revaluated burnup values were verified through the comparison with burnup values calculated by the burnup analyses for the measured fuel assemblies. (author)

  16. Mark I 1/12-scale pressure suppression pool swell tests. [BWR

    Energy Technology Data Exchange (ETDEWEB)

    Torbeck, J.E.; Galyardt, D.L.; Walker, J.P.

    1976-05-01

    A second series of 1/12-scale tests of the Mark I BWR containment have been run to define the torus and ring header loads resulting from pressure suppression pool swell following a postulated LOCA. These tests were conducted following modification of the test section used for earlier tests to tighten the sealing and improve control of the test conditions. Forty-two tests were performed, investigating the sensitivity of the pool response to drywell pressurization rate, initial downcomer submergence, initial system pressure and initial drywell/wetwell pressure differential, covering the range of scaled Mark I expected conditions (on the basis of the FSAR).

  17. A Mechanistic Approach for the Prediction of Critical Power in BWR Fuel Bundles

    Science.gov (United States)

    Chandraker, Dinesh Kumar; Vijayan, Pallipattu Krishnan; Sinha, Ratan Kumar; Aritomi, Masanori

    The critical power corresponding to the Critical Heat Flux (CHF) or dryout condition is an important design parameter for the evaluation of safety margins in a nuclear fuel bundle. The empirical approaches for the prediction of CHF in a rod bundle are highly geometric specific and proprietary in nature. The critical power experiments are very expensive and technically challenging owing to the stringent simulation requirements for the rod bundle tests involving radial and axial power profiles. In view of this, the mechanistic approach has gained momentum in the thermal hydraulic community. The Liquid Film Dryout (LFD) in an annular flow is the mechanism of CHF under BWR conditions and the dryout modeling has been found to predict the CHF quite accurately for a tubular geometry. The successful extension of the mechanistic model of dryout to the rod bundle application is vital for the evaluation of critical power in the rod bundle. The present work proposes the uniform film flow approach around the rod by analyzing individual film of the subchannel bounded by rods with different heat fluxes resulting in different film flow rates around a rod and subsequently distributing the varying film flow rates of a rod to arrive at the uniform film flow rate as it has been found that the liquid film has a strong tendency to be uniform around the rod. The FIDOM-Rod code developed for the dryout prediction in BWR assemblies provides detailed solution of the multiple liquid films in a subchannel. The approach of uniform film flow rate around the rod simplifies the liquid film cross flow modeling and was found to provide dryout prediction with a good accuracy when compared with the experimental data of 16, 19 and 37 rod bundles under BWR conditions. The critical power has been predicted for a newly designed 54 rod bundle of the Advanced Heavy Water Reactor (AHWR). The selected constitutive models for the droplet entrainment and deposition rates validated for the dryout in tube were

  18. Technical report on material selection and processing guidelines for BWR coolant pressure boundary piping

    International Nuclear Information System (INIS)

    It is the purpose of this report to set forth acceptable methods to reduce the stress corrosion cracking susceptibility of BWR piping and thereby also provide an increased level of reactor coolant pressure boundary integrity. Because the most straightforward and desirable approach or methods may not be practicable, or even possible, for all plants, the bases for varying degrees of conformance to the guidelines are provided. Augmented inservice inspection and leak detection requirements are established for plants that have not fully implemented the provisions presented

  19. Analysis of non-linear BWR stability behavior applying proper orthogonal decomposition

    International Nuclear Information System (INIS)

    The main drivers of BWR stability behavior are the multiple thermal hydraulic interactions between power, flow rate, and density, reinforced by the Neutronics feedback. This coupling is schematically presented in Figure 1. Especially for high power low flow operating conditions associated with unfavorable power distribution BWR operation requires attention with respect to power oscillations. Admissible reactor operation conditions maintain a certain distance to the stability limit given by linear theory. Evaluation of non-linear states requires application of time domain codes or measurement data but this depends on the specific transients considered. Improvements of non-linear stability analysis focus on the accelerating of simulations and to provide assessment for the whole parameter space. In our transient analysis, the physical behavior of the system is approximated by a reduced order model (ROM) that respects stability relevant characteristics. More precisely, the system of coupled non-linear partial differential equations (PDEs) is mapped to coupled non-linear ordinary differential equations (ODEs) that can be solved faster and analyzed with respect to non-linear stability phenomena. Proper orthogonal decomposition (POD), i.e. a spectral method based on experimental or computational fluid dynamic (CFD) data, is capable to detect oscillating states of the physical system needed. Moreover, POD provides a well-defined truncation criterion for the minimum number of modes. A standard Galerkin method employing POD modes as Ansatz functions yields a non-linear ROM. The exceptional advantage of our methodology is its generality. It is accessible for various physical systems including the reactor dynamics of BWR. We envision a fully coupled non-linear investigation of the BWR system. The method benefits from a well defined sequence of processing steps which are automated to a large extent. This minimizes the required user interaction. Obviously the user still needs to

  20. Results of the Simulator smart against synthetic signals using a model of reduced order of BWR with additive and multiplicative noise; Resultados del simulador smart frente a senales sinteticas utilizando un modelo de orden reducido de BWR con ruido aditivo y multiplicativo

    Energy Technology Data Exchange (ETDEWEB)

    Munoz-Cobo, J. L.; Montesino, M. E.; Pena, J.; Escriva, A.; Melara, J.

    2011-07-01

    Results of SMART-simulator front of synthetic signals with models of reduced order of BWR with additive and multiplicative noise Under the SMART project, which aims to monitor the signals Cofrentes nuclear plant, we have developed a signal generator of synthetics BWR that will allow together real signals of plant the validation of the monitor.

  1. La hidrología y su papel en ingeniería del agua

    OpenAIRE

    Amanda García-Marín; José Roldán-Cañas; Javier Estévez; Fátima Moreno-Pérez; Aleix Serrat-Capdevila; Javier González; Félix Francés; Francisco Olivera; Oscar Castro-Orgaz; Juan V. Giráldez

    2014-01-01

    La Hidrología es una ciencia esencial en Ingeniería del Agua, la cual abarca un amplio abanico de temas de investigación que engloban los diversos estadios del agua en el ciclo Hidrológico, tanto en atmósfera, superficie y suelo. Con motivo del relanzamiento de la revista Ingeniería del Agua se presenta un breve artículo de carácter introductorio en el que se muestran algunas de la líneas de investigación actuales en Hidrología, dedicadas a lluvia, interceptación de agua por la vegetación, se...

  2. Claves y oportunidades para un pacto del agua en España.

    OpenAIRE

    Garrido Colmenero, Alberto; Custodio, Emilio

    2012-01-01

    Las peculiaridades geográficas españolas y su errática gestión del agua en las últimas décadas la sitúa en el marco internacional como un país incapaz de armonizar su escasez de recursos hídricos con su alto consumo interior. Por otro lado, España es pionera en tecnología relacionada con el agua, situándose entre los diez países más relevantes a nivel mundial. Por esto, diversas organizaciones independientes como el Observatorio del Agua de la Fundación Botín abogan por un Pacto del Agua, que...

  3. La ley de aguas de Entre Rios : La necesidad de su estudio en dos dimensiones

    OpenAIRE

    Maiztegui Martínez, Horacio Francisco

    2014-01-01

    El tema asignado, es el análisis de la ley de aguas de Entre Ríos N° 9.172. Trataremos de responder a las siguientes preguntas ¿Que tipos de aguas regula la ley de aguas?; ¿como se organiza el Gobierno del Agua?; ¿Como es el sistema de permisos, concesiones?; ¿Que instrumentos de conocimiento y protección prevé la ley? La ley Entrerriana, presenta una falta de adecuación a la ley Nacional como la ley 25.688, a los principios de la sustentabilidad (art.41 ° de la C.N., Ley n ° 25675 general...

  4. Reflexiones sobre la codificación del derecho de aguas

    OpenAIRE

    Mathus Escorihuela, Miguel

    2014-01-01

    El trabajo aborda la cuestión de la sistematización del derecho de aguas através de códigos de agua en la República Argentina, es decir, considerando el esquema federal de competencias del país. Trata la gestión histórica del derecho provincial de aguas y de la codificación en particular. Define que debe entenderse por un código de aguas y cuáles son las temáticas que debe contener, a la vez que se ocupa de enunciar otros temas que algunos códigos incorporan, analizando la conveniencia de su ...

  5. Mitos y realidades sobre la crisis del agua en España

    Directory of Open Access Journals (Sweden)

    Llamas Madurga, M. Ramón

    1999-10-01

    Full Text Available Not available.Los problemas del agua están con tanta frecuencia en los periódicos que se ha hecho usual hablar de la existencia de una crisis del agua. Esos problemas se caracterizan por su complejidad y por su variabilidad, debida ésta tanto a la irregularidad climática, como a los rápidos cambios en la percepción social de estos problemas. Se analizan los principales paradigmas que rigen la política del agua en España. Se clasifican en tres grupos: éticos, estéticos y tecnológicos. Se da prioridad al análisis del primer grupo ya que los paradigmas éticos son los que más influyen en la gestión del agua.

  6. Geochemical interpretation of the isotopic fragmentation of uranium in the Aguas de Prata (SP) aquiferous

    Energy Technology Data Exchange (ETDEWEB)

    Bonotto, D.M. (UNESP, Rio Claro (Brazil). Inst. de Geociencias e Ciencias Exatas); Fujimori, K. (Sao Paulo Univ. (Brazil). Inst. Astronomico e Geofisico)

    1984-01-01

    The uranium-238; uranium-234 and radon content of spring waters of Aguas de Prata (SP) was found, and the activity ratio AR(/sup 234/U//sup 238/U) was applied to the geochemistry of local water sources.

  7. Acuaporinas: proteínas mediadoras del transporte de agua.

    OpenAIRE

    Julio César Sánchez

    2009-01-01

    Introducción. Todos los organismos vivos están compuestos en su mayoría por agua, siendo ésta fundamental para la homeostasis celular a todo nivel. Por esta razón su transporte a través de las membranas biológicas ha sido siempre un campo de gran interés en la fisiología. La investigación acerca de este tópico se ha incrementado notablemente en los últimos años a partir del descubrimiento de las acuaporinas, las cuales han permitido comprender mejor los mecanismos que la célula utiliza para e...

  8. Las matemáticas limpian el agua

    Directory of Open Access Journals (Sweden)

    Ana Elena Narro Ramírez

    2009-01-01

    Full Text Available En la ciudad de León es preocupante el problema del agua que es contaminada, principalmente, por curtidores de piel, fabricantes de calzado y agroindustriales. Por ley, las autoridades ambientales han presionado a cada infractor para que disminuya su contaminación, pero el esfuerzo ha resultado inútil. El objetivo de este trabajo es demostrar que este problema tiene solución. Para encontrarla se construye un programa no lineal dinámico que a partir de los procesos tradicionalmente utilizados en la limpieza proporciona como solución una estrategia innovadora de costo moderado que se prorratea entre los infractores usando jerarquización analítica.

  9. Structural response of DN15-tubes under radiolysis gas detonation loads for BWR safety applications

    International Nuclear Information System (INIS)

    A U-shaped DN15 tube with 15 mm ID, 3 mm wall thickness was exposed to radiolysis gas (2H2+O2) detonation loads to investigate the structural stability of typical BWR tubes. Radiolysis gas at ambient temperatures was used at initial pressure up to 70 bar. The effect of transient detonation loads with peak pressures up to 1540 bar on the tube response was studied with strain gauges and simultaneous local pressure measurements. The strain measurements demonstrated that the tube material remained in the elastic response regime for initial radiolysis gas pressures of up to 20 bar. For the case with 30 and 70 bar initial pressure, local plastic deformations were observed under peak detonation pressures of 540 and 1540 bar, respectively. The measured strain values could be well explained with a simplified analysis of the elastic-plastic material behaviour under quasi-static loading conditions. Based on the measured strain data for the DN-15 tube, upper and lower bounds were estimated for the burst pressures of the failed pipes in the Brunsbuettel and the Hamaoka-1 NPP events. The experiments provide new data for the validation of structural dynamic codes and models of the response of typical BWR tubes under radiolysis gas detonation loads. (authors)

  10. Nuclear coupled flow instability study for natural circulation BWR startup transient

    International Nuclear Information System (INIS)

    Natural circulation Boiling Water Reactor (BWR) startup transient was investigated in Purdue University Multidimensional Test Assembly (PUMA) facility based on a natural circulation BWR design. Strategy and results of the experiments, which consider the effects of void-reactivity and fuel heat conduction time constant, are discussed. Total reactivity is treated to be composed of two components: external reactivity due to control rod motion and void-reactivity. A detailed analysis for heat conduction problem is performed to derive dimensionless groups. Based on area-averaged heat conduction equations for pellet and clad regions, Fourier and Biot numbers are derived to simulate wall heat flux response. Power transient, which has been used for startup transient investigation without void-reactivity feedback is used to derive the control rod reactivity. Twelve conductivity probes are used to measure local void fraction inside core at three axial locations. The local void-fraction data is used to calculate volume average void fraction, which is used to calculate the voil-reactivity. A real-time Point Kinetic Model solver is implemented to PUMA heater power control program to determine power transient during startup. The results demonstrate that the inclusion of void-reactivity feedback worsen the scenario for startup instabilities and may cause large amplitude neutron flux oscillations. (author)

  11. Final results of the XR2-1 BWR metallic melt relocation experiment

    International Nuclear Information System (INIS)

    This report documents the final results of the XR2-1 boiling water reactor (BWR) metallic melt relocation experiment, conducted at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission. The objective of this experiment was to investigate the material relocation processes and relocation pathways in a dry BWR core following a severe nuclear reactor accident such as an unrecovered station blackout accident. The imposed test conditions (initial thermal state and the melt generation rates) simulated the conditions for the postulated accident scenario and the prototypic design of the lower core test section (in composition and in geometry) ensured that thermal masses and physical flow barriers were modeled adequately. The experiment has shown that, under dry core conditions, the metallic core materials that melt and drain from the upper core regions can drain from the core region entirely without formation of robust coherent blockages in the lower core. Temporary blockages that suspended pools of molten metal later melted, allowing the metals to continue draining downward. The test facility and instrumentation are described in detail. The test progression and results are presented and compared to MERIS code analyses. 6 refs., 55 figs., 4 tabs

  12. Electrochemical response to hydrogen water chemistry at the J.A. FitzPatrick BWR

    International Nuclear Information System (INIS)

    It was the goal of the HWC campaign at the FitzPatrick BWR to determine the hydrogen injection rates required to mitigate IGSCC and IASCC in the reactor internals. Electrochemical sensors were installed at two elevations in one of the local power range monitors (LPRMs). In the summer of 1990 the HWC campaign was conducted. The feedwater hydrogen injection rate was varied from 12 to 90 standard cubic feet/minute (SCFM) and the ECPs from the sensors in the LPRM were measured. The relationship of hydrogen injection versus ECP was determined with specific emphasis on the injection rate required to decrease the ECP to -0.230 V(SHE) at each location in the LPRM. The LPRM lower position, equivalent to the outlet of the lower plenum, required three times more hydrogen injection than previously determined for the recirculation piping system to achieve -0.230 V(SHE). The upper position in the LPRM required far greater hydrogen injection rates to approach the protection potentials. Since completion of the FitzPatrick test, a program with similar objectives was conducted at an overseas BWR. It was found that in the high radiation environment of the core bypass newly designed platinum sensors performed quite adequately as reversible reference electrodes. These results provide a possible approach for protection of key reactor structurals with minimum hydrogen injection and low main steam line dose rates

  13. Transient and stability analysis of a BWR core with thorium-uranium fuel

    Energy Technology Data Exchange (ETDEWEB)

    Nunez-Carrera, Alejandro [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan 779 Col. Narvarte, 03020 Mexico, DF (Mexico); Espinosa-Paredes, Gilberto [Division de Ciencias Basicas e Ingenieria, Universidad Autonoma Metropolitana, Av. San Rafael Atlixco 186, Col. Vicentina, 09340 Mexico, DF (Mexico)], E-mail: gepe@xanum.uam.mx; Francois, Juan-Luis [Departamento de Sistemas Energeticos, Facultad de Ingenieria, Universidad Nacional Autonoma de Mexico, Paseo Cuauhnahuac 8532, 62550 Jiutepec Mor. (Mexico)

    2008-08-15

    The kinetic response of a boiling water reactor (BWR) equilibrium core using thorium as a nuclear material, in an integrated blanket-seed assembly, is presented in this work. Additionally an in-house code was developed to evaluate this core under steady state and transient conditions including a stability analysis. The code has two modules: (a) the time domain module for transient analysis and (b) the frequency domain module for stability analysis. The thermal-hydraulic process is modeled by a set of five equations, considering no homogeneous flow with drift-flux approximation and non-equilibrium thermodynamic. The neutronic process is calculated with a point kinetics model. Typical BWR reactivity effects are considered: void fraction, fuel temperature, moderator temperature and control rod density. Collapsed parameters were included in the code to represent the core using an average fuel channel. For the stability analysis, in the frequency domain, the transfer function is determined by applying Laplace-transforming to the calculated pressure drop perturbations in each of the considered regions where a constant total pressure drop was considered. The transfer function was used to study the system response in the frequency domain when an inlet flow perturbation is applied. The results show that the neutronic behavior of the core with thorium uranium fuel is similar to a UO{sub 2} core, even during transient conditions. The stability and transient analysis show that the thorium-uranium fuel can be operated safely in current BWRs.

  14. Comparison of metaheuristic optimization techniques for BWR fuel reloads pattern design

    International Nuclear Information System (INIS)

    Highlights: ► This paper shows a performance comparison of several optimization techniques for fuel reload in BWR. ► Genetic Algorithms, Neural Networks, Tabu Search and several Ant Algorithms were used. ► All optimization techniques were executed under same conditions: objective function and an equilibrium cycle. ► Fuel bundles with minor actinides were loaded into the core. ► Tabu search and Ant System were the best optimization technique for the studied problem. -- Abstract: Fuel reload pattern optimization is a crucial fuel management activity in nuclear power reactors. Along the years, a lot of work has been done in this area. In particular, several metaheuristic optimization techniques have been applied with good results for boiling water reactors (BWRs). In this paper, a comparison of different metaheuristics: genetic algorithms, tabu search, recurrent neural networks and several ant colony optimization techniques, were applied, in order to evaluate their performance. The optimization of an equilibrium core of a BWR, loaded with mixed oxide fuel composed of plutonium and minor actinides, was selected to be optimized. Results show that the best average values are obtained with the recurrent neural networks technique, meanwhile the best fuel reload was obtained with tabu search. However, according to the number of objective functions evaluated, the two fastest optimization techniques are tabu search and Ant System.

  15. An intermediate break BWR LOCA test (RUN 991) at ROSA-III

    International Nuclear Information System (INIS)

    Double failures on the emergency-core-cooling systems (ECCSs) can be resulted in a case of loss-of-coolant accident (LOCA) of a boiling water reactor (BWR) by assuming an ECCS line break and the single failure criterion on another ECCS. In the Rig-of-Safety Assessment (ROSA)-III program, two BWR LOCA simulation tests with intermediate break areas were performed to experimentally study influences of the ECCS double failures on core cooling phenomena. As there was no break unit in the ROSA-III ECCS lines, two break locations were selected above and below the ECCS line elevation. Namely, one is a main steam line (MSL) break test of RUN 992 which was previously reported. Another one is a single-ended jet pump drive line (JPDL) break test of RUN 991. And this break location effect on the system responses was briefly studied in a report of JAERI 1307. This report presents precise experiment results of RUN 991 with respect to the core cooling phenomena related to transient system mass and also presents additional findings on the influences of ECCS double failures in some intermediate break LOCA tests including above two tests. (author)

  16. Investigation of control rod worth and nuclear end of life of BWR control rods

    Energy Technology Data Exchange (ETDEWEB)

    Magnusson, Per

    2008-01-15

    This work has investigated the Control Rod Worth (CRW) and Nuclear End of Life (NEOL) values for BWR control rods. A study of how different parameters affect NEOL was performed with the transport code PHOENIX4. It was found that NEOL, expressed in terms of {sup 10}B depletion, can be generalized beyond the conditions for which the rod is depleted, such as different power densities and void fractions, the corresponding variation in the NEOL will be about 0.2-0.4% {sup 10}B. It was also found that NEOL results for different fuel types and different fuel enrichments have a variation of about 2-3% in {sup 10}B depletion. A comparative study on NHOL and CRW was made between PHOENIX4 and the stochastic Monte Carlo code MCNP. It was found that there is a significant difference, both due to differences in the codes and to limitations in the geometrical modeling in PHOENIX4. Since MCNP is considered more physically correct, a methodology was developed to calculate the nuclear end of life of BWR control rods with MCNP. The advantages of the methodology are that it does not require other codes to perform the depletion of the absorber material, it can describe control rods of any design and it can deplete the control rod absorber material without burning the fuel. The disadvantage of the method is that is it time-consuming.

  17. Experimental investigation of control absorber blade effects in a modern 10x10 BWR assembly

    Energy Technology Data Exchange (ETDEWEB)

    Jatuff, F.; Grimm, P.; Murphy, M.; Luethi, A.; Seiler, R.; Joneja, O.; Meister, A.; Geemert, R. van; Brogli, R.; Chawla, R. [Paul Scherrer Inst., CH-5232 Villigen PSI (Switzerland); Williams, T. [EGL Laufenburg (Switzerland); Helmersson, S. [Westinghouse Atom (Sweden)

    2001-03-01

    The accurate estimation of reactor physics parameters related to the presence of cruciform absorber blades. In Boiling Water Reactors (BWR) is important for safety assessment, and for achieving a flexible operation during the cycle. Characteristics which are affected strongly include the power distribution for controlled core regions and its impact on linear heat generation rate margins, as well as the build-up of plutonium, and its influence on core excess reactivity and the reactivity worth of the shutdown system. PSI and the Swiss Nuclear Utilities (UAK) are conducting an experimental reactor physics programme related to modern Light Water Reactor (LWR) fuel assemblies, as employed in the Swiss nuclear power plants: the so-called. LWR-PROTEUS Phase I project. A significant part of this project has been devoted to the characterization of highly heterogeneous BWR fuel elements in the presence of absorber blades. The paper presents typical results for the performance of modern lattice codes in the estimation of controlled assembly reaction rate distributions, the sensitivity to the geometrical and material characterization, and a preliminary comparison of reflected-test-zone calculations with experimental reaction rate distributions measured in a Westinghouse SVEA-96+ assembly under full-density water moderation conditions in the presence of Westinghouse boron-carbide absorber blades. (author)

  18. TRACE Model for Simulation of Anticipated Transients Without Scram in a BWR

    Energy Technology Data Exchange (ETDEWEB)

    Cheng L. Y.; Baek J.; Cuadra,A.; Aronson, A.; Diamond, D.; Yarsky, P.

    2013-11-10

    A TRACE model has been developed for using theTRACE/PARCS computational package [1, 2] to simulate anticipated transients without scram (ATWS) events in a boiling water reactor (BWR). The model represents a BWR/5 housed in a Mark II containment. The reactor and the balance of plant systems are modeled in sufficient detail to enable the evaluation of plant responses and theeffectiveness of automatic and operator actions tomitigate this beyond design basis accident.The TRACE model implements features thatfacilitate the simulation of ATWS events initiated by turbine trip and closure of the main steam isolation valves (MSIV). It also incorporates control logic to initiate actions to mitigate the ATWS events, such as water levelcontrol, emergency depressurization, and injection of boron via the standby liquid control system (SLCS). Two different approaches have been used to model boron mixing in the lower plenum of the reactor vessel: modulate coolant flow in the lower plenum by a flow valve, and use control logic to modular.

  19. High-fidelity multiphysics simulation of BWR assembly with coupled TORT-TD/CTF

    Energy Technology Data Exchange (ETDEWEB)

    Magedanz, J. [Dept. of Mechanical and Nuclear Engineering, Pennsylvania State Univ., Reber Building, Univ. Park, PA 16802 (United States); Perin, Y. [Gesellschaft fuer Anlagen- und Reaktorsicherheit GRS mbH, Forschungsinstitute, D-85748 Garching (Germany); Avramova, M. [Dept. of Mechanical and Nuclear Engineering, Pennsylvania State Univ., Reber Building, Univ. Park, PA 16802 (United States); Pautz, A.; Puente-Espel, F.; Seubert, A.; Sureda, A.; Velkov, K.; Zwermann, W. [Gesellschaft fuer Anlagen- und Reaktorsicherheit GRS mbH, Forschungsinstitute, D-85748 Garching (Germany)

    2012-07-01

    This paper describes the application of the coupled codes TORT-TD and CTF to the pin-by-pin modeling of a BWR fuel assembly with thermal-hydraulic feedback. TORT-TD, developed at GRS, is a time-dependent three dimensional discrete ordinates code. CTF is the PSU's improved version of the subchannel code COBRA-TF, which uses a two-fluid, three-field model to represent two-phase flow with entrained droplets, and is commonly applied to evaluate LWR safety margins. The coupled codes system TORT-TD/CTF, already applied to several PWR cases involving MOX, was adapted from PWR to BWR applications. The purpose of the research described in this paper is to verify the coupling for modeling two-phase flow at the pin cell level. Using an ATRIUM-10 assembly, the system's steady-state capabilities were tested on two cases: one without control blade insertion and another with partially inserted blades. The influence of the neutron absorber on local axial and radial parameters is presented. The description of an inlet flow reduction transient is an example for the time-dependent capability of the coupled system. (authors)

  20. Basic evaluation on nuclear characteristics of BWR high burnup MOX fuel and core

    International Nuclear Information System (INIS)

    MOX fuel will be used in existing commercial BWR cores as a part of reload fuels with equivalent operability, safety and economy to UO2 fuel in Japan. The design concept should be compatible with UO2 fuel design. High burnup UO2 fuels are being developed and commercialized step by step. The MOX fuel planned to be introduced in around year 2000 will use the same hardware as UO2 8 x 8 array fuel developed for a second step of UO2 high burnup fuel. The target discharge exposure of this MOX fuel is about 33 GWd/t. And the loading fraction of MOX fuel is approximately one-third in an equilibrium core. On the other hand, it becomes necessary to minimize a number of MOX fuels and plants utilizing MOX fuel, mainly due to the fuel economy, handling cost and inspection cost in site. For the above reasons, it needed to developed a high burnup MOX fuel containing much Pu and a core with a large amount of MOX fuels. The purpose of this study is to evaluate basic nuclear fuel and core characteristics of BWR high burnup MOX fuel with batch average exposure of about 39.5 GWd/t using 9 x 9 array fuel. The loading fraction of MOX fuel in the core is within a range of about 50% to 100%. Also the influence of Pu isotopic composition fluctuations and Pu-241 decay upon nuclear characteristics are studied. (author). 3 refs, 5 figs, 3 tabs

  1. Final results of the XR2-1 BWR metallic melt relocation experiment

    Energy Technology Data Exchange (ETDEWEB)

    Gauntt, R.O.; Humphries, L.L.

    1997-08-01

    This report documents the final results of the XR2-1 boiling water reactor (BWR) metallic melt relocation experiment, conducted at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission. The objective of this experiment was to investigate the material relocation processes and relocation pathways in a dry BWR core following a severe nuclear reactor accident such as an unrecovered station blackout accident. The imposed test conditions (initial thermal state and the melt generation rates) simulated the conditions for the postulated accident scenario and the prototypic design of the lower core test section (in composition and in geometry) ensured that thermal masses and physical flow barriers were modeled adequately. The experiment has shown that, under dry core conditions, the metallic core materials that melt and drain from the upper core regions can drain from the core region entirely without formation of robust coherent blockages in the lower core. Temporary blockages that suspended pools of molten metal later melted, allowing the metals to continue draining downward. The test facility and instrumentation are described in detail. The test progression and results are presented and compared to MERIS code analyses. 6 refs., 55 figs., 4 tabs.

  2. Study on the feasibility of 1300 MWe class simplified BWR plant

    International Nuclear Information System (INIS)

    A range of power levels for 1000 MWe-1500 MWe natural circulation core was found to be feasible from the thermal hydraulic performance standpoint by our sensitivity analysis. In this study, we selected a power level of 1300 MWe that is expected to satisfy Japanese Utilities needs. After we set the RPV configuration, we will study the detailed comprehensive analysis so that we can confirm the technical feasibility of large scaled simplified BWR. RPV inner diameter 7.5 m, which can be manufactured with current technology and present facilities, and the chimney height of 8.5 m was selected. After a preliminary design of the core and fuel was carried out, the natural circulation core flow was calculated by EASHAP code. The stability evaluation during normal operation is analyzed and a major transient analysis is conducted. The design of the core and fuel is evaluated based on PANACEA code. The detailed analysis shows that a 1300 MWe class natural circulation core satisfies the thermal and stability criteria. The containment system, which consists of the drywell and suppression chamber, is determined with supporting containment pressure-temperature analytical response. The layout inside the primary containment vessel that is applicable to a RPV incorporating the 1300 MWe core is approximately arranged. From the above, it is confirmed that 1000 MWe is not technical upper power limit of the simplified BWR plant. (author)

  3. TRACE/PARCS validation for BWR stability based on OECD/NEA Oskarshamn-2 benchmark

    International Nuclear Information System (INIS)

    On February 25, 1999, the Oskarshamn-2 NPP experienced a stability event, which culminated in diverging power oscillations with decay ratio greater than 1.3. The event was successfully modeled by TRACE/PARCS coupled code system and the details of the modeling and solution are described in the paper. The obtained results show excellent agreement with the plant data, capturing the entire behavior of the transient including onset of instability, growth of oscillation (decay ratio) and the oscillation frequency. The event allows coupled code validation for BWR with a real, challenging stability event, which challenges accuracy of neutron kinetics (NK), thermal-hydraulics (TH) and TH/NK coupling. The success of this work has demonstrated the ability of 3-D coupled code systems to capture the complex behavior of BWR stability events. The problem is released as an international OECD/NEA benchmark, and it is the first benchmark based on measured plant data for a stability event with a DR greater than one. Interested participants are invited to contact authors for more information. (author)

  4. Thermal-hydraulics stability of natural circulation BWR under startup. Flashing effects

    International Nuclear Information System (INIS)

    To help achieve the necessary natural circulation flow, a fairly long chimney is installed in a boiling natural circulation reactor like the ESBWR. In such systems, thermal-hydraulic stability during low pressure start-up should be examined while considering the flashing induced by the pressure drop in the channel and the chimney due to gravity head. In this work, a BWR stability analysis code in the frequency domain, named FISTAB (Flashing-Induced STability Analysis for BWR), was developed to address the issue of flashing-induced instability. A thermal-hydraulics non-homogeneous equilibrium model (NHEM) based on a drift flux formulation along with a lumped fuel dynamics model is incorporated in the work. The vapor generation rate is derived from the mixture energy conservation equation while considering the effect of flashing. The functionality of the FISTAB code was confirmed by comparison to experimental results from SIRIUS-N facility at CRIEPI, Japan. Both stationary and perturbation results agree well with the experimental results. (author)

  5. Analysis of Void Reactivity Coefficient for 3D BWR Assembly Model

    Directory of Open Access Journals (Sweden)

    Andrius Slavickas

    2016-01-01

    Full Text Available The effect of BWR fuel assembly 3D model on void reactivity coefficient (VRC estimation is investigated. VRC values were calculated for different BWR assembly models applying deterministic T-NEWT and Monte Carlo KENO-VI functional modules of SCALE 6.1 code package. The difference between deterministic T-NEWT and Monte Carlo KENO-VI simulations is negligible (0.18 pcm/%. The influence of the assumed more detailed coolant density profile was estimated as well. VRC increases with the application of a larger number of coolant density values across fuel assembly height. It was shown that the coolant density profile described by 6 values per height could be considered sufficient from prospect of VRC estimation, as a more detailed density profile has impact below 1% on total assembly void effects. VRC values were decomposed to values for individual nodes and isotopes, since decomposition provides useful insights to describe the overall behaviour of VRC in detail.

  6. Respuesta productiva del cafeto al manejo del riego. Función agua-rendimiento

    Directory of Open Access Journals (Sweden)

    Enrique Cisneros Zayas

    2015-01-01

    Full Text Available La disponibilidad de agua para la agricultura está disminuy endo progresivamente, debido a la competencia entre dif erentes usuarios, lo que impone una utilización eficiente de este importante recurso. Para lograr elevar la productividad del agua es imprescindible el estudio de las f unciones agua-rendimiento. E l presente trabaj o tiene como obj etivo determinar las distintas f ormas de ex presió n de la f unció n agua-rendimiento, así como la productividad del agua (WP para el caf eto. Como resultado se tiene q ue el modelo lineal f ue el de mej or aj uste para las relaciones rendimiento/ evapotranspiración y rendimiento/agua aplicada por riego del cafeto, con coeficientes de determinación superiores a 0,70 y una eficiencia del agua evapotranspirada alrededor de 0,75 k g de caf é oro por cada milí metro adicional de agua. L os resultados del aná lisis de las f unciones usando valores relativos mostraron q ue si se satisf acen al 100% las necesidades del caf eto durante todo el ciclo del cultivo se puede esperar un rendimiento má x imo de 2,78 t· h a-1, y si se logra satisf acer en má s del 8 0% podrían ser superiores a 2,6 t· h a-1. E l f actor de respuesta del rendimiento Ky para el cafeto en las condiciones de este estudio resultó ser de 0,52. Por cada metro cú bico de agua consumida y agua aplicada por riego el caf eto produce como promedio 1,9 2 y 3 ,8 k g de caf é oro, respectivamente. L a productividad máxima se obtuvo con 5 3 9 9 m3 · h a-1 de agua consumida durante todo el año.

  7. Servicios ambientales, agua y economía

    Directory of Open Access Journals (Sweden)

    Juan Pablo Ruiz Soto

    2007-11-01

    Full Text Available Los servicios ambientales (SA asociados a los ecosistemas naturales están seriamente amenazados por acciones locales y por el calentamiento global. El SA asociado al agua y su efecto sobre calidad y cantidad en cuencas hidrográficas aportantes a acueductos y sistemas de riego, son de gran importancia económica y social. Para Bogotá-Colombia el SA de los páramos y bosque nublado en la cuenca de Chingaza representa US$18,2 millones anuales. Para el abastecimiento de agua a la ciudad de Quito-Ecuador, el efecto negativo del cambio climático (CC asociado a la contracción de los glaciares representa un incremento en la inversión de un 31% versus el escenario sin CC. Se deben tomar medidas para asegurar la permanencia de los SA y mitigar los efectos del CC./ Environmental services (ES related to natural ecosystems are seriously threatened by local activities and global warming. The ES related to water and its effect on quality and quantity in watersheds that supply aqueducts and irrigation systems has great social and economic importance. For Bogotá-Colombia the ES of páramos and cloudy forest in the Chingaza basin represents US$18.2 million per year. For water supply in the city of Quito-Ecuador, the negative effect of climate change (CC related to the contraction of glaciers represents a 31% increase in investments versus the scenario without CC. Measures must be taken to ensure the permanence of ES and mitigate the effects of CC.

  8. BWR stability analysis: methodology of the stability analysis and results of PSI for the NEA/NCR benchmark task

    International Nuclear Information System (INIS)

    The report describes the PSI stability analysis methodology and the validation of this methodology based on the international OECD/NEA BWR stability benchmark task. In the frame of this work, the stability properties of some operation points of the NPP Ringhals 1 have been analysed and compared with the experimental results. (author) figs., tabs., 45 refs

  9. Development, assessment and application of TRAC-BF1/v2001.2 for beyond design basis BWR LOCA transients

    International Nuclear Information System (INIS)

    In preparation for the possible transition to risk based licensing, it is increasingly important to demonstrate the applicability of Best Estimate codes to more extreme conditions corresponding for example to limited equipment availability. With this idea in mind, we have reviewed the application of TRAC-BF1 to Large and Small Break LOCAs. In this context this work describes the assessment and applications of the Penn State University (PSU) version 2001.2 of TRAC-BF1 with all the PSI updates, to the analysis of hypothetical Large Break (LB) LOCAs in a BWR/4 with postulated limited ECC availability. Since in contrast to a LB-LOCA in a BWR with full ECC availability, the rod surface temperatures reach relatively high values, additional assessment of the code under such conditions is required. Hence, after analyzing bottom flooding separate-effect experiments in two different heater rod bundles and a TLTA LB-LOCA test, we shall present and discuss the results of the analysis of a LB-LOCA with highly restricted Emergency Core Cooling flow in a BWR/4. In this context, we shall also assess different descretization of some terms of the 3D momentum equations, which was found to be important in the analysis of BWR Small Break LOCAs

  10. Diseño de una planta depuradora de aguas residuales urbanas

    OpenAIRE

    Rodríguez Ruiz, Lucía

    2005-01-01

    El presente proyecto tiene por objeto el diseño de una estación depuradora de aguas residuales urbanas situada próxima a un núcleo urbano y cuyo vertido se hará en una zona considerada como zona sensible según el Real Decreto-Ley 11/1995, de 28 de diciembre, por el que se establecen las normas aplicables al tratamiento de las aguas residuales urbanas.

  11. Agua que no has de beber… déjala correr

    OpenAIRE

    Agredo Cardona, Gustavo Adolfo

    2010-01-01

    En el panorama mundial existe preocupación por la utilización o consumo del agua, sus costos (Spiller, Savedoff, y Banco Interamericano de Desarrollo, 2000), disponibilidad, aprovechamiento o pérdida de ésta. La consideración ambiental no está relacionada con la desaparición de algunas especies o por la ausencia del agua, sino porque se pone en riesgo la vida humana.

  12. ¿Qué tan importante es el agua? Desarrollo sustentable y recursos naturales

    OpenAIRE

    Kras, Eva; Simonsen, Ove

    2001-01-01

    A partir de una definición de desarrollo sustentable, se presenta el modelo de desarrollo global como filosofía imperante en torno al agua, y las realidades globales del agua, particularmente en torno a la contaminación, la salud, y la sustentabilidad y seguridad. Se analizan las oportunidades y retos para los países en desarrollo de América Latina, y se proponen acciones puntuales.

  13. Editorial of the twenty first edition of Ambiente & Agua - An Interdisciplinary Journal of Applied Science

    Directory of Open Access Journals (Sweden)

    Getulio Teixeira Batista

    2013-04-01

    Full Text Available This issue marks the 21st edition of Ambiente & Agua. This edition has included 20 peer evaluated and reviewed articles, and all editions were published on time. We continue to employ a policy of complete open access, and to foster the visibility of articles. We continue to register the doi of all articles and to publish each issue as a single document in addition to the individual articles. This editorial emphasizes new important recognition received by the Ambiente & Agua journal.

  14. Plan director red de abastecimiento de agua potable en la localidad de Gestalgar (Valencia)

    OpenAIRE

    HERRERA AGUILAR, MANUEL JOSÉ

    2011-01-01

    El objeto de este proyecto es definir las características técnicas necesarias para aumentar la eficiencia de las redes de alta de suministro de agua potable en la localidad de Gestalgar (Valencia) Herrera Aguilar, MJ. (2011). Plan director red de abastecimiento de agua potable en la localidad de Gestalgar (Valencia). http://hdl.handle.net/10251/12468. Archivo delegado

  15. Solubilidad de acetaminofén en sistemas agua-alcohol usp-jarabe usp y agua-alcohol usp-sorbitol usp

    OpenAIRE

    Bolaños, Clara Inés; Erazo, Ernesto Alonso; Luengas, Pilar; Barbosa, Helber; Martínez, Fleming

    2009-01-01

    Se determinó la solubilidad de una muestra de acetaminofén del mercado nacional a 20.0 ± 0.5 ºC en sistemas solventes ternarios agua – alcohol USP – jarabe USP – y agua – alcohol USP – sorbitol USP, como aporte a la generación sistemática de información sobre las propiedades fisicoquímicas en estudios de preformulación de formas farmacéuticas líquidas homogéneas. Los resultados muestran que las mezclas agua – alcohol USP – jarabe USP de composición en peso 30 – 60 – 10 % y a...

  16. Corrosion fatigue initiation behaviour of wrought austenitic stainless pipe steels under simulated BWR/HWC and PWR conditions

    Energy Technology Data Exchange (ETDEWEB)

    Leber, H.J.; Ritter, S.; Seifert, H.P [Paul Scherrer Institute, Nuclear Energy and Safety Research Department, Laboratory for Nuclear Materials, 5232 Villigen PSI (Switzerland)

    2011-07-01

    The corrosion fatigue (CF) initiation and short crack growth behavior of different low-carbon and stabilized austenitic stainless steels was characterized under simulated BWR and primary PWR conditions by cyclic fatigue tests with sharply notched fracture mechanics specimens in the temperature range from 70 to 320 C. Environmental reduction of fatigue initiation life was observed in all stainless steels at strain rates {<=} 0.1 %/s in BWR and PWR environment. The stationary short crack CF crack growth rates after crack advances of 50 to 300 {mu}m from the notch-root were in the typical range of corresponding results from tests with long cracks (pre-cracked specimens) and also showed the same system parameter response. The effect of environment on the initiation process ({Delta}a = 10 {mu}m) was relevantly stronger than on the subsequent stationary short crack growth. Both, under BWR/HWC and PWR conditions, a relevant environmental reduction of fatigue initiation life occurred for the combination of temperatures {>=} 100 C, notch strain rates {<=} 0.1 %/s and notch strain amplitudes {>=} 0.3 %. If these conjoint threshold conditions were simultaneously satisfied, the environmental enhancement increased with decreasing strain rate and increasing temperature. Material and water chemistry parameters usually only had a little effect. Sensitization affected the CF behavior under highly oxidizing BWR/NWC conditions only. Preliminary block loading experiments did not reveal significant static load hold period effects on the technical corrosion fatigue initiation life. If the critical requirements were satisfied, the BWR/HWC and PWR environments usually resulted in acceleration of short fatigue crack growth by a factor of 5 to 20 with respect to air. Solution annealed steels showed slightly shorter CF initiation lives, but also lower stationary short CF crack growth rates under BWR/HWC and PWR conditions with low ECPs than under highly oxidizing BWR/NWC conditions. A very

  17. ECOFICCIONES E IMAGINARIOS DEL AGUA Y SU IMPORTANCIA PARA LA MEMORIA CULTURAL Y LA SOSTENIBILIDAD

    Directory of Open Access Journals (Sweden)

    Eloy Martos Núñez

    2013-07-01

    Full Text Available La cultura del agua debe ser vinculada de forma especial a las manifestaciones del patrimonio cultural intangible de los pueblos, como las tradiciones orales o escritas, la simbología o los rituales, que conforman lo que llamamos los Imaginarios del Agua. Estos deben ser analizados y deconstruidos a la luz de los nuevos paradigmas, como la hermenéutica y la ecocrítica. De este modo, la mitografía ayuda a perfilar el significado profundo de la cultura del agua ante las nuevas demandas medioambientales, educativas y culturales del siglo XXI, en un contexto donde el agua ya no es solo un recurso estratégico, sino un bien cultural ligado al desarrollo local y a las políticas de sostenibilidad. Por ello, al conocer las tradiciones ancestrales y los imaginarios en torno al agua, y al sensibilizar a los alumnos con los valores plurales de estas manifestaciones culturales --que siempre van encaminados al respeto y al conocimiento del patrimonio natural y cultural--, contribuimos de forma decisiva a la gobernanza del agua y a la gestión sostenible y responsable de los recursos hídricos, pues sin duda el principal problema de la sostenibilidad será la educación de los ciudadanos.

  18. La hidrología y su papel en ingeniería del agua

    Directory of Open Access Journals (Sweden)

    Amanda García-Marín

    2014-07-01

    Full Text Available La Hidrología es una ciencia esencial en Ingeniería del Agua, la cual abarca un amplio abanico de temas de investigación que engloban los diversos estadios del agua en el ciclo Hidrológico, tanto en atmósfera, superficie y suelo. Con motivo del relanzamiento de la revista Ingeniería del Agua se presenta un breve artículo de carácter introductorio en el que se muestran algunas de la líneas de investigación actuales en Hidrología, dedicadas a lluvia, interceptación de agua por la vegetación, sensores en Hidrología, agua subterránea, entre otras. Dicha revisión no pretende ser exhaustiva, dado el tamaño limitado de este formato de publicación, sino motivar la publicación en Ingeniería del Agua de artículos dentro de la temática Hidrología.

  19. Estudio del mecanismo de falla de terraplenes debido a la infiltración de aguas lluvias mediante el monitoreo de presiones de poros y contenidos de agua

    OpenAIRE

    García, Edwin; Uchimura, Taro

    2008-01-01

    El presente artículo muestra experimentos realizados utilizando modelos a escala para estudiar el proceso de infiltración en terraplenes sometidos a aguas lluvias. Varios modelos a escala fueron construidos usando un suelo arenoso con alto contenido de finos; para aplicar la lluvia artificial y observar el proceso de infiltración del agua se utilizó un tubo de irrigación. Para monitorear los cambios en succión ocasionados por los ciclos de humedecimiento y secado se instalaron dentro del suel...

  20. Estudio del mecanismo de falla de terraplenes debido a la infiltración de aguas lluvias mediante el monitoreo de presiones de poros y contenidos de agua

    OpenAIRE

    EDWIN GARCÍA; TARO UCHIMURA

    2007-01-01

    El presente artículo muestra experimentos realizados utilizando modelos a escala para estudiar el proceso de infiltración en terraplenes sometidos a aguas lluvias. Varios modelos a escala fueron construidos usando un suelo arenoso con alto contenido de finos; para aplicar la lluvia artificial y observar el proceso de infiltración del agua se utilizó un tubo de irrigación. Para monitorear los cambios en succión ocasionados por los ciclos de humedecimiento y secado se instalaron den...

  1. EFECTOS DE LA PRIVACIÓN DE AGUA EN UN PROGRAMA DE REFORZAMIENTO IV 5' SOBRE EL PESO CORPORAL, EL CONSUMO DE AGUA Y ALIMENTO EN RATAS

    OpenAIRE

    Antonio López-Espinoza; Américo Ríos; Ma. Eugenia Soto

    2004-01-01

    Cuatro ratas fueron expuestas a un programa de privación de agua con 1 hora de acceso libre y 23 horas de privación en un programa de reforzamiento N 5; otras cuatro ratas fueron usadas como sujetos control. Laduración de los periodos de restricción fuede 30, 64, 25 Y 28 días con intervalos de libre acceso entre cadaunode ellos. El alimento se mantuvo en libreacceso durante todoel experimento. Los resultaron confirmaron que al retirar la privación de agua se modificó el patrón de alimentación...

  2. Pobreza, agua y tierra en Ambato, Ecuador: Perfil de pobreza y el acceso y manejo de agua y tierra en la cuenca de Ambato, Ecuador

    OpenAIRE

    Chapalbay, Washington; Cordero, Doris; Gómez, Ligia Ivette; Munk Ravnborg, Helle

    2007-01-01

    Este informe tiene coma objetivo presentar el perfil de pobreza para la cuenca del rio Ambato, la prov1ncia de Tungurahua, Ecuador, )' analizar en que medida el acceso al agua, particularmente para el riego, ya la tierra, depende de los niveles de pobreza. El manejo del agua es clave en la cuenca de Ambato, principalmente para la producci6n agricola. Con base en el perEl de pobreza, casi dos terceras partes de las familias tienen acceso al riego. De la misma forma, casi la totalidad de las fa...

  3. Estudio geoquímico de suelos y aguas como base para evaluar la contaminación: relación roca-suelo-agua

    OpenAIRE

    Vázquez Garranzo, Icíar

    2008-01-01

    Los objetivos generales del estudio de los suelos han sido, por un lado, establecer los valores de referencia de elementos traza a partir de la determinación de los valores de fondo y, por otro, demostrar las diferencias de disponibilidad entre el contenido de un elemento aportado al suelo y el contenido litogénico del mismo en suelo. Para el estudio de las aguas, los objetivos han sido: establecer la calidad química del agua en base a su comparación con indicadores de acuerdo con los req...

  4. La posible creación de mercados de agua y la gobernabilidad de este recurso en Colombia. Comentarios sobre el proyecto de ley del agua

    OpenAIRE

    Manuel Rodríguez Becerra

    2005-01-01

    En la actualidad se está tramitando un proyecto de Ley del Agua en el Congreso de la República, presentado a su consideración por el Gobierno Nacional, mediante el cual "se establecen medidas para orientar la planificación y administración del recurso hídrico en el territorio nacional." Se trata de la segunda reforma del gobierno del Presidente Alvaro Uribe relacionada con la gestión del agua en Colombia. En efecto, al principio de su gobierno se expidió la Ley de 2003 de creación del Ministe...

  5. Dispositivo electrónico de medición del caudal de agua para canales abiertos

    OpenAIRE

    Julio Cesar Ayala López; Roberto Albóniga Gil

    2015-01-01

    El método de riego por inundación, que desplaza el agua mediante canales abiertos y surcos ha sido usado durante años en la producción agrícola, aunque requiere una gran cantidad de agua y su eficacia no es muy alta ya que la mayoría del agua no se puede extraer directamente en las raíces de las plantas. Siendo de vital importancia lograr datos de campo confiables y lo suficientemente precisos que nos permitan estudiar y proyectar manejos del agua con el menor grado de incertidumbre posi...

  6. Normalización de la terminología mexicana sobre el agua Standardization of Mexican terminology on water

    OpenAIRE

    Catalina Naumis-Peña; Verónica Vargas-Suárez

    2009-01-01

    Se expone el resultado de una investigación llevada acabo para conocer el estado de la normalización terminológica en tesauros especializados que incluyen el agua dentro de sus áreas contratando los términos usados en la literatura mexicana. La documentación que se genera sobre el tema del agua en México crece en forma exponencial en tanto que la problemática del agua exige soluciones integrales. Actualmente no existe un tesauro, ni terminologías relacionadas con el tema del agua en México, n...

  7. Funciones agua rendimiento para 14 cultivos agrícolas en condiciones del sur de La Habana

    OpenAIRE

    Felicita González Robaina; Julián Herrera Puebla; Teresa López Seijas; Greco Cid Lazo

    2013-01-01

    El estudio de las funciones agua rendimiento y su uso dentro de la planificación del uso del agua es una vía importante para trazar estrategias de manejo que contribuyan al incremento en la producción agrícola. Utilizando los datos de consumo de agua, agua aplicada por riego, precipitaciones y los rendimientos obtenidos en más de 100 experimentos de campo realizados fundamentalmente en suelo Ferralítico Rojo de la zona sur de La Habana y con ayuda de herramientas de análisis de regresión en e...

  8. La lucha por el agua en el país de la lluvia (Galicia, siglos XVI-XIX)

    OpenAIRE

    Ofelia REY CASTELAO

    2013-01-01

    En este artículo se estudia la intensa conflictividad por el agua que se vivió en la Galicia de la Edad Moderna debido al déficit de aguas de riego durante el verano, y a los complejos sistemas de usufructo del agua para uso doméstico y agrícola. Para conocer las causas de los conflictos, su cronología, su distribución territorial y los grupos sociales que los protagonizaron, se utilizan escrituras notariales –sobre todo, poderes y concordias–, y los pleitos por aguas atendidos por la Real Au...

  9. Development of high performance catalyst for off-gas treatment system in BWR

    International Nuclear Information System (INIS)

    A high performance catalyst for off-gas treatment system in boiling water reactor (BWR) has been developed. The hydrogen concentration in the outlets of off-gas recombiners increased at several BWR plants in Japan. These phenomena were caused by deactivation of catalysts for the recombiners, and we assumed two types of deactivation mechanisms. The first cause was an increase of the amount of boehmite in the catalyst support due to alternation of the manufacturing process. The other cause was catalysts being poisoned by cyclic siloxanes that were introduced from the silicone sealant used in the upstream of the off-gas recombiners. The catalysts were manufactured by Pt adhering on alumina support. The conventional catalyst (CAT-A) used the aqueous solution of the chloroplatinic acid for adhesion of Pt. A dechlorination process by autoclave was applied to prevent the equipment at the downstream of the recombiners from stress corrosion cracking, but this process caused the support material to transform into boehmite. The boehmite-rich catalysts were deactivated more easily by organic silicon than gamma alumina-rich catalysts. Therefore, the CAT-A was replaced at many Japanese BWR plants by the improved catalyst (CAT-B), and their support was transformed into more stable gamma alumina by heating at 500degC. However, the siloxanes keep being detected in the off-gas though the source of siloxane had been removed and there still remain possibilities to deactivate the catalysts. Therefore, we have been developing high performance catalyst (CAT-C) that has higher activity and durability against poisoning. We investigated the properties of CAT-C by performance tests and instrumental analyses. The dependency of thermal output of nuclear reactor, and durability against siloxane poisoning were investigated. We found that CAT-C showed higher performance and better properties than CAT-B did. Moreover, we have been developing a modeling method to evaluate the hydrogen recombination

  10. Analysis of a German BWR core with TRACE/PARCS using different cross section sets

    Energy Technology Data Exchange (ETDEWEB)

    Hartmann, C., E-mail: Christoph.Hartmann@kit.edu [Karlsruhe Inst. of Tech. (KIT), Inst. for Neutron Physics and Reactor Technology (INR), Eggenstein-Leopoldshafen (Germany); Westinghouse Electric Germany GmbH, Mannheim (Germany); Sanchez, V.H. [Karlsruhe Inst. of Tech. (KIT), Inst. for Neutron Physics and Reactor Technology (INR), Eggenstein-Leopoldshafen (Germany); Tietsch, W. [Westinghouse Electric Germany GmbH, Mannheim (Germany)

    2011-07-01

    'Full text:' Coupled Thermal-hydraulic/Neutron-kinetic (TH/NK) simulations of Boiling Water Reactor transients require well validated and accurate simulation tools as well as appropriate cross sections (XS) libraries depending on the individual thermal hydraulic state parameters. Problem-dependent XS-sets for 3D core simulations are being generated mainly by well validated, fast running and user-friendly lattice codes such as Casco and Helios. At research institutions and universities, alternative tools to the commercial ones with full access to the source code as well as moderate cost are urgently needed. The Scale system is being developed and improved for lattice physics calculations of real core loading of Light Water Reactors (LWR). It represents a promising alternative to the commercial lattice codes. At Karlsruhe Institute of Technology (Kit) a computational route based on Scale/Triton/Newt for BWR core loading is under development. The generated XS-data sets have to be transformed in PMAXS-format for use in the reactor dynamic code PARCS. This task is performed by the module GenPMAXS being developed and tested at the Michigan University. To verify the computational route, a BWR fuel assembly depletion problem was calculated by PARCS and compared to the CASMO results. Since the SCALE/TRITON XS-file does actually not contain all required neutronic data, FORTRAN routines have been developed to incorporate the missing data e.g. the yields of Iodine, Xenon and Promethium into the XS-data sets in the PMAXS-format. The comparison of the results obtained with PARCS (using the corrected PMAXS file) and CASMO for the depletion problem exhibited a good agreement. Consequently, this approach was followed for the generation of a complete XS-set for a real BWR core to be used in subsequent transient analysis. Then 3D neutronic and thermal hydraulic core model were elaborated for a TRACE/PARCS analysis. The thermal hydraulic model is based on the 3D VESSEL

  11. Analysis of a German BWR core with TRACE/PARCS using different cross section sets

    International Nuclear Information System (INIS)

    'Full text:' Coupled Thermal-hydraulic/Neutron-kinetic (TH/NK) simulations of Boiling Water Reactor transients require well validated and accurate simulation tools as well as appropriate cross sections (XS) libraries depending on the individual thermal hydraulic state parameters. Problem-dependent XS-sets for 3D core simulations are being generated mainly by well validated, fast running and user-friendly lattice codes such as Casco and Helios. At research institutions and universities, alternative tools to the commercial ones with full access to the source code as well as moderate cost are urgently needed. The Scale system is being developed and improved for lattice physics calculations of real core loading of Light Water Reactors (LWR). It represents a promising alternative to the commercial lattice codes. At Karlsruhe Institute of Technology (Kit) a computational route based on Scale/Triton/Newt for BWR core loading is under development. The generated XS-data sets have to be transformed in PMAXS-format for use in the reactor dynamic code PARCS. This task is performed by the module GenPMAXS being developed and tested at the Michigan University. To verify the computational route, a BWR fuel assembly depletion problem was calculated by PARCS and compared to the CASMO results. Since the SCALE/TRITON XS-file does actually not contain all required neutronic data, FORTRAN routines have been developed to incorporate the missing data e.g. the yields of Iodine, Xenon and Promethium into the XS-data sets in the PMAXS-format. The comparison of the results obtained with PARCS (using the corrected PMAXS file) and CASMO for the depletion problem exhibited a good agreement. Consequently, this approach was followed for the generation of a complete XS-set for a real BWR core to be used in subsequent transient analysis. Then 3D neutronic and thermal hydraulic core model were elaborated for a TRACE/PARCS analysis. The thermal hydraulic model is based on the 3D VESSEL

  12. Optimization of fuel cells for BWR based in Tabu modified search; Optimizacion de celdas de combustible para BWR basada en busqueda Tabu modificada

    Energy Technology Data Exchange (ETDEWEB)

    Martin del Campo M, C.; Francois L, J.L. [Facultad de Ingenieria, UNAM, Laboratorio de Analisis en Ingenieria de Reactores Nucleares, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico); Palomera P, M.A. [Facultad de Ingenieria, UNAM, Posgrado en Ingenieria en Computacion, Circuito exterior s/n, Ciudad Universitaria, Mexico, D.F. (Mexico)]. e-mail: cmcm@fi-b.unam.mx

    2004-07-01

    The advances in the development of a computational system for the design and optimization of cells for assemble of fuel of Boiling Water Reactors (BWR) are presented. The method of optimization is based on the technique of Tabu Search (Tabu Search, TS) implemented in progressive stages designed to accelerate the search and to reduce the time used in the process of optimization. It was programed an algorithm to create the first solution. Also for to diversify the generation of random numbers, required by the technical TS, it was used the Makoto Matsumoto function obtaining excellent results. The objective function has been coded in such a way that can adapt to optimize different parameters like they can be the enrichment average or the peak factor of radial power. The neutronic evaluation of the cells is carried out in a fine way by means of the HELIOS simulator. In the work the main characteristics of the system are described and an application example is presented to the design of a cell of 10x10 bars of fuel with 10 different enrichment compositions and gadolinium content. (Author)

  13. Artificial intelligence applied to fuel management in BWR type reactors; Inteligencia artificial aplicada a la administracion de combustible en reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz S, J.J

    1998-10-01

    In this work two techniques of artificial intelligence, neural networks and genetic algorithms were applied to a practical problem of nuclear fuel management; the determination of the optimal fuel reload for a BWR type reactor. This is an important problem in the design of the operation cycle of the reactor. As a result of the application of these techniques, comparable or even better reloads proposals than those given by expert companies in the subject were obtained. Additionally, two other simpler problems in reactor physics were solved: the determination of the axial power profile and the prediction of the value of some variables of interest at the end of the operation cycle of the reactor. Neural networks and genetic algorithms have been applied to solve many problems of engineering because of their versatility but they have been rarely used in the area of fuel management. The results obtained in this thesis indicates the convenience of undertaking further work on this area and suggest the application of these techniques of artificial intelligence to the solution of other problems in nuclear reactor physics. (Author)

  14. Prediction of the stability of BWR reactors during the start-up process; Prediccion de la estabilidad de reactores BWR durante el proceso de arranque

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz E, J.A.; Castillo D, R. [ININ, Km. 36.5 Carretera Mexico-Toluca, 52045 Salazar, Estado de Mexico (Mexico); Blazquez M, J.B. [Centro de Investigaciones Energetics, Medioambientales y Tecnologicas, Av Complutense 22, 28040 Madrid (Spain)

    2004-07-01

    The Boiling Water Reactors (BWR) are susceptible of uncertainties of power when they are operated to low flows of coolant (W) and high powers (P), being presented this situation mainly in the start-up process. The start-up process could be made but sure if the operator knew the value of the stability index Decay reason (Dr) before going up power and therefore to guarantee the stability. The power and the flow are constantly measures, the index Dr could also be considered its value in real time. The index Dr depends on the power, flow and many other values, such as, the distribution of the flow axial and radial neutronic, the temperature of the feeding water, the fraction of holes and other thermohydraulic and nuclear parameters. A simple relationship of Dr is derived leaving of the pattern reduced of March-Leuba, where three independent variables are had that are the power, the flow and a parameter that it contains the rest of the phenomenology, that is to say all the other quantities that affect the value of Dr. This relationship developed work presently and verified its prediction with data of start-up of commercial reactors could be used for the design of a practical procedure practice of start-up, what would support to the operator to prevent this type of events of uncertainty. (Author)

  15. SUN-RAH: a nucleoelectric BWR university simulator based in reduced order models; SUN-RAH: simulador universitario de nucleoelectrica BWR basado en modelos de orden reducido

    Energy Technology Data Exchange (ETDEWEB)

    Morales S, J.B.; Lopez R, A.; Sanchez B, A.; Sanchez S, R.; Hernandez S, A. [DEPFI, Campus Morelos, en IMTA Jiutepec, Morelos (Mexico)]. e-mail: jms0620@yahoo.com

    2003-07-01

    The development of a simulator that allows to represent the dynamics of a nucleo electric central, with nuclear reactor of the BWR type, using reduced order models is presented. These models present the characteristics defined by the dominant poles of the system (1) and most of those premature operation transitories in a power station can be reproduced with considerable fidelity if the models are identified with data of plant or references of a code of better estimate like RAMONA, TRAC (2) or RELAP. The models of the simulator are developments or own simplifications starting from the physical laws and retaining the main terms. This work describes the objective of the project and the general specifications of the University student of Nucleo electric simulator with Boiling Water Reactor type (SUN-RAH) as well as the finished parts that fundamentally are the nuclear reactor, the one of steam supply (NSSS), the plant balance (BOP), the main controllers of the plant and the implemented graphic interfaces. The pendent goals as well as the future developments and applications of SUN-RAH are described. (Author)

  16. Dynamic reconstruction and Lyapunov experiments from time series data in boiling water reactors. Application to B.W.R. stability analysis

    International Nuclear Information System (INIS)

    This paper shows how to obtain Lyapunov exponents from time series data on Boiling Water Reactor (BWR) stability. In order to validate the method, these characteristic exponents are compared with the ones obtained directly from the governing equations of the dynamic system. Finally, we present a method for obtaining the stability of the B.W.R. from Lyapunov exponents and describe some other applications related to limit cycles. (Author)

  17. Ahorro de agua y materia prima en los procesos de pelambre y curtido del cuero mediante precipitación y recirculación de aguas

    Directory of Open Access Journals (Sweden)

    SANDRA AGUDELO A.

    2007-01-01

    Full Text Available El principio del proceso de recuperación de cromo, consiste en precipitar el cromo contenido en el licor residual como hidróxido utilizando un álcali; este precipitado se separa por sedimentación y se disuelve nuevamente con ácido sulfúrico. De los resultados obtenidos, se observaron porcentajes de remoción superiores al 99%. Con la recirculación directa de aguas de pelambre fue posible obtener ahorros de agua del 64% y ahorros en materia prima del 32 %, además, con una adecuada selección del tamizador es posible recircular el agua un número máximo de tres veces, sin afectar la calidad del producto final. Así mismo, se comprobó la viabilidad de la recirculación directa de aguas de curtido, con ahorros de materia prima del 17%. Con medidas de este tipo, prácticas y fáciles de implementar, la industria del curtido del cuero podría disminuir considerablemente la contaminación, operar de una forma mas segura y con mayor eficiencia de producción.

  18. La posible creación de mercados de agua y la gobernabilidad de este recurso en Colombia. Comentarios sobre el proyecto de ley del agua

    Directory of Open Access Journals (Sweden)

    Manuel Rodríguez Becerra

    2005-11-01

    Full Text Available En la actualidad se está tramitando un proyecto de Ley del Agua en el Congreso de la República, presentado a su consideración por el Gobierno Nacional, mediante el cual "se establecen medidas para orientar la planificación y administración del recurso hídrico en el territorio nacional." Se trata de la segunda reforma del gobierno del Presidente Alvaro Uribe relacionada con la gestión del agua en Colombia. En efecto, al principio de su gobierno se expidió la Ley de 2003 de creación del Ministerio del Ambiente, Vivienda y Desarrollo Territorial (MAVDT, a partir del anterior Ministerio del Medio Ambiente, al cual se le trasladaron las funciones de vivienda, agua potable, saneamiento básico y desarrollo territorial, antes en cabeza del Ministerio de Desarrollo que se clausuró. Este ensayo tiene como objetivo hacer un examen de algunos aspectos críticos del proyecto de ley, tal como fue aprobado en primer debate en al Comisión Quinta de la Cámara de Representantes, y también efectuar algunas consideraciones sobre la marcha del MAVDT como autoridad nacional del agua, debido a que ambas reformas están encaminadas a fortalecer la gobernabilidad de este recurso en Colombia.

  19. La competencia por el agua en el valle de Izúcar, Puebla. Los repartimientos de agua y los ingenios, 1550-1650

    Directory of Open Access Journals (Sweden)

    Gloria Camacho Pichardo

    2010-01-01

    Full Text Available El eje principal de este artículo consiste en analizar el proceso de adquisición de derechos, distribución y uso del agua por parte de los labradores españoles e indígenas, en torno al río Nexapa en el valle de Izúcar, Puebla, entre 1550 y 1650, en un período de expansión de la propiedad de los españoles, de la introducción de nuevos cultivos que implicaban riego y de una baja considerable de población indígena. Se analizan los conflictos entre los regantes de aguas arriba con los de aguas abajo, así como las formas de solucionar las tensiones a través de los diversos repartimientos de agua en torno al Nexapa, como instrumento que les permitió a los regantes "resolver" sus diferencias.

  20. Assessment of hydrogen combustion effects in the BWR/6 - Mark III Standard Plant

    International Nuclear Information System (INIS)

    This report discusses General Electric's study of potential hydrogen combustion effects on the Standard Mark III containment during postulated severe accidents. This study was performed as part of the Probabilistic Risk Assessment of the BWR/6 - Mark III Standard Plant. The methodology of determining the accident event sequence and modeling of the Boiling Water Reactor core response, including hydrogen generation by metal-water reaction, is described. Combustion of hydrogen released to the containment is analyzed and effects on the Mark III containment system are assessed. It is concluded that even for those cases where containment integrity may be lost, the containment function (i.e., limiting offsite doses) is maintained by the drywell and suppression pool

  1. Calculation of activity content and related properties in PWR and BWR fuel using ORIGEN 2

    International Nuclear Information System (INIS)

    This report lists the conditions for calculations of the core inventory for a PWR and BWR. The calculations have been performed using the computer code ORIGEN 2. The amount (grams), the total radioactivity (bequerels), the thermal power (watts), the radioactivity from theα-decay (bequerels), and the neutron emission (neutrons/sec) from the core after the last burnup have been determined. All the parameters have been calculated as a function of the burnup and the natural decay, the latter over a time period of 0-1.0E07 years. The calculations have been performed for 68 heavy nuclides, 60 daughter nuclides, to the heavy nuclides with atomic numbers under 92, 852 fission products and 7 light nucli ides. The most important results are listed. (author)

  2. Kuosheng BWR/6 containment pressure and temperature responses after recirculation line break using GOTHIC code

    International Nuclear Information System (INIS)

    In this study, we presented the calculated results of the containment P/T (pressure and temperature) response after the recirculation line break (RCLB) accident of a GE-designed twin-unit BWR/6 plant, which can be served as the design basis for the containment system. During the simulation, a power of SPU (stretch power uprate) range was used and a model of the Mark III type containment was built using the GOTHIC (Generation of Thermal-Hydraulic Information for Containments) code. The calculated results, similar to the FSAR (Final Safety Analysis Report) results, indicate the GOTHIC code has the capability to simulate the containment P/T response to the RCLB accident. (author)

  3. Critical experiments for BWR fuel assemblies with cluster of gadolinia rods

    International Nuclear Information System (INIS)

    Gadolinia-bearing fuel rods are needed for high-burnup fuels. Strong neutron absorption of gadolinia makes an assembly heterogeneous from the viewpoint of reactor physics. The cluster of gadolinia-bearing fuel rods is useful for higher-burnup fuels than current fuels. Few critical experiments have been reported for fuel assemblies with the cluster of gadolinia-bearing fuel rods. We conducted critical experiments for BWR fuel assemblies with the cluster of gadolinia-bearing fuel rods in the Toshiba Nuclear Critical Assembly (NCA). Critical water level and power distribution were measured. Measurements were compared with analyses by a continuous-energy Monte Carlo code, MCNP, with the JENDL3.3 nuclear data library. (author)

  4. Taking burnup credit for interim storage and transportation system for BWR fuels

    International Nuclear Information System (INIS)

    In order to establish a realistic burnup credit design system, a calculation system has been developed for determining isotope compositions, burnup, and criticality. The calculation system consists of several modules such as TGBLA, ORIGEN, CITATION, MCNP, and KENO. The TGBLA code is a fuel design code for LWR fuels developed in TOSHIBA Corporation. A compact measurement system for a fuel assembly has been being developed to meet requirements for the burnup determination, the neutron emission-rate evaluation, and the nuclear materials management. For a spent MOX fuel, a neutron emission rate measurement method has been being developed. The system consists of Cd-Te detectors and / or fission chambers. Some model calculations were carried out for the latest design BWR fuels. The effect of taking burnup credit for a transportation cask is shown. (authors)

  5. Microstructure in cast stainless steel used for long-term in BWR environment

    International Nuclear Information System (INIS)

    Microstructure in a cast stainless steel used for a PLR pump casing cover in a BWR was investigated by atom probe tomography and nanoindentation testing. Ferrite phase decomposition and G-phase precipitation were not observed in the as-received PLRP casing cover. Thermal aging and solution treatment were carried out on the as-received PLRP casing cover and an unused model alloy of cast stainless steel. The ferrite phase decomposition and G-phase precipitates in the thermal aged model alloy disappeared after the solution treatment, and the nanoindentation hardness in the ferrite phase was recovered. Changes in the microstructures were almost the same between the PLRP casing cover and the model alloy after the thermal aging and the solution treatment. The effect of thermal aging on the as-received material was considered to be very little in service. (author)

  6. Analysis Applied Multivariate to the Studies of Stability in the Reactors BWR

    International Nuclear Information System (INIS)

    Presently work is presented the application of the analysis multivariate in the studies of stability of reactors BWR. For the confirmation of the applicability of the method of Hilbert Huang is used a group of series acquired neutronic during an outburst in the power station nuclear of Cofrentes. The peculiarity of the analyzed data is that they are not stationary and contaminated by the performance of other systems of the plant, for that that when applying the methods traditional autoregressive to these data, is values non realists of the DR In the work the DR is compared obtained by the methodology presented with the true DR and with the one obtained starting from the application of methods autoregressive to the original sign. The conclusion is evident, the value of the DR obtained by the methodology explained in this work is next to the one True DR that the resulting DR of the application of the method AR to the original sign

  7. State of the art of second international exercise on benchmarks in BWR reactors

    International Nuclear Information System (INIS)

    This is a second in series of Benchmarks based on data from operating Swedish BWRs. The first one concerned measurements made in cycles 14,15 16 and 17 at Ringhals 1 Nuclear Power Plant and addressed predictive power of analytical tools used in BWR stability analysis. Part of the data was disclosed only after participants had provided their results. This work has been published in the report: NEA/NSC/DOC(96)22, November 1996. In this report it was recognised that there is a need for better qualification of the applied noise analysis methods. A follow up Benchmark was thus proposed dedicated to the analysis of time series data and including the evaluation of both global and regional stability of Forsmarks 1 and 2 Nuclear Power Plant. In this second Benchmark have participated Forsmarks Kraftgrupp AB,NEA Nuclear Science Committee, CSN Consejo de Seguridad Nuclear and Department of Chemical and Nuclear Engineering of Polytechnic University of Valencia. (Author)

  8. Study of transient rod extraction failure without RBM in a BWR

    International Nuclear Information System (INIS)

    The study and analysis of the operational transients are important for predicting the behavior of a system to short-term events and the impact that would cause this transient. For the nuclear industry these studies are indispensable due to economic, environmental and social impacts that could cause an accident during the operation of a nuclear reactor. In this paper the preparation, simulation and analysis results of the transient rod extraction failure in which not taken into operation the RBM is presented. The study was conducted for a BWR of 2027 MWt, in an intermediate cycle of its useful life and using the computer code Simulate-3K a scenario of anomalies was created in the core reactivity which gave a coherent prediction to the type of presented event. (Author)

  9. Non-local two phase flow momentum transport in S BWR

    International Nuclear Information System (INIS)

    The non-local momentum transport equations derived in this work contain new terms related with non-local transport effects due to accumulation, convection, diffusion and transport properties for two-phase flow. For instance, they can be applied in the boundary between a two-phase flow and a solid phase, or in the boundary of the transition region of two-phase flows where the local volume averaging equations fail. The S BWR was considered to study the non-local effects on the two-phase flow thermal-hydraulic core performance in steady-state, and the results were compared with the classical local averaging volume conservation equations. (Author)

  10. Sphere-pac versus pellet UO2 fuel in de Dodewaard BWR

    International Nuclear Information System (INIS)

    Comparative testing of UO2 sphere-pac and pellet fuel rods under LWR conditions has been jointly performed by the Netherlands Utilities Research Centre (KEMA) in Arnhem, the Netherlands Energy Research Foundation (ECN) at Petten and the Netherlands Joint Nuclear Power Utility (GKN) at Dodewaard. This final report summarizes the highlights of this 1968-1988 program with strong emphasis on the fuel rods irradiated in the Dodewaard BWR. The conclusion reached is that under normal LWR conditions sphere-pac UO2 in LWR fuel rods offers better resistance against stress corrosion cracking of the cladding, but that under fast, single step, power ramping conditions pellet UO2 in LWR fuel rods has a better resistance against hoop stress failure of the cladding. 128 figs., 36 refs., 19 tabs

  11. Optimization of fuel reloads for a BWR using the ant colony system

    International Nuclear Information System (INIS)

    In this work some results obtained during the development of optimization systems are presented, which are employees for the fuel reload design in a BWR. The systems use the ant colony optimization technique. As first instance, a system is developed that was adapted at travel salesman problem applied for the 32 state capitals of Mexican Republic. The purpose of this implementation is that a similarity exists with the design of fuel reload, since the two problems are of combinatorial optimization with decision variables that have similarity between both. The system was coupled to simulator SIMULATE-3, obtaining good results when being applied to an operation cycle in equilibrium for reactors of nuclear power plant of Laguna Verde. (Author)

  12. Revised uranium--plutonium cycle PWR and BWR models for the ORIGEN computer code

    Energy Technology Data Exchange (ETDEWEB)

    Croff, A. G.; Bjerke, M. A.; Morrison, G. W.; Petrie, L. M.

    1978-09-01

    Reactor physics calculations and literature searches have been conducted, leading to the creation of revised enriched-uranium and enriched-uranium/mixed-oxide-fueled PWR and BWR reactor models for the ORIGEN computer code. These ORIGEN reactor models are based on cross sections that have been taken directly from the reactor physics codes and eliminate the need to make adjustments in uncorrected cross sections in order to obtain correct depletion results. Revised values of the ORIGEN flux parameters THERM, RES, and FAST were calculated along with new parameters related to the activation of fuel-assembly structural materials not located in the active fuel zone. Recommended fuel and structural material masses and compositions are presented. A summary of the new ORIGEN reactor models is given.

  13. BWR core thermal-hydraulic stability in anticipated transients without SCRAM

    International Nuclear Information System (INIS)

    The potential exists for core thermal hydraulic density wave oscillations to occur in the boiling water reactor (BWR) during anticipated transients without scram (ATWS) events. Conditions which may lead to oscillations in ATWS result either from recirculation pump trip (RPT) from appropriate ATWS signals, or from the failure to scram during core oscillations. A program to evaluate these scenarios will assess the adequacy of the system design and emergency operating procedures relative to the reactor system performance. Evaluation of ATWS events with oscillations is extremely complex, and defining the bases for the analyses is critical to the success of the program. Accurate analysis requires detailed modeling of the sequence of events, the plant configuration, and initial conditions

  14. Experimental simulation of the water cooling of corium spread over the floor of a BWR containment

    Energy Technology Data Exchange (ETDEWEB)

    Morage, F.; Lahey, R.T. Jr.; Podowski, M.Z. [Rensselaer Polytechnic Institute, Troy, NY (United States)

    1995-09-01

    This paper is concerned with an experimental investigation of the cooling effect of water collected on the surface of corium released onto the floor of a BWR drywell. In the present experiments, the actual reactor materials were replaced by simulant materials. Specifically, the results are shown for Freon-11 film boiling over liquid Wood`s metal spread above a solid porous surface through which argon gas was injected. An analysis of the obtained experimental data revealed that the actual film boiling heat transfer between a molten pool of corium and the water above the pool should be more efficient than predicted by using standard correlations for boiling over solid surfaces. This effect will be further augmented by the gas released due to the ablation of concrete floor beneath the corium and percolating towards its upper surface and into through the water layer above.

  15. BUTREN-RC an hybrid system for the recharges optimization of nuclear fuels in a BWR

    International Nuclear Information System (INIS)

    The obtained results with the hybrid system BUTREN-RC are presented that obtains recharges of nuclear fuel for a BWR type reactor. The system has implemented the methods of optimization heuristic taboo search and neural networks. The optimization it carried out with the technique of taboo search, and the neural networks, previously trained, were used to predict the behavior of the recharges of fuel, in substitution of commercial codes of reactor simulation. The obtained recharges of nuclear fuel correspond to 5 different operation cycles of the Laguna Verde Nuclear Power plant, Veracruz in Mexico. The obtained results were compared with the designs of this cycles. The energy gain with the recharges of fuel proposals is of approximately 4.5% with respect to those of design. The time of compute consumed it was considerably smaller that when a commercial code for reactor simulation is used. (Author)

  16. Non-local two phase flow momentum transport in S BWR

    Energy Technology Data Exchange (ETDEWEB)

    Espinosa P, G.; Salinas M, L.; Vazquez R, A., E-mail: gepe@xanum.uam.mx [Universidad Autonoma Metropolitana, Unidad Iztapalapa, Area de Ingenieria en Recursos Energeticos, Apdo. Postal 55-535, 09340 Ciudad de Mexico (Mexico)

    2015-09-15

    The non-local momentum transport equations derived in this work contain new terms related with non-local transport effects due to accumulation, convection, diffusion and transport properties for two-phase flow. For instance, they can be applied in the boundary between a two-phase flow and a solid phase, or in the boundary of the transition region of two-phase flows where the local volume averaging equations fail. The S BWR was considered to study the non-local effects on the two-phase flow thermal-hydraulic core performance in steady-state, and the results were compared with the classical local averaging volume conservation equations. (Author)

  17. Comparison of trial seismic PSA and seismic margin analysis for a BWR

    International Nuclear Information System (INIS)

    A case study of seismic PSA (SPSA) and seismic margin analysis (SMA) for a Japanese standard BWR was performed, and their results were compared. The SPSA results showed that dominant contributors were common cause random failure and seismic failure of several components and that random failure had a large portion of contribution to core damage frequency (CDF). On the other hand, the SMA results showed that dominant contributors were seismic failure of several components. The dominantly contributing seismic acceleration region was around (0.6 - 2.5) x S2 level in SPSA, while the SMA results gave a plant HCLPF capacity of about 2.5 x S2 level, which was larger than the contributing acceleration region in SPSA. Dominant accident sequences obtained were almost the same in SPSA and SMA. (author)

  18. A methodology for obtaining the control rod patterns in a BWR using genetic algorithms

    International Nuclear Information System (INIS)

    In this work the GACRP system based on the genetic algorithms technique for the obtaining of the drivers of control bars in a BWR reactor is presented. This methodology was applied to a transition cycle and a one of balance of the Laguna Verde nuclear power station (CNLV). For each one of the studied cycles, it was executed the methodology with a fixed length of the cycle and it was compared the effective multiplication factor of neutrons at the end of the cycle that it is obtained with the proposed drivers of control bars and the multiplication factor of neutrons obtained by means of a Haling calculation. It was found that it is possible to extend several days the length of both cycles with regard to the one Haling calculation. (Author)

  19. Development of a parametric containment event tree model for a severe BWR accident

    Energy Technology Data Exchange (ETDEWEB)

    Okkonen, T. [OTO-Consulting Ay, Helsinki (Finland)

    1995-04-01

    A containment event tree (CET) is built for analysis of severe accidents at the TVO boiling water reactor (BWR) units. Parametric models of severe accident progression and fission product behaviour are developed and integrated in order to construct a compact and self-contained Level 2 PSA model. The model can be easily updated to correspond to new research results. The analyses of the study are limited to severe accidents starting from full-power operation and leading to core melting, and are focused mainly on the use and effects of the dedicated severe accident management (SAM) systems. Severe accident progression from eight plant damage states (PDS), involving different pre-core-damage accident evolution, is examined, but the inclusion of their relative or absolute probabilities, by integration with Level 1, is deferred to integral safety assessments. (33 refs., 5 figs., 7 tabs.).

  20. Development of neural network simulating power distribution of a BWR fuel bundle

    International Nuclear Information System (INIS)

    A neural network model is developed to simulate the precise nuclear physics analysis program code for quick scoping survey calculations. The relation between enrichment and local power distribution of BWR fuel bundles was learned using two layers neural network (ENET). A new model is to introduce burnable neutron absorber (Gadolinia), added to several fuel rods to decrease initial reactivity of fresh bundle. The 2nd stages three layers neural network (GNET) is added on the 1st stage network ENET. GNET studies the local distribution difference caused by Gadolinia. Using this method, it becomes possible to survey of the gradients of sigmoid functions and back propagation constants with reasonable time. Using 99 learning patterns of zero burnup, good error convergence curve is obtained after many trials. This neural network model is able to simulate no learned cases fairly as well as the learned cases. Computer time of this neural network model is about 100 times faster than a precise analysis model. (author)

  1. Application of expert system and neural network in diagnosis during BWR ATWS sequences

    International Nuclear Information System (INIS)

    A prototype operator aid system employing an expert system and neural network is designed to help the plant operator during a BWR ATWS accident. The expert system is the driver of the inference engine, it consists of IF -- THEN -- and DO -- format rules developed from the knowledge base. A back propagation neural network is used when the operator can not supply the needed information to the expert system. Data of various plant parameters are fed into a pretrained neural network for transient identification. The case signature is then fed into the expert system, where a decision is made regarding the proper operator response. Testing results show that the neural network can retrieve the transients correctly even when random noise is added or the input data is incomplete. The computer simulation of the integrated system has also been demonstrated

  2. Composition and Distribution of Tramp Uranium Contamination on BWR and PWR Fuel Rods

    International Nuclear Information System (INIS)

    In a joint research project of VGB and AREVA NP GmbH the behaviour of alpha nuclides in nuclear power plants with light water reactors has been investigated. Understanding the source and the behaviour of alpha nuclides is of big importance for planning radiation protection measures for outages and upcoming dismantling projects. Previous publications have shown the correlation between plant specific alpha contamination of the core and the so called 'tramp fuel' or 'tramp uranium' level which is linked to the defect history of fuel assemblies and accordingly the amount of previously washed out fuel from defective fuel rods. The methodology of tramp fuel estimation is based on fission product concentrations in reactor coolant but also needs a good knowledge of tramp fuel composition and in-core distribution on the outer surface of fuel rods itself. Sampling campaigns of CRUD deposits of irradiated fuel assemblies in different NPPs were performed. CRUD analyses including nuclide specific alpha analysis have shown systematic differences between BWR and PWR plants. Those data combined with literature results of fuel pellet investigations led to model improvements showing that a main part of fission products is caused by fission of Pu-239 an activation product of U-238. CRUD investigations also gave a better picture of the in-core composition and distribution of the tramp uranium contamination. It was shown that the tramp uranium distribution in PWR plants is time dependent. Even new fuel assemblies will be notably contaminated after only one cycle of operation. For PWR applies the following logic: the higher the local power the higher the contamination. With increasing burnup the local rod power usually decreases leading to decreasing tramp uranium contamination on the fuel rod surface. This is not applicable for tramp uranium contamination in BWR. CRUD contamination (including the tramp fuel deposits) is much more fixed and is constantly increasing

  3. Considerations in small-scale modeling of pool swell in BWR containments

    Energy Technology Data Exchange (ETDEWEB)

    Huber, P.W.; Sonin, A.A.; Anderson, W.G.; Burke, R.P.; Ruggieri, N.G.

    1979-11-01

    Experiments were conducted in a laboratory scale test system to study limitations to the hydrodynamic scaling laws used in reduced scale simulations of BWR pool swell. Detailed experimental records of pool swell are presented. Predictions from a one-dimensional pool swell model are compared with results from small scale pool swell tests. The main elements of the model other than the geometric simplification are identical to the assumptions that underlie the hydrodynamic scaling laws investigated in the pool swell experiments. Based on a simple model for the vent flow and pool swell processes, calculations are performed to illustrate the effects that mis-scaling of vent volume and orifice placement can have on typical small-scale pool swell simulations in single-vent systems.

  4. Considerations in small-scale modeling of pool swell in BWR containments

    International Nuclear Information System (INIS)

    Experiments were conducted in a laboratory scale test system to study limitations to the hydrodynamic scaling laws used in reduced scale simulations of BWR pool swell. Detailed experimental records of pool swell are presented. Predictions from a one-dimensional pool swell model are compared with results from small scale pool swell tests. The main elements of the model other than the geometric simplification are identical to the assumptions that underlie the hydrodynamic scaling laws investigated in the pool swell experiments. Based on a simple model for the vent flow and pool swell processes, calculations are performed to illustrate the effects that mis-scaling of vent volume and orifice placement can have on typical small-scale pool swell simulations in single-vent systems

  5. Thermal hydraulics characterization of the core and the reactor vessel type BWR

    International Nuclear Information System (INIS)

    The thermal hydraulics design of a reactor type BWR 5 as the employees in the nuclear power plant of Laguna Verde involves the coupling of at least six control volumes: Pumps jet region, Stratification region, Core region, Vapor dryer region, Humidity separator region and Reactor region. Except by the regions of the core and reactor, these control volumes only are used for design considerations and their importance as operative data source is limited. It is for that is fundamental to complement the thermal hydraulics relations to obtain major data that allow to determine the efficiency of internal components, such as pumps jet, humidity separator and vapor dryer. Like example of the previous thing, calculations are realized on the humidity of the principal vapor during starting, comparing it with the values at the moment incorporated in the data banks of the computers of process of both units. (Author)

  6. Safety/relief valve quencher loads: evaluation for BWR Mark II and III containments

    Energy Technology Data Exchange (ETDEWEB)

    Su, T.M.

    1982-10-01

    Boiling water reactor (BWR) plants are equipped with safety/relief valves (SRVs) to protect the reactor from overpressurization. Plant operational transients, such as turbine trips, will actuate the SRV. Once the SRV opens, the air column within the partially submerged discharge line is compressed by the high-pressure steam released from the reactor. The compressed air discharged into the suppression pool produces high-pressure bubbles. Oscillatory expansion and contraction of these bubbles create hydrodynamic loads on the containment structures, piping, and equipment inside containment. This report presents the results of the staff's evaluation of SRV loads. The evaluation, however, is limited to the quencher devices used in Mark II and III containments. With respect to Mark I containments, the SRV acceptance criteria are presented in NUREG-0661 issued July 1980. The staff acceptance criteria for SRV loads for Mark II and III containments are presented in this report.

  7. Modeling of BWR core meltdown accidents - for application in the MELRPI.MOD2 computer code

    International Nuclear Information System (INIS)

    This report summarizes improvements and modifications made in the MELRPI computer code. A major difference between this new, updated version of the code, called MELRPI.MOD2, and the one reported previously, concerns the inclusion of a model for the BWR emergency core cooling systems (ECCS). This model and its computer implementation, the ECCRPI subroutine, account for various emergency injection modes, for both intact and rubblized geometries. Other changes to MELRPI deal with an improved model for canister wall oxidation, rubble bed modeling, and numerical integration of system equations. A complete documentation of the entire MELRPI.MOD2 code is also given, including an input guide, list of subroutines, sample input/output and program listing

  8. Real time simulation of the main steam system of a BWR nuclear power station

    International Nuclear Information System (INIS)

    This paper presents a real time model of the main steam system for a BWR 675 MW power plant unit. The model includes the start up and shut down of the system, where the steam flow is very small or non existent and phenomena like condensation can occur, changing drastically the effects observed from those of normal operation at medium or high loads. Severe transients are also contemplated. Consistency and stability tests were done to the model, and it was validated for steady state using plant design data. During transients the model's results were compared with the predictions of the Final Safety Analysis Report (FSAR) for the prototype unit, and it was found that the model's response follow the expected trends

  9. CAE advanced reactor demonstrators for CANDU, PWR and BWR nuclear power plants

    International Nuclear Information System (INIS)

    CAE, a private Canadian company specializing in full scope flight, industrial, and nuclear plant simulators, will provide a license to IAEA for a suite of nuclear power plant demonstrators. This suite will consist of CANDU, PWR and BWR demonstrators, and will operate on a 486 or higher level PC. The suite of demonstrators will be provided to IAEA at no cost to IAEA. The IAEA has agreed to make the CAE suite of nuclear power plant demonstrators available to all member states at no charge under a sub-license agreement, and to sponsor training courses that will provide basic training on the reactor types covered, and on the operation of the demonstrator suite, to all those who obtain the demonstrator suite. The suite of demonstrators will be available to the IAEA by March 1997. (author)

  10. Semi-automated proper orthogonal decomposition reduced order model non-linear analysis for future BWR stability

    International Nuclear Information System (INIS)

    Highlights: • Techniques within the field of ROMing based on POD are reviewed regarding “well-behaved” applications. • A systematic, general, mostly automated, reduction methodology based on POD is derived. • It is applicable for many classes of dynamical problems including the envisioned BWR application. • Robustness of this approach is demonstrated by a “pathological” test example. • The derived ROM accurately predicts dynamics of transients not included in the data set. - Abstract: Thermal–hydraulic coupling between power, flow rate and density, intensified by neutronics feedback are the main drivers determining the stability behavior of a boiling water reactor (BWR). High-power low-flow conditions in connection with unfavorable power distributions can lead the BWR system into unstable regions where power oscillations can be triggered. This important threat to operational safety requires careful analysis for proper understanding. Current design rules assure admissible operation conditions by exclusion regions determined by numerical calculations and analytical methods based on non-linear states for specific transients. Analyzing an exhaustive parameter space of the non-linear BWR system becomes feasible with methodologies based on reduced order models (ROMs), saving computational cost and improving the physical understanding. A new self-contained methodology is developed, based on the general general proper orthogonal decomposition (POD) reduction technique. It is mostly automated, applicable for generic partial differential equation (PDE) systems, and reduces them in a grid-free manner to a small ordinary differential equation (ODE) system able to capture even non-linear dynamics. This allows a much more extensive analysis of the represented physical system. Symbolic mathematical manipulations are performed automatically by Mathematica routines. A novel and general calibration roadmap is proposed which simplifies choices on specific POD

  11. Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in BWR Environments

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Y. [Argonne National Lab. (ANL), Argonne, IL (United States); Chopra, O. K. [Argonne National Lab. (ANL), Argonne, IL (United States); Gruber, Eugene E. [Argonne National Lab. (ANL), Argonne, IL (United States); Shack, William J. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2010-06-01

    The internal components of light water reactors are exposed to high-energy neutron irradiation and high-temperature reactor coolant. The exposure to neutron irradiation increases the susceptibility of austenitic stainless steels (SSs) to stress corrosion cracking (SCC) because of the elevated corrosion potential of the reactor coolant and the introduction of new embrittlement mechanisms through radiation damage. Various nonsensitized SSs and nickel alloys have been found to be prone to intergranular cracking after extended neutron exposure. Such cracks have been seen in a number of internal components in boiling water reactors (BWRs). The elevated susceptibility to SCC in irradiated materials, commonly referred to as irradiation-assisted stress corrosion cracking (IASCC), is a complex phenomenon that involves simultaneous actions of irradiation, stress, and corrosion. In recent years, as nuclear power plants have aged and irradiation dose increased, IASCC has become an increasingly important issue. Post-irradiation crack growth rate and fracture toughness tests have been performed to provide data and technical support for the NRC to address various issues related to aging degradation of reactor-core internal structures and components. This report summarizes the results of the last group of tests on compact tension specimens from the Halden-II irradiation. The IASCC susceptibility of austenitic SSs and heat-affected-zone (HAZ) materials sectioned from submerged arc and shielded metal arc welds was evaluated by conducting crack growth rate and fracture toughness tests in a simulated BWR environment. The fracture and cracking behavior of HAZ materials, thermally sensitized SSs and grain-boundary engineered SSs was investigated at several doses (≤3 dpa). These latest results were combined with previous results from Halden-I and II irradiations to analyze the effects of neutron dose, water chemistry, alloy compositions, and welding and processing conditions on IASCC

  12. An efficient modeling method for thermal stratification simulation in a BWR suppression pool

    Energy Technology Data Exchange (ETDEWEB)

    Haihua Zhao; Ling Zou; Hongbin Zhang; Hua Li; Walter Villanueva; Pavel Kudinov

    2012-09-01

    The suppression pool in a BWR plant not only is the major heat sink within the containment system, but also provides major emergency cooling water for the reactor core. In several accident scenarios, such as LOCA and extended station blackout, thermal stratification tends to form in the pool after the initial rapid venting stage. Accurately predicting the pool stratification phenomenon is important because it affects the peak containment pressure; and the pool temperature distribution also affects the NPSHa (Available Net Positive Suction Head) and therefore the performance of the pump which draws cooling water back to the core. Current safety analysis codes use 0-D lumped parameter methods to calculate the energy and mass balance in the pool and therefore have large uncertainty in prediction of scenarios in which stratification and mixing are important. While 3-D CFD methods can be used to analyze realistic 3D configurations, these methods normally require very fine grid resolution to resolve thin substructures such as jets and wall boundaries, therefore long simulation time. For mixing in stably stratified large enclosures, the BMIX++ code has been developed to implement a highly efficient analysis method for stratification where the ambient fluid volume is represented by 1-D transient partial differential equations and substructures such as free or wall jets are modeled with 1-D integral models. This allows very large reductions in computational effort compared to 3-D CFD modeling. The POOLEX experiments at Finland, which was designed to study phenomena relevant to Nordic design BWR suppression pool including thermal stratification and mixing, are used for validation. GOTHIC lumped parameter models are used to obtain boundary conditions for BMIX++ code and CFD simulations. Comparison between the BMIX++, GOTHIC, and CFD calculations against the POOLEX experimental data is discussed in detail.

  13. Influence of iron and nickel species upon activity buildup under simulated BWR conditions

    Energy Technology Data Exchange (ETDEWEB)

    Bjornsson, S.; Chen, J. [Studsvik Nuclear AB, Nykoping (Sweden); Lejon, J. [OKG AB, Oskarshamn (Sweden); Granath, G. [Ringhals AB, Varobacka (Sweden); Tanse-Larsson, M. [Forsmarks Kraftgrupp AB, Osthammar (Sweden)

    2010-07-01

    Activity build-up in BWR systems are of importance for service- and maintenance work performed at the plants. Minimizing the activity build-up is desirable for minimizing doses of personnel at the plants. Numerous studies have been carried out in this important field to understand the activity uptake mechanisms. This paper studied the possible role of Fe(II/III) and Ni(II) impurities in reactor water in activity uptake on stainless steel surfaces. The study was carried out by using a test loop with simulated BWR water containing Fe(II/III), Ni(II) and Co-60 marked Co(II) species of varied concentration and 500 ppb O{sub 2}. The test tube section in the loop system was pre-exposed type 316L stainless steel material. The microstructures of the formed oxide films were examined with high resolution electron microscopy (FE-SEM and FE-TEM). The activity monitoring on the test section showed that injection of 10 ppb Ni(II) and 0.1 ppb Fe(II/III) in the water with 0.1 ppb Co(II) was capable of stopping completely activity uptake. When Co(II) addition in the loop was stopped no activity return to the water could be seen. In another exposure test, injection of combined 2 ppb Fe(II/III) and 0.5∼10 ppb Ni(II) profoundly increased activity uptake on the test section with a maximum in activity buildup at 5 ppb Ni(II). When Co(II) addition in the loop was stopped a slight activity return was seen. The observed differences as seen in the two tests are discussed in view of the microstructures of the oxide films formed. (author)

  14. Simulation of Thermal Stratification in BWR Suppression Pools with One Dimensional Modeling Method

    International Nuclear Information System (INIS)

    The suppression pool in a boiling water reactor (BWR) plant not only is the major heat sink within the containment system, but also provides the major emergency cooling water for the reactor core. In several accident scenarios, such as a loss-of-coolant accident and extended station blackout, thermal stratification tends to form in the pool after the initial rapid venting stage. Accurately predicting the pool stratification phenomenon is important because it affects the peak containment pressure; the pool temperature distribution also affects the NPSHa (available net positive suction head) and therefore the performance of the Emergency Core Cooling System and Reactor Core Isolation Cooling System pumps that draw cooling water back to the core. Current safety analysis codes use zero dimensional (0-D) lumped parameter models to calculate the energy and mass balance in the pool; therefore, they have large uncertainties in the prediction of scenarios in which stratification and mixing are important. While three-dimensional (3-D) computational fluid dynamics (CFD) methods can be used to analyze realistic 3-D configurations, these methods normally require very fine grid resolution to resolve thin substructures such as jets and wall boundaries, resulting in a long simulation time. For mixing in stably stratified large enclosures, the BMIX++ code (Berkeley mechanistic MIXing code in C++) has been developed to implement a highly efficient analysis method for stratification where the ambient fluid volume is represented by one-dimensional (1-D) transient partial differential equations and substructures (such as free or wall jets) are modeled with 1-D integral models. This allows very large reductions in computational effort compared to multi-dimensional CFD modeling. One heat-up experiment performed at the Finland POOLEX facility, which was designed to study phenomena relevant to Nordic design BWR suppression pool including thermal stratification and mixing, is used for

  15. CSAU methodology and results for an ATWS event in a BWR using information theory methods

    International Nuclear Information System (INIS)

    Highlights: • We apply the CSAU methodology to an ATWS in a BWR using information theory methods. • We show how to perform the selection of the most influential inputs on the critical safety parameter. • We apply the maximum entropy principle to get the input parameter distribution. • We examine the maximum relative entropy principle to update the input parameter PDF. • We quantify the uncertainty of the critical safety parameter using order statistics and information theory. - Abstract: This paper shows an application of the CSAU methodology to an ATWS in a BWR reactor, when the temperature of the suppression pool is taken as the critical safety parameter. The method combines CSAU methodology with recent techniques of information theory. In this paper we use auxiliary tools to help in the evaluation and improvement of the parameters distribution that enter in the elements II and III of CSAU based methodologies. These tools have been implemented in two FORTRAN programs: GEDIPA (Generation of the Parameter Distribution) and UNTHERCO (Uncertainty in Thermal Hydraulic Codes). The first one analyzes the information data available on a given parameter or parameters with the goal to know all the information about the probability distribution function of these parameters. The second apply information theory methods, as the maximum entropy principle (MEP) and the maximum relative entropy Principle (MREP), in order to build conservative distribution functions for the parameters from the available data. Also, the distribution function of a given parameter can be updated using the MREP principle when new information is provided. UNTHERCO performs the MONTECARLO sampling for a given set of parameters when the distribution function of these parameters is previously known. If the distribution of a parameter is unknown, then, the MEP is applied to deduce the distribution function for this parameter

  16. Evaluation of the radial design of fuel cells in an operation cycle of a BWR reactor

    International Nuclear Information System (INIS)

    This work is continuation of one previous in the one that the application of the optimization technique called Tabu search to the radial design of fuel cells of boiling water reactors (BWR, Boiling Water Reactor) is presented. The objective function used in the optimization process only include neutron parameters (k-infinite and peak of radial power) considering the cell at infinite media. It was obtained to reduce the cell average enrichment completing the characteristics of reactivity of an original cell. The objective of the present work is to validate the objective function that was used for the radial design of the fuel cell (test cell), analyzing the operation of a one cycle of the reactor in which fuels have been fresh recharged that contain an axial area with the nuclear database of the cell designed instead of the original cell. For it is simulated it with Cm-Presto the cycle 10 of the reactor operation of the Unit 1 of the Nuclear Power station of Laguna Verde (U1-CNLV). For the cycle evaluation its were applied so much the simulation with the Haling strategy, as the simulation of the one cycle with control rod patterns and they were evaluated the energy generation and several power limits and reactivity that are used as design parameters in fuel reloads of BWR reactors. The results at level of an operation cycle of the reactor, show that the objective function used in the optimization and radial design of the cell is adequate and that it can induce to one good use of the fuel. (Author)

  17. Progress of Ambiente & Agua Journal after three years of life

    Directory of Open Access Journals (Sweden)

    Getulio Teixeira Batista

    2009-08-01

    Full Text Available After completing three years since its first issue was published on August 2006, we are proud to report the development of Ambiente & Agua - An Interdisciplinary Journal of Applied Science, ISSN:1980-993X, doi:10.4136/1980-993X that is publishing its 10th issue with 17 peer reviewed articles. Thanks to the great support of the scientific community, especially to the authors e peer reviewers, all issues have been published on-time, i.e. at the end of April, August and December. Missions and goals are progressively being achieved. We have two new metadata harvester agencies listing the journal: the Portal of the Brazilian Agency from the Ministry of Education concerned with the graduate level education, known as CAPES in its service “Portal de Periódicos da CAPES” accessed by most of the scientific community in Brazil and the Summary of Brazilian Journals (Sumarios.org. We report in this current issue the growing international interest in the journal, by monitoring the access of readers, using several tools. Therefore, we anticipate a growing interest in the journal from notonly the Brazilian but also from the global scientific community.

  18. Bioética del derecho al agua potable

    Directory of Open Access Journals (Sweden)

    Bohórquez Caldera, Luis Alfredo

    2016-02-01

    Full Text Available Resumen. Se observa también, que en la prestación del servicio domiciliario de agua potable en Colombia, servicio que ha de ser asumido como derechos humanos fundamental, hoy en Colombia se conrroboran aspectos preocupantes en relación a la prestación de este servicio fundamental en los que se evidencia improvisación, manejo bajo la lógica del negocio y aplicación por ende de modelos inequitativos de prestación de servicios públicos. Abstract. It is observed that in the provision of the service of drinking water in Colombia, a service that has to be taken as a fundamental human right. Today in Colombia, worrying aspects as for the provision of this key service are corroborated, in which improvisation is made evident, which is carried out under the logics of business and the application, therefore, of inequitable models of the provision of public utilities.

  19. Analysis of the performance of fuel cells BWR with a single enrichment and radial distribution of enrichments; Analisis del desempeno de celdas combustibles BWR con un solo enriquecimiento y con distribucion radial de enriquecimientos

    Energy Technology Data Exchange (ETDEWEB)

    Gonzalez, J. A.; Vargas, S.; Alonso, G.; Del Valle, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN s/n, Col. Lindavista, Mexico D. F. 07738 (Mexico); Xolocostli M, J. V. [ININ, 52750 La Marquesa, Estado de Mexico (Mexico)]. e-mail: govaj666@hotmail.com

    2008-07-01

    The efficient use of the fuel is one of the objectives in the assemblies design of type BWR. The present tendency in the assemblies design of type BWR is through a radial distribution of enrichments. The present work has like object showing the because of this decision, for what a comparison of the neutronic performance of two fuel cells with the same enrichment average but one of them with radial distribution of enrichment and the other with a single enrichment equal to the average. The cells were analyzed with the CASMO-4 code and the obtained results of the behavior of the neutron flow and the power sustain the because of the radial distribution of enrichments. (Author)

  20. Concepto y trascendencia del derecho de aprovechamiento en materia de aguas (Propiedad y Aprovechamiento

    Directory of Open Access Journals (Sweden)

    Enrique Guerra Daneri

    2013-12-01

    Full Text Available La disciplina de las aguas se encuentra estructurada jurídicamente, sólo en base a dos derechos: el de propiedad y el de aprovechamiento. La caracterización que posee el agua como cosa, impide que puedan ejercerse otros derechos sobre ella.El punto de partida para explicar este fenómeno, radica en que el agua responde a dos hechos técnicos que ofician como fuente material o factor de calificación jurídica: el principio de territorialidad y la unidad del ciclo hidrológico. Estos dan motivo a su comportamiento universal y en ellos se asienta su disciplina, más allá de la regulación particular que cada derecho positivo quiera desarrollar, imponiendo una política en la materia.  En síntesis, el agua es un bien cuyas particularidades determinan que en definitiva, el derecho de propiedad sea desplazado en su trascendencia patrimonial por otro derecho que ocupa su lugar en jerarquía e individualidad: el derecho de aprovechamiento. Sin embargo y a pesar de los sólidos fundamentos que lo sustentan, la identidad de este derecho parece todavía opacada por los reflejos de una propiedad, que en materia de aguas, es inoperante.       

  1. Derecho ambiental legislación nacional e internacional sobre calidad de aguas

    Directory of Open Access Journals (Sweden)

    Gastón Casaux

    2015-09-01

    Full Text Available Contenido: Antecedentes. Principios esenciales. El criterio general de Naciones Unidas. La costumbre en Uruguay. Competencias nacionales. Código Civil y Código Penal. Código Rural. Código de Aguas. Ley 13.667 de 18.6.68 sobre Suelos y Aguas y su modificativa decreto-ley 15.239 de 23-12-81 o Ley de Suelos. Ley de Riego Nº16.858 y reglamentación posterior. Ministerio de Transporte y Obras Públicas (Dirección de Hidrografía, Ministerio de Ganadería, Agricultura y Pesca (Dirección de Suelos yAguas, Ministerio de Medio Ambiente (DINAMA, Ministerio de Salud Pública (Ley 9.202 de 1934, Ministerio de Relaciones Exteriores (Dirección de Asuntos Internacionales, Ministerio de Industria y Energía (Dirección de Minería y Geología Municipios.  Obras Sanitarias del Estado (OSE Universidad de la República. Panorama jurídico de la región. Tratados internacionales. Normas. Mercosur. Derecho Ambiental y Obras de la zona. Pasivo y activo del Mercosur. El Derecho Comparado. Conclusiones. La importancia económica, jurídica y ambiental del agua. Las diferenteslegislaciones y su trascendencia para el desarrollo. El recurso agua como fuente de poder

  2. [Water birds from Agua Dulce lake and El Ermitaño estuary, Jalisco, Mexico].

    Science.gov (United States)

    Hernández Vázquez, Salvador

    2005-01-01

    Waterbird abundance, and seasonal and spatial distribution, were studied in two natural water pools at Jalisco, Mexico, from December 1997 through November 1998. Maximum monthly abundance in Agua Dulce lake and El Ermitaño estuary was 86 471 birds (29 686 in Agua Dulce and 56 785 in Ermitaño), with a total cummulative abundance of 179 808 individuals (66 976 in Agua Dulce and 112 832 in Ermitaño). A total of 87 waterbirds species were recorded, 78 in Agua Dulce and 73 in Ermitaño. The higher species richness and abundance was observed during winter, when migratory species arrived. Most species prefered shallow waters, except seabirds which prefered protected areas such as dunes in Agua Dulce. Other groups, like clucks and related species. prefered low salinity areas, for example in the south-east area of Ermitaño. The higher abundance of the shorehirds was found when the water level on the estuary was low. Herons were seen often at areas with high salinity and influenced by tides (e.g. mouth of Ermitaño).

  3. Pueblos indígenas de Sonora: el agua, ¿es de todos?

    Directory of Open Access Journals (Sweden)

    Diana Luque

    2012-01-01

    Full Text Available La diversidad cultural y la problemática ambiental del agua en el estado de Sonora convergen en el presente trabajo, abordadas desde la perspectiva de la ecología política y la diversidad biocultural mediante un análisis transdisciplinario. Se distingue entre el acceso al agua para la subsistencia tradicional del agua para el desarrollo. Se advierten tendencias generalizadas de despojo de los territorios indígenas y sus recursos naturales, en las que los conflictos por el agua para la subsistencia son cada vez más graves, que exacerban la vulnerabilidad de las comunidades y la desorganización del complejo biocultural. El servicio del agua potable no tiene las condiciones para impulsar el desarrollo comunitario sustentable. Estas tendencias no son homogéneas, y se observan posibilidades de reconfiguración. Se requiere precisar el análisis para aportar al desarrollo de los pueblos indígenas, desde una plataforma biocultural contemporánea, en pleno respeto de sus derechos humanos individuales y colectivos.

  4. Calidad del agua y sedimento en el lago de Maracaibo, estado Zulia

    Directory of Open Access Journals (Sweden)

    Giovany José-Bracho

    2016-03-01

    Full Text Available Se analizó el agua y el sedimento del lago de Maracaibo en seis estaciones de muestreo distribuidas de norte a sur del lago. Los parámetros físicoquímicos y ambientales fueron determinados y establecidas las relaciones entre estos y las áreas afectadas por descargas de aguas residuales, depósitos de basura, residuos industriales líquidos y sólidos, actividad petrolera y agrícola y materiales orgánicos acarreados por ríos y drenajes pluviales. Se evidenció la contaminación por incremento de utrientes(nitrógeno y fósforo en las zonas influenciadas por los ríos y vertederos de agua residual y se validó la presencia de una cuña salina por la penetración al lago de las aguas del golfo de Venezuela. Las concentraciones de metalespesados están por debajo de los límites permisibles para el agua; en los sedimentos es muy heterogénea.

  5. EVALUACIÓN DE LA PLANTA Lemna minor COMO BIORREMEDIADORA DE AGUAS CONTAMINADAS CON MERCURIO

    Directory of Open Access Journals (Sweden)

    Adolfo D. Arenas

    2011-01-01

    Full Text Available Se evaluó la capacidad biorremediadora de Lemna minor en función del tiempo en aguas contaminadas con mercurio mediante un diseño experimental de 3 bloques al azar con cinco réplicas: un grupo experimental con 100 g de Lemna, 7,5 L de agua contaminada con Hg (0,13 mgL-1 y solución nutritiva; un grupo Testigo con 100 g de Lemna, 7,5 L de agua y solución nutritiva y un grupo control con mercurio al nivel de 0,13 mgL-1 en agua destilada sin plantas. La eficiencia de remoción de mercurio de la Lemna minor, en 22 días, fue de 30%. Las variables peso fresco, peso seco, y nitrógeno y fósforo foliares no presentaron diferencias significativas entre los dos tratamientos. La absorción de potasio, fue afectada por los niveles de mercurio. La planta Lemna minor representa una alternativa para la remoción de mercurio en aguas contaminadas hasta un nivel de 0,13 mg/L.

  6. Los Imaginarios del agua y sus lecturas pansemióticas

    Directory of Open Access Journals (Sweden)

    Alberto E. Martos García

    2012-12-01

    Full Text Available Los Imaginarios del Agua constituyen un conjunto de etnotextos, ritos y símbolos que son susceptibles de ser leídos desde muy diferentes perspectivas. En este artículo se profundiza en dos aspectos concretos: la totemización o personificación que suponen los genios del agua y sus lecturas plurisimbólicas, y la necesidad de establecer una lectura poética y pansemiótica del agua, conforme a los postuladosde la Ecocrítica. En segundo lugar, se exponen las virtualidades de la cultura del agua en la educación en cuanto a contribuir a la adquisición de las competencias básicas educativas, y en particular, a la educación literaria y del patrimonio, además de ayudar a comprenderla gobernanza del agua y a la gestión sostenible y responsable de los recursos hídricos. Como indica E. Morin, la lectura y la literatura son una escuela de complejidad, y estos mitos inciden siempre en lacomplejidad del sentido de las acciones humanas.

  7. Nematodos en las plantas de tratamiento de agua para consumo humano en Costa Rica

    Directory of Open Access Journals (Sweden)

    Mariano Peinador

    2000-12-01

    Full Text Available Los nematodos acuáticos son habitantes frecuentes en las plantas de tratamiento de agua para consumo humano. Su presencia en ellas y el grado en que son removidos por dichas plantas puede ser utilizado como un parámetro de funcionamiento y de calidad de agua, ya que muchos organismos patógenos pueden pasar a los sistemas de distribución de agua dentro del cuerpo de los nematodos. Para analizar esta problemática se realizaron 1356 muestreos en el agua cruda y tratada de 27 plantas de tratamiento. Los resultados demuestran la alta incidencia de nematodos y la baja taza de remoción que presentan varias plantas de tratamiento, llegando a ser de 0. 5 en el 11% de las plantas, 0.4 en el 18% y 0.3 en el 29%. Este hecho se agrava si se toma en cuenta que dentro de las plantas de tratamiento que tienen una menor taza de remoción se encuentran las de mayor producción de agua para consumo.

  8. Comparative analysis of results between CASMO, MCNP and Serpent for a suite of Benchmark problems on BWR reactors; Analisis comparativo de resultados entre CASMO, MCNP y SERPENT para una suite de problemas Benchmark en reactores BWR

    Energy Technology Data Exchange (ETDEWEB)

    Xolocostli M, J. V.; Vargas E, S.; Gomez T, A. M. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Reyes F, M. del C.; Del Valle G, E., E-mail: vicente.xolocostli@inin.gob.mx [IPN, Escuela Superior de Fisica y Matematicas, UP - Adolfo Lopez Mateos, Edif. 9, 07738 Mexico D. F. (Mexico)

    2014-10-15

    In this paper a comparison is made in analyzing the suite of Benchmark problems for reactors type BWR between CASMO-4, MCNP6 and Serpent code. The Benchmark problem consists of two different geometries: a fuel cell of a pin and assembly type BWR. To facilitate the study of reactors physics in the fuel pin their nuclear characteristics are provided to detail, such as burnt dependence, the reactivity of selected nuclide, etc. With respect to the fuel assembly, the presented results are regarding to infinite multiplication factor for burning different steps and different vacuum conditions. Making the analysis of this set of Benchmark problems provides comprehensive test problems for the next fuels generation of BWR reactors with high extended burned. It is important to note that when making this comparison the purpose is to validate the methodologies used in modeling for different operating conditions, if the case is of other BWR assembly. The results will be within a range with some uncertainty, considering that does not depend on code that is used. Escuela Superior de Fisica y Matematicas of Instituto Politecnico Nacional (IPN (Mexico) has accumulated some experience in using Serpent, due to the potential of this code over other commercial codes such as CASMO and MCNP. The obtained results for the infinite multiplication factor are encouraging and motivate the studies to continue with the generation of the X S of a core to a next step a respective nuclear data library is constructed and this can be used by codes developed as part of the development project of the Mexican Analysis Platform of Nuclear Reactors AZTLAN. (Author)

  9. 76 FR 63614 - Agua Caliente Solar, LLC; Supplemental Notice That Initial Market-Based Rate Filing Includes...

    Science.gov (United States)

    2011-10-13

    ... From the Federal Register Online via the Government Publishing Office DEPARTMENT OF ENERGY Federal Energy Regulatory Commission Agua Caliente Solar, LLC; Supplemental Notice That Initial Market-Based Rate...-referenced proceeding of Agua Caliente Solar, LLC's application for market-based rate authority, with...

  10. Plan de empresa y estudio de viabilidad de una consultora especializada en el ahorro y uso eficiente del agua

    OpenAIRE

    Rubio Berástegui, Javier

    2011-01-01

    Este proyecto fin de carrera consta de dos partes bien diferenciadas. En la primera parte se desarrolla el plan de empresa y el estudio de viabilidad de una consultora especializada en el ahorro y uso eficiente del agua, mientras que la segunda parte muestra el desarrollo técnico de un sistema de aprovechamiento de aguas grises para aseos.

  11. Pre-study of dynamic loads on the internals caused by a large pipe break in a BWR; Foerstudie av stroemningsinducerade laster paa interndelar vid brott i huvudcirkulationskretsarna i BWR

    Energy Technology Data Exchange (ETDEWEB)

    Marcinkiewicz, Jerzy; Lindgren, Anders [Det Norske Veritas Nuclear Technology AB, Stockholm (Sweden)

    2002-12-01

    Det Norske Veritas Nuclear Technology has performed a literature study of dynamic load on a BWR (Boiling Water Reactor) internals caused by a large pipe break. The goal of the study was to improve the knowledge about the physics of phenomena occurring in the RPV (Reactor Pressure Vessel) after pipe break in the main circulation system and also to make a review of calculation methods, models and computer programs including their capabilities when calculating the dynamic loads. The report presents description of relevant parts of a BWR, initial and boundary conditions, and phenomena determining the loads - rapid depressurization and propagation of pressure wave (including none-equilibrium). Furthermore, the report generally describes possible methodologies for calculating the dynamic loads on internals after the pipe break and the experiences from calculations the dynamic loads with different methods (computer programs) including comparisons with experimental data. Fluid-Structure Interaction methodology and its importance for calculation of dynamic loads on reactor internals is discussed based on experimental data. A very intensive research program for studying and calculating the dynamic loads on internals after pipe breaks has been performed in USA and Germany during the seventies and the eighties. Several computer programs have been developed and a number of large-scale experiments have been performed to calibrate the calculation methods. In spite of the fact that all experiments were performed for PWR several experiences should be valid also for BWR. These experiences, connected mainly to capabilities of computer programs calculating dynamic loads, are discussed in the report.

  12. Condensate treatment in BWR circuits by filter demineralizer units using powdered ion exchange resin at medium and high temperature

    International Nuclear Information System (INIS)

    Considering the radiation build-up in some BWR reactors, we make a correlation between this phenomenon and the condensate purification system applied and the point of its utilization into the circuits. The application temperature of such a plant seems to have a very important role on the equilibria of metals contained in the reactor water and on the oxide composition. The efficiency of the condensate polishing system and the corrosion control are the most interesting objectives to achieve and to maintain, to control and regulate the physical and chemical process in the feedwater and in the reactor water. Up to date the technology owns major knowledge and a consistent know-how on using chemical products in order to increase the condensate polishing system efficiency. It is also considered a typical parallel case of a conventional power station and a secondary system of BWR units. (author)

  13. BWR spent fuel storage cask performance test. Volume 1. Cask handling experience and decay heat, heat transfer, and shielding data

    International Nuclear Information System (INIS)

    This report documents a heat transfer and shielding performance test conducted on a Ridihalgh, Eggers and Associates REA 2023 boiling water reactor (BWR) spent fuel storage cask. The testing effort consisted of three parts: pretest preparations, performance testing, and post-test activities. Pretest preparations included conducting cask handling dry runs and characterizing BWR spent fuel assemblies from Nebraska Public Power District's Cooper Nuclear Station. The performance test matrix included 14 runs consisting of two loadings, two cask orientations, and three backfill environments. Post-test activities included calorimetry and axial radiation scans of selected fuel assemblies, in-basin sipping of each assembly, crud collection, video and photographic scans, and decontamination of the cask interior and exterior

  14. VIPRE-W / MEFISTO-T - A mechanistic tool for transient prediction of dryout in BWR fuel

    Energy Technology Data Exchange (ETDEWEB)

    Adamsson, C., E-mail: carl.adamsson@psi.ch [Westinhouse Electric Sweden, Vasteras (Sweden); Paul Scherrer Institut, Villigen (Switzerland); Le Corre, J-M., E-mail: lecorrjm@westinghouse.com [Westinhouse Electric Sweden, Vasteras (Sweden)

    2011-07-01

    The VIPRE-W/MEFISTO-T code package constitutes a simplified approach to sub-channel film-flow analysis whereby the transport equations for the liquid films are decoupled from each other. The approach allows fast and robust simulation with high axial resolution of realistic BWR transients. It has previously been shown that a steady-state version of the model agrees well with dryout measurements in full-scale fuel assembly mock-ups performed at the Westinghouse FRIGG loop. In this paper, we present validation of the transient version of the code with around 300 transient dryout experiments from the same loop. The transients involve realistic variations of flow and power and three different axial power distributions at conditions typical for BWR operation. The results from the film-flow analysis show high precision in the dryout prediction but a hitherto unexplained bias that reduces the accuracy. (author)

  15. Investigation of distorted-geometry simulation of pool dynamics in horizontal-vent BWR containments. Topical report

    International Nuclear Information System (INIS)

    Experiments were conducted to investigate the accuracy of distorted-geometry testing of pool dynamics in horizontal-vent BWR containments. Distorted-geometry testing implies testing in systems where the flow-wise dimensions are full scale, but all dimensions transverse to the flow are reduced in the same proportion. The assumption is that flow velocities, pressures and other thermodynamic properties can be interpreted as being the same in the distorted-geometry system as in its correctly proportioned counterpart. The experiments discussed in this report, which were done at small scale using the established scaling laws, showed that the geometric distortions can have a significant effect on the pool swell under conditions which are roughly representative of horizontal-vent BWR containment systems during a LOCA

  16. BWR spent fuel storage cask performance test. Volume 1. Cask handling experience and decay heat, heat transfer, and shielding data

    Energy Technology Data Exchange (ETDEWEB)

    McKinnon, M.A.; Doman, J.W.; Tanner, J.E.; Guenther, R.J.; Creer, J.M.; King, C.E.

    1986-02-01

    This report documents a heat transfer and shielding performance test conducted on a Ridihalgh, Eggers and Associates REA 2023 boiling water reactor (BWR) spent fuel storage cask. The testing effort consisted of three parts: pretest preparations, performance testing, and post-test activities. Pretest preparations included conducting cask handling dry runs and characterizing BWR spent fuel assemblies from Nebraska Public Power District's Cooper Nuclear Station. The performance test matrix included 14 runs consisting of two loadings, two cask orientations, and three backfill environments. Post-test activities included calorimetry and axial radiation scans of selected fuel assemblies, in-basin sipping of each assembly, crud collection, video and photographic scans, and decontamination of the cask interior and exterior.

  17. Parametric study of the potential for BWR ECCS strainer blockage due to LOCA generated debris. Final report

    International Nuclear Information System (INIS)

    This report documents a plant-specific study for a BWR/4 with a Mark I containment that evaluated the potential for LOCA generated debris and the probability of losing long term recirculation capability due ECCS pump suction strainer blockage. The major elements of this study were: (1) acquisition of detailed piping layouts and installed insulation details for a reference BWR; (2) analysis of plant specific piping weld failure probabilities to estimate the LOCA frequency; (3) development of an insulation and other debris generation and drywell transport models for the reference BWR; (4) modeling of debris transport in the suppression pool; (5) development of strainer blockage head loss models for estimating loss of NPSH margin; (6) estimation of core damage frequency attributable to loss of ECCS recirculation capability following a LOCA. Elements 2 through 5 were combined into a computer code, BLOCKAGE 2.3. A point estimate of overall DEGB pipe break frequency (per Rx-year) of 1.59E-04 was calculated for the reference plant, with a corresponding overall ECCS loss of NPSH frequency (per Rx-year) of 1.58E-04. The calculated point estimate of core damage frequency (per Rx-year) due to blockage related accident sequences for the reference BWR ranged from 4.2E-06 to 2.5E-05. The results of this study show that unacceptable strainer blockage and loss of NPSH margin can occur within the first few minutes after ECCS pumps achieve maximum flows when the ECCS strainers are exposed to LOCA generated fibrous debris in the presence of particulates (sludge, paint chips, concrete dust). Generic or unconditional extrapolation of these reference plant calculated results should not be undertaken

  18. Stakes and Solutions for current and up-coming Licensing Challenges in PWR and BWR Reload and Safety Analysis

    Energy Technology Data Exchange (ETDEWEB)

    Curca-Tiving, F.; Opel, S.

    2014-07-01

    Regulatory requirements for reloads and safety analyses are evolving: New safety criteria, requests for enlarged qualification databases, statistical applications, uncertainty propagation... In order to address these challenges and access more predictable licensing processes, AREVA implements a consistent code and methodology suite for PWR and BWR core design and safety analysis, based on a first principles modeling with an extremely broad international verification and validation data base. (Author)

  19. Experience of MOX-fuel operation in the Gundremmingen BWR plant: Nuclear characteristics and in-core fuel management

    International Nuclear Information System (INIS)

    After 4 years of good experience with MOX-fuel operation in the BWR plants Gundremmingen units B and C the number of inserted MOX-FAs will be increased in the future continuously. Until now all MOX-FAs are in good condition. Furthermore calculations and measurements concerning zero power tests and tip measurements are in good agreement as expected: all results lead to the conclusion that MOX-FAs can be calculated with the same precision as uranium-FAs. (author)

  20. Effect of two impurities and zinc on stress corrosion cracking of stainless steel and nickel alloys in BWR environments

    International Nuclear Information System (INIS)

    Boiling water reactors (BWRs) operate with very high purity water with only small additions of dissolved hydrogen and, most recently, noble metals. However, even operation with very low conductivity water (e.g., 0.07 μS/cm) coolant will not prevent intergranular stress corrosion cracking (IGSCC) of sensitized stainless steel and nickel alloys under atypical oxygenated conditions. The presence of certain impurities dissolved in the coolant can dramatically increase the propensity of this most insidious form of environmentally-assisted cracking. The goal of this paper is to present the effect of effect of chloride and sulfate plus zinc on the IGSCC propensities of BWR piping and reactor internals under both oxygenated, i.e., normal water chemistry (NWC) and deoxygenated, i.e., hydrogen water chemistry (HWC) conditions. While it is well documented the sulfate and chloride are particularly aggressive in promoting IGSCC of BWR structural materials, several anions such as chromate and nitrate have little impact while of zinc added as zinc oxide appears to be beneficial. To emphasize the effect of impurities on the structural integrity of BWR components in perspective, the BWR fleet's most severe documented water chemistry transient, where the conductivity reached on 232 μS/cm with 21.2 ppm chloride and 93.8 ppm sulfate, will be presented. For example, on-line real-time crack growth rate measurements using the highly accurate reversing DC potential drop technique revealed a crack growth rate increase by almost a factor of 300 for an Alloy 182 weld metal compact tension fracture mechanics specimen during this raw water transient. The recommendations for subsequent plant inspection and start up after this transient will also be discussed where the value of real time crack growth rate monitoring cannot be overemphasized. (author)

  1. Comparative analysis of results between CASMO, MCNP and Serpent for a suite of Benchmark problems on BWR reactors

    International Nuclear Information System (INIS)

    In this paper a comparison is made in analyzing the suite of Benchmark problems for reactors type BWR between CASMO-4, MCNP6 and Serpent code. The Benchmark problem consists of two different geometries: a fuel cell of a pin and assembly type BWR. To facilitate the study of reactors physics in the fuel pin their nuclear characteristics are provided to detail, such as burnt dependence, the reactivity of selected nuclide, etc. With respect to the fuel assembly, the presented results are regarding to infinite multiplication factor for burning different steps and different vacuum conditions. Making the analysis of this set of Benchmark problems provides comprehensive test problems for the next fuels generation of BWR reactors with high extended burned. It is important to note that when making this comparison the purpose is to validate the methodologies used in modeling for different operating conditions, if the case is of other BWR assembly. The results will be within a range with some uncertainty, considering that does not depend on code that is used. Escuela Superior de Fisica y Matematicas of Instituto Politecnico Nacional (IPN (Mexico) has accumulated some experience in using Serpent, due to the potential of this code over other commercial codes such as CASMO and MCNP. The obtained results for the infinite multiplication factor are encouraging and motivate the studies to continue with the generation of the X S of a core to a next step a respective nuclear data library is constructed and this can be used by codes developed as part of the development project of the Mexican Analysis Platform of Nuclear Reactors AZTLAN. (Author)

  2. Gobernanza del agua residual en Aguascalientes: captura regulatoria y arreglos institucionales complejos

    Directory of Open Access Journals (Sweden)

    Raul Pacheco-Vega

    2015-01-01

    Full Text Available El manejo de agua en Aguascalientes se ha estudiado desde la perspectiva del suministro, pero no se ha analizado la gobernanza del agua residual. En este artículo se examina el manejo de efluentes del municipio de Aguascalientes utilizando las teorías del neoinstitucionalismo histórico, de la gobernanza y de la captura regulatoria. Se explica los factores que han influido en la operación reciente (2010-2013 del tratamiento y reuso de agua municipal. El análisis está fundamentado en los debates contemporáneos sobre priva - tización del recurso hídrico, y enfocado en el periodo de la administración priista de Lorena Martínez, y sus proyectos emblemáticos: Línea Verde y Líneas Moradas.

  3. El arte de aforar: del nilómetro a la paja de agua cordobesa

    OpenAIRE

    Roldán Cañas, José

    2014-01-01

    Esta ponencia pretende describir la evolución diacrónica del aforo desde los orígenes hasta la paja de agua cordobesa, o medida de agua que se usó en la ciudad de Córdoba entre los siglos XVI y XIX. También se presenta la determinación de su valor expresándolo en unidades del sistema métrico decimal. El aforo de corrientes de agua ha tenido un gran interés para la humanidad desde sus albores. Las grandes civilizaciones han nacido y crecido a la orilla de los grandes ríos, y ...

  4. Portal Web "Portagua" para apoyar los conocimientos sobre la calidad del agua

    Directory of Open Access Journals (Sweden)

    José R. Ramírez Venega

    2012-01-01

    Full Text Available Se elaboró el portal Web "Portagua" cuyo contenido, sobre calidad del agua, resulta de vital importancia ya que en las últimas décadas la contaminación del agua, tanto superficial como subterránea, se ha incrementado notablemente. El portal incluye informaciones tales como: conferencias, regulaciones, artículos científicos, trabajos de diploma, figuras, videos y otras que han sido recopiladas y debidamente organizadas, a las que puede accederse con facilidad. Por el alcance de su contenido, permite quesea utilizado por todas las personas interesadas en el tema. Su uso contribuye a: optimizar el tiempo de búsqueda de los usuarios y apoyar los conocimientos sobre la calidad del agua.

  5. Las aguas de consumo envasadas en España. Trasvases muy rentables y nada cuestionados

    Directory of Open Access Journals (Sweden)

    Cayetano Espejo Marín

    2001-01-01

    Full Text Available El consumo de agua envasada en España ha ido en paralelo desde finales de los años ochenta al incremento en el nivel de vida de los españoles. Un reducido grupo de empresas, con una gran incidencia de las multinacionales, controla la mayor parte del mercado. Con este artículo se pretende destacar la importancia de este sector a través del análisis de los siguientes aspectos: tipos de agua envasada, evolución de la producción, localización de los manantiales, estructura de las empresas, y por último se estudia el caso de la ciudad de Murcia, ejemplo significativo de área de recepción de agua envasada procedente de varias provincias españolas.

  6. Usos y riesgos del agua en la cuenca La Antigua, Veracruz, México

    OpenAIRE

    Ana Rita Román-Jiménez; Martín Alfonso Mendoza-Briseño; Alejandro Velázquez-Martínez; Mario Roberto Martínez-Ménez; Juan Manuel Torres-Rojo; Hugo Ramírez-Maldonado

    2011-01-01

    El agua en México se considera un recurso escaso y valioso. Este trabajo es un ensayo que toma como caso de estudio la cuenca del río La Antigua, en Veracruz, México. En este lugar la condición y manejo de las tierras se relacionó con atributos del agua en función de usos varios. La cuenca de La Antigua capta una gran cantidad de agua y aún así se perciben problemas relacionados con el vital líquido. Las evidencias y el análisis en este estudio revelan la existencia de un imaginario colectiv...

  7. Riesgos a la salud por presencia del aluminio en el agua potable

    Directory of Open Access Journals (Sweden)

    Rodolfo Trejo Vázquez

    2004-01-01

    Full Text Available En la actualidad el aluminio tiene una amplia aplicación en la industria alimenticia, farmacéutica, del papel, de la construcción y en el tratamiento de agua para beber y agua residual. Sin embargo, no se ha dado énfasis a los posibles daños a la salud originados por el consumo de este elemento. Una de las enfermedades que ha sido asociada a la ingesta de este elemento es el Alzheimer y se corre el riesgo de desarrollar otros padecimientos. En el presente documento se resumen los resultados obtenidos de una investigación bibliográfica relacionada con los daños a la salud originados por el consumo de aluminio y compuestos fluoroaluminados, la finalidad es poner de manifiesto la importancia que tiene vigilar y controlar el contenido del aluminio en el agua potable

  8. Metagabro sill zircon dating: Archean age confirmation from the Aguas Claras formation, Carajas, Para State, Brazil

    International Nuclear Information System (INIS)

    The Carajas region, situated at Para State, Brazil, presents a great diversity of the mafic rock occurrences, distributed between various units. The rocks have been described petrographically and its geochemical and geochronological data have been accumulated. However, these last data are relatively limited or inexact due to the difficulties to these rock dating using the Uranium-Lead (U-Pb) in zircons method. The Aguas Claras Formation age is another problem in the Carajas stratigraphy. The occurrence of metagabros sills in the Aguas Claras region and the fact of existing zircons in these metagabros, stimulated the authors to realize a geochronological study of these metagabros aiming to define its age and, consequently, the minimum age of the Aguas Claras Formation. The paper presents the geological context and the methodology to develop the geochronological studies of these rocks. (author)

  9. Pre-study of dynamic loads on the internals caused by a large pipe break in a BWR

    International Nuclear Information System (INIS)

    Det Norske Veritas Nuclear Technology has performed a literature study of dynamic load on a BWR (Boiling Water Reactor) internals caused by a large pipe break. The goal of the study was to improve the knowledge about the physics of phenomena occurring in the RPV (Reactor Pressure Vessel) after pipe break in the main circulation system and also to make a review of calculation methods, models and computer programs including their capabilities when calculating the dynamic loads. The report presents description of relevant parts of a BWR, initial and boundary conditions, and phenomena determining the loads - rapid depressurization and propagation of pressure wave (including none-equilibrium). Furthermore, the report generally describes possible methodologies for calculating the dynamic loads on internals after the pipe break and the experiences from calculations the dynamic loads with different methods (computer programs) including comparisons with experimental data. Fluid-Structure Interaction methodology and its importance for calculation of dynamic loads on reactor internals is discussed based on experimental data. A very intensive research program for studying and calculating the dynamic loads on internals after pipe breaks has been performed in USA and Germany during the seventies and the eighties. Several computer programs have been developed and a number of large-scale experiments have been performed to calibrate the calculation methods. In spite of the fact that all experiments were performed for PWR several experiences should be valid also for BWR. These experiences, connected mainly to capabilities of computer programs calculating dynamic loads, are discussed in the report

  10. Impact of modeling Choices on Inventory and In-Cask Criticality Calculations for Forsmark 3 BWR Spent Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Martinez-Gonzalez, Jesus S. [Univ. Politecnica de Madrid (Spain); Ade, Brian J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bowman, Stephen M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Gauld, Ian C. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ilas, Germina [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Marshall, William BJ J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-01-01

    Simulation of boiling water reactor (BWR) fuel depletion poses a challenge for nuclide inventory validation and nuclear criticality safety analyses. This challenge is due to the complex operating conditions and assembly design heterogeneities that characterize these nuclear systems. Fuel depletion simulations and in-cask criticality calculations are affected by (1) completeness of design information, (2) variability of operating conditions needed for modeling purposes, and (3) possible modeling choices. These effects must be identified, quantified, and ranked according to their significance. This paper presents an investigation of BWR fuel depletion using a complete set of actual design specifications and detailed operational data available for five operating cycles of the Swedish BWR Forsmark 3 reactor. The data includes detailed axial profiles of power, burnup, and void fraction in a very fine temporal mesh for a GE14 (10×10) fuel assembly. The specifications of this case can be used to assess the impacts of different modeling choices on inventory prediction and in-cask criticality, specifically regarding the key parameters that drive inventory and reactivity throughout fuel burnup. This study focused on the effects of the fidelity with which power history and void fraction distributions are modeled. The corresponding sensitivity of the reactivity in storage configurations is assessed, and the impacts of modeling choices on decay heat and inventory are addressed.

  11. Verification of the Advanced Nodal Method on BWR Core Analyses by Whole-Core Heterogeneous Transport Calculations

    International Nuclear Information System (INIS)

    Recent boiling water reactor (BWR) core and fuel designs have become more sophisticated and heterogeneous to improve fuel cycle cost, thermal margin, etc. These improvements, however, tend to lead to a strong interference effect among fuel assemblies, and it my cause some inaccuracies in the BWR core analyses by advanced nodal codes. Furthermore, the introduction of mixed-oxide (MOX) fuel will lead to a much stronger interference effect between MOX and UO2 fuel assemblies. However, the CHAPLET multiassembly characteristics transport code was developed recently to solve two-dimensional cell-heterogeneous whole-core problems efficiently, and its results can be used as reference whole-core solutions to verify the accuracy of nodal core calculations. In this paper, the results of nodal core calculations were compared with their reference whole-core transport solutions to verify their accuracy (in keff, assembly power and pin power via pin power reconstruction) of the advanced nodal method on both UO2 and MOX BWR whole-core analyses. Especially, it was investigated if there were any significant differences in the accuracy between MOX and UO2 results

  12. Vigilancia sanitaria del agua: un nuevo enfoque para municipalidades de Costa Rica

    Directory of Open Access Journals (Sweden)

    Carmen Valiente

    1999-12-01

    Full Text Available Los programas de vigilancia sanitaria constituyen el nuevo enfoque para complementar los programas de control de calidad del agua y consisten en la aplicación de una metodología que permite determinar el grado de riesgo para la salud que presentan los sistemas de agua para consumo humano. En el presente trabajo se presenta el desarrollo y adaptación de un Programa de Vigilancia Sanitaria para ser utilizado en Costa Rica. Este programa se basa principalmente en determinar el grado de riesgo para la salud que posee un acueducto, relacionando el nivel de contaminación fecal con el grado de la inspección sanitaria obtenido a partir de encuestas de campo. Los alcances del programa son proveer una plataforma para dar prioridad racional a las inversiones en el sector agua y unifica esfuerzos entre los dos roles importantes en esta área, el de las instituciones encargadas del abastecimiento de agua y el ente rector o autoridad reguladora en el campo del agua y la salud. Inicialmente, para implementar este programa se seleccionaron las Municipales de Costa Rica, de las 81 municipalidades existentes, 37 operan sistemas de suministro de agua para un total de 243 acueductos. El programa fue implementado durante los años 1996 y 1997. Se presentan para ilustración los resultados obtenidos en dos acueductos pertenecientes a las municipalidades de Cartago y San Marcos de Tarrazú. La ventaja de este tipo de programas sobre otros de control de calidad, radica principalmente en poder determinar el estado en que se encuentran las estructuras del acueducto y no solo su calidad, con el fin de establecer las prioridades para una inversión eficiente de los recursos existentes y así evitar la exposición de los usuarios a enfermedades de transmisión hídrica.

  13. Genotoxicidad del agua contaminada por plaguicidas en un área de Antioquia

    Directory of Open Access Journals (Sweden)

    Flor Tobón M.

    2011-05-01

    Full Text Available Objetivo. Determinar genotoxicidad del extracto orgánico de recursos hídricos de la vereda Monterredondo (Antioquia, contaminados por el uso de pesticidas en la agricultura, en la producción porcina y avícola como un diagnóstico de su calidad para entender su influencia en estas fuentes de agua en el municipio de San Pedro de Los Milagros (Antioquia. Materiales y métodos. Se empleó el ensayo cometa para establecer fragilidad osmótica de eritrocitos, viabilidad celular y alteración del ADN de linfocitos humanos al incubar estas células en agua recogida de tres fuentes hídricas de la vereda Monterredondo en el laboratorio de Bioquímica de la Facultad de Medicina de la Universidad de Antioquia. Resultados. El análisis de los datos de la longitud del cometa del extracto orgánico de las tres muestras, indicaron genotoxicidad. Este efecto fue dependiente de la concentración del extracto y del sitio de muestreo (p<0.001. La muestra de agua de la quebrada el Hato, presentó el mayor efecto genotóxico a 4 y 37ºC; la muestra de agua de la planta de tratamiento de la Hacienda La Montaña, presentó una alta genotoxicidad relativa, comparada con la muestra de agua de la quebrada Fray Juana. Conclusiones. El análisis de las tres muestras de agua recogidas en la vereda Monterredondo reveló genotoxicidad. Sin embargo, se sugiere en el futuro evaluar el grado de toxicidad de los componentes orgánicos concentrados y la genotoxicidad en personas que la consumen.

  14. Aguaclara, una alternativa para el tratamiento de agua para consumo humano. Aguaclara - an alternativefor drinking water treatment.

    Directory of Open Access Journals (Sweden)

    Gilberto Arturo Díaz Ordóñez

    2011-05-01

    Full Text Available Agua Para el Pueblo con el apoyo técnico del Programa AguaClara de la Universidad de Cornell, facilita asistencia técnica a comunidades rurales mayores de 2,000 habitantes y pequeñas y medianas ciudades con poblaciones menores de 50,000 habitantes, para la construcción de plantas de tratamiento denominadas AguaClara. Este esfuerzo institucional es una respuesta para optimizar la desinfección del agua con cloro en aquellos sistemas de agua ya construidos y que por razones naturales o antropicas se han visto afectados con problemas de alta turbiedad en los suministros de agua. La tecnología consiste en la floculación hidráulica, la sedimentación de alto rendimiento y la desinfección con alta eficiencia, sin el uso de la filtración o energía eléctrica para asegurar una entrega de agua de acuerdo a la Norma Técnica Nacional de Calidad del Agua de Honduras. La gestión de las plantas de tratamiento AguaClara va más allá de los aspectos constructivos y enfatiza simultáneamente la organización comunitaria, la capacitación de los diferentes actores, la readecuación de las tarifas, la operación y mantenimiento del sistema incluyendo la planta de tratamiento, así como la mitigación de las vulnerabilidades del sistema de agua y la protección sanitaria y ambiental en general de los entornos comunitarios donde se construyen las plantas de tratamiento.

  15. Tratamiento con ozono de las aguas residuales de almazara

    Directory of Open Access Journals (Sweden)

    Domínguez Vargas, Joaquín R.

    2000-10-01

    Full Text Available In the present work, the ozonation of olive mill wastewater has been studied. The evolution process was followed by measuring the chemical oxygen demand, the aromaticity and the contents of phenolic compounds. The aromaticity conversion ranged between 4.85 and 21%, chemical oxygen demand degradation varied from 3.25 to 19.4%, and the total polyphenolic reduction varied between 6.86 and 43.7%. The ozone consumption in the reduction of each variable was determined, being the average values of 57.2 g COD/mol O3, 2.9 un. Abs/mol O3 and 3.3 g polyphen./mol O3. Finally, considering a first order kinetic equation with respect to each reactant, the apparent kinetic constants are evaluated for the studied variables.En el presente trabajo se ha estudiado la ozonización de las aguas residuales provenientes de almazaras (alpechín. La evolución del proceso de degradación fue seguida por la medida de la demanda química de oxígeno (DQO, de la aromaticidad y del contenido en polifenoles totales. El tanto por ciento de DQO eliminada varía entre 3.25 y 19.4%, el de aromaticidad entre 4.85 y 21.1% y el de polifenoles totales entre 6.86 y 43.7%. Se determinó el consumo de ozono en la reducción de cada variable, dando valores medios de 57.2 g DQO/mol O3, 2.9 un. Abs/mol O3 y 3.3 g polif/mol O3. Por último, considerando una cinética de primer orden respecto de cada reaccionante, se han evaluado las constantes cinéticas aparentes respecto de cada variable.

  16. Tratabilidad de aguas residuales de matadero con filtros

    Directory of Open Access Journals (Sweden)

    Jesús Mario Ortiz A.

    2011-06-01

    Full Text Available Para estudiar la tratabilidad anaeróbica de las aguas residuales provenientes de un matadero de ganado vacuno, se emplearon un sistema de dos filtros en serie y un tercer filtro único como testigo. Con valores promedio de carga orgánica volumétrica y tiempo de retención de 1.6 kg/(m3*d y 26 horas respectivamente, las eficiencias de remoción de DQO total fueron similares en el filtro único y en el sistema en serie, del orden del 64% en promedio. Así mismo, la retención y acumulación de sólidos biológicos en el lecho, se mostro como la vía principal de remoción de la DQO. La diferenciación del proceso lograda con los dos filtros en serie permitió establecer que la mayor parte de la acumulación ocurrió en el filtro primario, en tanto que lo fundamental de la bioconversion en metano se produjo en el filtro secundario del sistema en serie. EI bajo nivel relativo de metanogenización obtenido podría explicarse por las limitaciones a la actividad de la biomasa metanogénica impuestas por las bajas temperaturas, aunque no se podría descartar una probable inhibición por los productos de hidrolisis de las grasas acumuladas: Resumen del Proyecto de Tesis Presentado por el autor Para optar al titulo de Magister en Ambiental. Dirección: Consuelo Díaz, Bióloga; M.S.c. U.N. Facultad de Ingenieria.1992.

  17. Agua Para Todos: A New Regionalist Hydraulic Paradigm in Spain

    Directory of Open Access Journals (Sweden)

    Elena Lopez-Gunn

    2009-10-01

    Full Text Available This paper reviews the hydraulic paradigm in Spain and its evolution over the last 100 years to the current decentralisation process of "agua para todos", i.e. where different regional governments vie for control over 'scarce' water resources and defining the concept of hydro-solidarity between regions. Recent events seem to point to a new hydraulic bureaucracy at the sub-national level due to the political devolution currently taking place in Spain, where water has an increased political value in electoral terms. Water has strategic importance in single-issue politics and territorial identity, as compared to traditional left/right ideological politics for both national and regional parties in the Spanish multilevel electoral system. This refers to an important aspect of water politics – openly discussed in Spain but rarely analysed – namely the 'political returns' on water (or 'political rent-seeking'. This also points to spatial dimensions of the definition of state, identity, and access to resources in a semiarid country. This historical process of decentralisation of water is highlighted with particular reference to key events in recent Spanish history, including the Hydraulic Plan of the 1930s, its reappearance in the 1993 National Hydrological Plan, a revised version in the year 2001, and a final change in paradigm in 2005 at the national level. This suggests that the hydraulic paradigm is re-enacted at the regional government level. It is argued that a multi-scalar analysis of Spanish water decentralisation is essential in order to understand change and stasis in public policy paradigms related to water.

  18. Agua Caliente Wind/Solar Project at Whitewater Ranch

    Energy Technology Data Exchange (ETDEWEB)

    Hooks, Todd [Agua Caliente Band of Cahuilla Indians, Palm Springs, CA (United States); Stewart, Royce [Red Mountain Energy Partners, Sante Fe, NM (United States)

    2014-12-16

    Agua Caliente Band of Cahuilla Indians (ACBCI) was awarded a grant by the Department of Energy (DOE) to study the feasibility of a wind and/or solar renewable energy project at the Whitewater Ranch (WWR) property of ACBCI. Red Mountain Energy Partners (RMEP) was engaged to conduct the study. The ACBCI tribal lands in the Coachella Valley have very rich renewable energy resources. The tribe has undertaken several studies to more fully understand the options available to them if they were to move forward with one or more renewable energy projects. With respect to the resources, the WWR property clearly has excellent wind and solar resources. The DOE National Renewable Energy Laboratory (NREL) has continued to upgrade and refine their library of resource maps. The newer, more precise maps quantify the resources as among the best in the world. The wind and solar technology available for deployment is also being improved. Both are reducing their costs to the point of being at or below the costs of fossil fuels. Technologies for energy storage and microgrids are also improving quickly and present additional ways to increase the wind and/or solar energy retained for later use with the network management flexibility to provide power to the appropriate locations when needed. As a result, renewable resources continue to gain more market share. The transitioning to renewables as the major resources for power will take some time as the conversion is complex and can have negative impacts if not managed well. While the economics for wind and solar systems continue to improve, the robustness of the WWR site was validated by the repeated queries of developers to place wind and/or solar there. The robust resources and improving technologies portends toward WWR land as a renewable energy site. The business case, however, is not so clear, especially when the potential investment portfolio for ACBCI has several very beneficial and profitable alternatives.

  19. Estación depuradora del agua de abastecimiento a Córdoba

    Directory of Open Access Journals (Sweden)

    Barrón Egusquiza, Pablo

    1958-05-01

    Full Text Available Por Orden ministerial del 1 de septiembre de 1951 comenzó a redactarse el proyecto definitivo del abastecimiento de agua a la ciudad de Córdoba. En el abastecimiento existente por aquella época, las múltiples procedencias del agua, aportaciones, casi todas, de pequeño caudal, sin garantía alguna respecto a su posible contaminación, tenían como consecuencia la aparición periódica de epidemias que se propagaban rápidamente.

  20. Agua y saneamiento rural: Oportunidades para la participación comunitaria en Colombia

    OpenAIRE

    Claudia Useche Melo

    2012-01-01

    Esta Nota no pretende hacer un análisis exhaustivo sobre las causas de la problemática de cobertura rural, sino más bien mostrar algunos de los aspectos a considerar en el diseño de nuevas intervenciones en la prestación de servicios de agua y saneamiento en zonas rurales, valiéndose de las experiencias contenidas en los estudios de caso presentados durante la Semana Sectorial de Agua del Banco Interamericano de Desarrollo (BID), llevada a cabo en Santiago de Chile en abril de 2011, y de expe...

  1. PRODUCCIÓN DE AGUA ELECTROLIZADA PARA ELIMINACIÓN DE MICROORGANISMOS EN LECHUGA

    Directory of Open Access Journals (Sweden)

    Gustavo Adolfo Chaves

    2004-06-01

    Full Text Available Se llevó a cabo la construcción de una celda electrolítica para la producción de agua electrolizada oxidante (EO, observando constantemente su pH y contenido de cloro residual. La eficacia del agua EO (14ppm de cloro residual y pH 2.7±0.2 fue evaluada con la cepa de Escherichia coli ATCC 25922 (Experimentos “in vitro” y carga microbiana de lechuga (recuento de bacterias mesófilas aeróbios, NMP coliformes y coliformes termotolerantes, hongos y levaduras. Después de obtener un inóculo de E. coli de 9 horas (fase estacionaria, 63 X 10 11UFC/ml, este fue sometido a tratamiento con agua EO en diferentes tiempos de exposición (0, 2, 5, 10, 15, 20min para luego hacer recuentos en placa. Para el análisis microbiológico in vivo se sumergieron 10 gramos de lechuga en 200ml de agua EO a diferentes tiempos de acción (0, 2, 5, 10, 15, 20min. Posterior a esto serealizaron pruebas microbiológicas de estos ensayos (Recuento de mesófilos aeróbios, número mas probable de coliformes totales, coliformes termotolerantes y recuento de hongos y levaduras. Los ensayos in vitro arrojaron datos que comprueban la acción microbicida del agua EO sobre el inoculo sometido a tratamiento durante 20 minutos, reduciendo en 11.34 Unidades Logarítmicas (UL los recuen-tos de E. coli.La experimentación con la lechuga mostró reducciones en el NMP de coliformes totales y termotolerantes que pasaron de >2400 NMP a <3 NMP, descenso de 4.16 UL para los recuentos de mesófilos aeróbios(Recuento inicial de 57 X 105 UFC/g y 3.95 UL para los de hongos y levaduras (recuento inicial de 89 X 103; luego del tratamiento con agua EO durante 20 min. Se demostró que la utilización de agua EO sobre lechuga contaminada tiene efecto microbicida estadísticamente significativo (p=0.0001, permitiendo de esta manera utilizar esta agua para el proceso de lavado y desinfección de las lechugas.

  2. Estudio del tratamiento anaerobio de aguas residuales urbanas en biorreactores de membranas

    OpenAIRE

    Giménez García, Juan Bautista

    2014-01-01

    Las aguas residuales urbanas (ARU) constituyen la fuente puntual de contaminantes más importante a escala global. Actualmente, un elevado porcentaje de las aguas residuales producidas a nivel mundial son vertidas al medio sin haber recibido ningún tipo de tratamiento, con consecuencias inmediatas, y en algunas ocasiones desastrosas, para la salud pública y la calidad del entorno natural. El tratamiento anaerobio está considerado como una de las alternativas más atractivas para el desarroll...

  3. Perdida de carga en conductos de hierro galvanizado conduciendo agua residual de instalaciones de gallinas ponedoras

    OpenAIRE

    JOSÉ ANTONIO RODRIGUES DE SOUZA; DÉBORA ASTONI MOREIRA; RAFAEL OLIVEIRA BATISTA; JAIRO ALEXANDER OSORIO S; OLGA LUCÍA ZAPATA MARÍN

    2011-01-01

    Las operaciones relacionadas con la producción de aves de corral pueden generar efluentes procedentes de fuentes distintas, incluida la escorrentía originada en las jaulas, alimentación y abastecimiento de agua de las aves y de las instalaciones de almacenamiento y manejo de residuos. En todo proyecto de explotación de aves de corral, se debe tener en cuenta el manejo de residuos y aguas residuales, las cuales pueden ser conducidas en tuberías de hierro galvanizado. El objetivo de este trabaj...

  4. Abastecimiento de agua y depósito regulador en Fuente el Saz de Jarama (Madrid)

    OpenAIRE

    Muslera López, Elena

    2012-01-01

    El presente proyecto consiste en el abastecimiento de agua potable de una urbanización de nueva construcción que va a realizarse en el municipio de Fuente el Saz de Jarama (Madrid). La primera parte consiste en preparar el terreno donde está situada la urbanización, esta preparación se basa en dotar de acceso a la urbanización y realizar los movimientos de tierra necesarios para igualar el terreno con las necesidades de la zona. La segunda parte, trata de abastecer de agua potable a la ...

  5. Tratamiento de aguas residuales por humedales artificiales tropicales en Tabasco, México

    Directory of Open Access Journals (Sweden)

    Cristian Marín Acosta

    2016-05-01

    Full Text Available En las dos últimas décadas, los humedales artificiales han incrementado mundialmente su desarrollo para el tratamiento de aguas residuales. En el presente estudio, doce humedales artificiales tropicales de flujo subsuperficial (HAFS fueron diseñados y operados específicamente para el tratamiento de aguas residuales domésticas. La eficiencia de remoción de contaminantes básicos (DBO5, DQO, SST, NT, PT, Turbiedad y Color fue evaluada bajo tres tratamientos: 1 Pontederia cordata (HAFS-Tule, 2 Phragmites australis (HAFS-Carrizo y 3 grava como prueba testigo (HAFS-Grava.

  6. PREVENCIÓN DE LA LEGIONELOSIS EN SISTEMAS DE REFRIGERACIÓN DE AGUA

    OpenAIRE

    ENRIQUE GEA-IZQUIERDO

    2011-01-01

    Los sistemas de refrigeración de agua constituyen unas de las fuentes principales de desarrollo de la bacteria Legionella . El sur de España (Comunidad Autónoma de Andalucía, Málaga) presenta enclaves industriales y turísticos, con gran afluencia de personas, que disponen las instalaciones de riesgo. El análisis del grado de control y desinfección del agua se presenta como un indicador preventivo frente al desarrollo del agente biológico, recogido en la normativa nacional. Mediante un estudio...

  7. Medida de la concentración de actividad Alfa/Beta grueso, en agua potable

    OpenAIRE

    Zutta Villate, Julián Mateo

    2014-01-01

    Introducción: La calidad del agua de consumo humano es de creciente interés en el mundo; para que esta pueda ser considerada como potable, debe ajustarse a ciertos niveles biológicos, químicos, físicos y radiológicos. Siguiendo recomendaciones de organismos internacionales de salud o, a estándares emitidos por cada país, establecidos según sus condiciones tanto ambientales, como socioeconómicas. La Organización Mundial de la Salud (OMS), en sus guías de potabilización del agua de consu...

  8. COSTUMBRES COMUNES, DERECHOS INDIVIDUALES. BARRIOS Y AGUA EN IZÚCAR, PUEBLA

    OpenAIRE

    Francisco Javier Gómez Carpintero

    2002-01-01

    Este trabajo analiza una forma de organización local para el uso del agua en los barrios de Izúcar de Matamoros, Puebla, la cual fue transformada en las dos primeras décadas de la etapa posrevolucionaria. El estudio es una buena oportunidad para entender los procesos de formación del Estado y la comunidad nacional y su articulación a los poderes locales; en este caso a partir de las políticas barriales en torno al control del agua federal para riego

  9. Las características del mercado de derechos de agua en España

    OpenAIRE

    Antonio Embid Irujo

    2013-01-01

    Por diversas circunstancias el derecho español conoce desde 1999 de una regulación jurídica de los mercados de derechos de uso de aguas. De ellos se ha hecho bastante utilización durante la última gran sequía (2005-2009) y la experiencia ha sido favorable. La regulación de los mercados intenta evitar la especulación y el acaparamiento de derechos. Sin que sea gran cantidad de agua la que se mueve por razón de los mercados, sí que es suficiente para evitar graves inconvenientes y, con el adecu...

  10. Vigilancia sanitaria del agua: un nuevo enfoque para municipalidades de Costa Rica

    OpenAIRE

    Carmen Valiente

    1999-01-01

    Los programas de vigilancia sanitaria constituyen el nuevo enfoque para complementar los programas de control de calidad del agua y consisten en la aplicación de una metodología que permite determinar el grado de riesgo para la salud que presentan los sistemas de agua para consumo humano. En el presente trabajo se presenta el desarrollo y adaptación de un Programa de Vigilancia Sanitaria para ser utilizado en Costa Rica. Este programa se basa principalmente en determinar el grado de riesgo pa...

  11. Aptitud del agua caliente para su uso en agricultura de regadío

    OpenAIRE

    Villar Mir, Josep M.; Carrasco Martín, Israel

    2002-01-01

    En este trabajo se considera el suelo como el sumidero más importante para el calor residual industrial. El agua es el refrigerante más utilizado en las plantas productoras de energía para disipar el exceso de energía calorífica industrial. Esta agua, una vez ha realizado su función y con la temperatura más elevada, puede ser reutilizada en agricultura a través del riego. Se ha realizado una revisión bibliográfica de las experiencias realizadas en todo el mundo sobre los efectos que puede ...

  12. Alternativas para conocer el comportamiento de la calidad del agua en un tramo del arroyo guachinango

    OpenAIRE

    Jeny Pérez P.; Geisy Hernández C.; Felicita González R.; Teresa López S.

    2008-01-01

    En el mundo actual ha evolucionado la tecnología para tratamiento y reutilización de aguas residuales, pero la obtención y aplicación de las mismas conlleva grandes inversiones, por lo que un país como el nuestro no está al alcance de la misma. Esto conlleva a la búsqueda de alternativas que se ajusten a nuestro presupuesto y nuestras condiciones, siempre que las mismas cumplan con las medidas de protección e higiene que existen para la utilización de estas aguas. En un tramo de arroyo con ve...

  13. Planes de seguridad del agua. fundamentos y perspectivas de implementación en colombia

    OpenAIRE

    Pérez Vidal, Andrea; Torres Lozada, Patricia; Cruz Vélez, Camilo Hernán

    2010-01-01

    El agua para consumo humano debe estar libre de organismos patógenos, sustancias químicas, impurezas y cualquier contami- nante que cause problemas a la salud humana. América Latina y el Caribe (ALC) presentan problemas de calidad por deficien- cias en la operación, mantenimiento y continuidad de los servicios, incorrecto funcionamiento de las plantas de tratamiento y precariedad de las redes de distribución e instalaciones domiciliarias. Las tendencias mundiales del sector agua potable es...

  14. Editorial of the twenty second edition of Ambiente & Agua - An Interdisciplinary Journal of Applied Science

    Directory of Open Access Journals (Sweden)

    Getulio Teixeira Batista

    2013-08-01

    Full Text Available This is the 22nd edition of Ambiente & Agua. As with recent editions, it includes 20 peer-reviewed articles. We continue our policies of complete open access and of working to increase the visibility of articles. As a result of these policies, we recently were accepted by two important indexers: The Scientific Electronic Library Online (SciELO and the US National Agricultural Library (NAL. We continue to register the doi of all articles and to publish each issue as a single document in addition to the individual articles. This editorial describes the current status of the Ambiente & Agua journal in the Qualis CAPES.

  15. Caracterización de las aguas residuales de la planta refinadora de aceites comestibles ERASOL

    Directory of Open Access Journals (Sweden)

    Arelis Abalos

    2007-01-01

    regulaciones de la Norma Cubana para el vertido en cuerpos receptores marinos. Los análisis demostraron que la bahía recibe la descarga de aguas residuales de ERASOL con un pH de 9,7 unidades, 40232,50 mg/L de materia orgánica, 18537,13 g/L de aceites y 0,2 mL/L de sólidos sedimentables. Estos resultados evidenciaron que las aguas residuales de la planta de aceites ERASOL no cumplen con las especificaciones de la norma de vertido en cuerpos marinos.

  16. Biotratamiento de las aguas residuales de una planta de enlatado de vegetales

    OpenAIRE

    Ruiz Colorado, Angela Adriana

    2001-01-01

    Resumen: En este trabajo se evaluó la efectividad de cultivos mixtos comerciales utilizados para el tratamiento de las aguas residuales de una de las empresas comercializadora de estos en Colombia. La entrada de ellos al país ha ocasionado un cambio en los tratamientos tradicionalmente anaerobios de las aguas residuales industriales, siendo reemplazados por tratamientos aerobios -facultativos. Para su aplicación en esta investigación se realizó inicialmente la caracterización fisicoquímica y ...

  17. Calentador solar de agua : Manual del usuario. Tecnología sencilla

    OpenAIRE

    San Juan, Gustavo Alberto; Barros, Victoria

    2011-01-01

    Este manual aporta los conocimientos necesarios para la construcción y uso del calentador solar de agua. Tiene por objeto divulgar y transferir tecnología apropiadas a muestra realidad social, mediante la incorporación de conocimiento, a partir de la utilización de tecnología sencilla, tendiendo a la promoción del ser humano. Está orientado a familias en emergencia social que no cuentan con agua caliente en sus hogares, y que actualmente queman leña o carbón en el interior de las mismas, p...

  18. Hydro geochemistry of uranium in Aguas de Lindoia (Sao Paulo State)

    International Nuclear Information System (INIS)

    A preliminary investigation concerning to the geochemical behaviour of uranium isotopes (233 U and 238 U) was performed on spring waters for Aguas de Lindoia city, Sao Paulo State. The reason for this study is because the natural radioactivity of these waters is poorly known, and no uranium content data have been published. Measurements of Uranium-238 contents and 234 U/238 U activity ratios in groundwaters were performed on the following springs issuing in the urban area from Aguas de Lindoia: Levissima I, Levissima II, Beleza, Sao Roque, Lindalia and Santa Izabel. (author)

  19. Estación depuradora de aguas residuales de Leganés

    OpenAIRE

    García Ramos, Marta

    2015-01-01

    El objeto del presente proyecto consiste en estudiar las características de las aguas residuales de Leganés y diseñar un sistema de depuración para éstas. Se definirán y valorarán las obras civiles y equipos electromecánicos necesarios para ejecutar las obras de la Estación Depuradora de Aguas Residuales de Leganés. Para ello se estudia una planta que, cumpliendo los parámetros y requisitos técnicos necesarios, obtenga los rendimientos de depuración necesarios. Con esto se debe tener en cuent...

  20. Derecho humano al agua y al saneamiento: derechos estrechamente vinculados al derecho a la vida

    OpenAIRE

    Fernández Aller, Maria Celia; Luis Romero, Elena de; Guzmán Acha, Cristina

    2013-01-01

    Los derechos humanos al agua y al saneamiento están íntimamente relacionados con otros derechos esenciales para la vida, como la alimentación o la salud. Su reconocimiento como derechos humanos en 2010 marca un hito importante en el respeto, protección y realización de estos derechos, que se encuentran seriamente vulnerados para una mayoría de población más vulnerable y empobrecida, sobre todo en el ámbito rural. Mucho camino queda aún para conseguir no sólo la disponibilidad de agua y saneam...

  1. Calidad del agua marina en un tramo costero con uso industrial de la provincia La Habana.

    OpenAIRE

    Carmenate, M.; Arriaza, L.; Busutil, L.; Durán, A.; C. García; García, I

    2010-01-01

    Se efectuó una campaña de muestreo en un tramo costero perteneciente a Boca de Jaruco, provincia La Habana. El objetivo fue determinar la calidad de las aguas de este sitio, sujeto a un intenso desarrollo industrial. En las siete estaciones escogidas se analizaron los principales indicadores físicos y químicos de calidad del agua, incluyendo hidrocarburos, debido a la cercanía de instalaciones petroleras. También se realizó el análisis cualitativo y cuantitativo de la comunidad de...

  2. Brote de gastroenteritis por agua potable de suministro público

    Directory of Open Access Journals (Sweden)

    Godoy P.

    2003-01-01

    Full Text Available Introducción: La potabilidad del agua induce a descartar el posible origen hídrico de los brotes. El objetivo fue investigar un brote de gastroenteritis por agua potable de suministro público. Métodos: Después de la notificación de un brote de gastroenteritis en el municipio de Baqueira (Valle de Arán se diseñó un estudio epidemiológico de cohortes retrospectivo. Mediante un muestreo sistemático se eligió a 87 personas hospedadas en los hoteles y a 62 alojadas en diferentes apartamentos. Se recogió información sobre 4 factores (consumo de agua de la red, bocadillos, agua y alimentos en las pistas de esquí y presencia de síntomas. Se determinó la existencia de cloro, se analizó el agua de la red y se realizó un coprocultivo a 4 enfermos. La implicación de cada factor se determinó con el riesgo relativo (RR y su intervalo de confianza (IC del 95%. Resultados: La incidencia de gastroenteritis fue del 51,0% (76/149. Los porcentajes de los síntomas fueron los siguientes: fiebre, 27,0%; diarrea, 87,5%; náuseas, 50,7%; vómitos, 30,3%, y dolor abdominal, 80,0%. El único factor que presentó un riesgo estadísticamente significativo fue el consumo de agua de la red (RR = 11,0; IC del 95%, 1,6-74,7. La calificación sanitaria del agua fue de potabilidad. Se observó un defecto de situación del clorador en el depósito, que fue corregido. Se recomendó incrementar aún más las concentraciones de cloro, lo cual se acompañó de una disminución de los casos. Los coprocultivos de los 4 enfermos fueron negativos para las enterobacterias investigadas. Conclusiones: El estudio demuestra la posibilidad de presentación de brotes hídricos por agua cualificada como potable y sugiere la necesidad de mejorar la investigación microbiológica (determinación de protozoos y virus en este tipo de brotes.

  3. Agua termal envasada para el cuidado de la piel: plan de marketing

    OpenAIRE

    Arbeláez Cifuentes, Lucas Ignacio

    2013-01-01

    Agua termal envasada para el cuidado de la piel”, surge como idea de un nuevo producto para impulsar el crecimiento de la empresa Aura de Vida S.A., hasta el momento dedicada solamente al embotellamiento y comercialización de agua para consumo -- La estructura de costos y las estrategias de mercadeo para hacer posible la implementación de la idea empresarial, se construyeron siguiendo como orientación principal la metodología propuesta en el libro El plan de marketing en la práctica (Sainz d...

  4. ACERCAMIENTO AL SABER CIENTÍFICO EN EDUCACIÓN INFANTIL: EL AGUA

    OpenAIRE

    Aguilera-Gómez, Carmen

    2014-01-01

    El agua es un elemento esencial para la vida de todos los seres vivos. Cada vez es más necesario planificar desde las escuelas hábitos responsables que transmitan experiencias y reflexiones sobre la importancia del agua en nuestras vidas. Este trabajo pretende introducir a los alumnos de tercer curso del segundo ciclo de educación infantil la aplicación del método científico como técnica que fomenta la adquisición y desarrollo de las capacidades en los alumnos, impulsando el desarrollo integr...

  5. SISTEMAS DE SIEMBRA EN TRIGO: ENCARANDO LA ESCASEZ DE AGUA CAUSADA POR EL CALENTAMIENTO GLOBAL

    OpenAIRE

    Héctor Eduardo Villaseñor Mir; Agustín Limón Ortega; Eduardo Espitia Rangel; Luis Antonio Mariscal Amaro

    2011-01-01

    En 80% de las regiones productoras de trigo de temporal hay deficiencias de humedad, por lo que la disponibilidad de agua y la eficiencia en su uso son los factores más importantes, para mejorar la rentabilidad del cultivo, y más aún, cuando se prevé que gran parte de México, en los próximos años, enfrentará temporales más escasos por el calentamiento global. La siembra de trigo en camas, con y sin microcuencas, ha sido ideada para una captación efectiva del agua de lluvia, que permite mayor ...

  6. Riesgo genotóxico de los subproductos de la desinfección del agua

    OpenAIRE

    Liviac Muñoz, Danae Marcela

    2010-01-01

    Los subproductos de la desinfección del agua de consumo son compuestos químicos que se generan por la reacción entre el desinfecante usado, cloro en la mayoría de los casos, y la materia orgánica e inorgánica presente en el agua a desinfectar. El perfil de estos subproductos es diferente entre las distintas plantas de tratamiento, debido a varios factores involucrados en su formación como son el tipo de desinfectante usado, el desinfectante secundario, el pH, la temperatura y la materia orgán...

  7. Estrategias para coadyuvar a la sustentabilidad en la gestión del agua en la ciudad de México

    OpenAIRE

    J. Jesús Ceja Pizano; María Luisa Gómez González; Concepción Herrera Alcázar

    2013-01-01

    El garantizar el acceso al agua potable se ha vuelto un reto difícil de vencer. Primeramente por la escasez de agua potable, la falta de saneamiento y alcantarillado. Además del urbanismo desordenado que impide la planeación de infraestructura hidráulica acorde a las necesidades de los usuarios de agua. Por lo que es imprescindible contar con un Modelo de Gestión de Agua para garantizar el acceso al agua potable, motivando una sana gobernanza e incentivando la participación ciudadana. Para lo...

  8. Los códigos de agua provinciales y la distribución de competencias legislativas en la constitución

    OpenAIRE

    Torre, Genaro Osmar de la

    2013-01-01

    El sumario de la ponencia contiene: I- Introducción. II- Referencias sobre el Agua en los textos Constitucionales. a) Constitución Nacional; b) Constitución de la Provincia de Buenos Aires; III.-Deslinde de competencias legislativas entre la Nación y las Provincias. IV- El agua como objeto de derechos reales. V- Agua de dominio público y agua de dominio privado. Enumeración. VI.- Regulación del uso, los Códigos de Agua.

  9. Vigilancia sanitaria de cianobacterias en aguas de consumo humano y aguas de baño Health surveys of cyanobacteria in drinking and recreational waters

    Directory of Open Access Journals (Sweden)

    Guadalupe Martínez Juárez

    2008-06-01

    Full Text Available Las autoridades de Salud Pública tienen implantados y consolidados programas de vigilancia sanitaria de aguas de consumo humano y aguas de baño, cuya finalidad es evitar riesgos para la salud de la población que consume agua o que utiliza con fines recreativos zonas de baño continentales. A la luz de los conocimientos científicos actuales, la proliferación de cianobacterias es un nuevo riesgo, que es necesario tener en cuenta en los programas de protección de la salud. En el presente trabajo, cuyo principal objetivo es conocer la presencia de cianobacterias y microcistinas en aguas utilizadas para consumo humano y baño, se muestran los resultados obtenidos en los programas de vigilancia llevados a cabo en el Área de Salud de Talavera de la Reina en los últimos cuatro años. Se ha realizado un estudio descriptivo de la presencia de cianobacterias y microcistinas, en agua bruta de la captación de dos embalses y en agua tratada a la salida de dos plantas de tratamiento de agua potable. Esto mismo se ha estudiado en otros dos embalses utilizados para baño en época estival. Para ello se han efectuado muestreos quincenales y posterior identificación y recuento de cianobacterias y determinación de microcistinas disueltas en agua mediante técnica ELISA. De los resultados de la vigilancia de aguas de consumo humano, se concluye que los valores de microcistinas detectados en los embalses no son elevados, apareciendo en menos del 6% de los muestreos efectuados y que el tratamiento aplicado en las plantas de tratamiento de agua potable, es eficaz para su eliminación. De la vigilancia de cianobacterias en el agua de baño, se concluye que a lo largo de tres temporadas, en el 48% de los muestreos realizados en las dos zonas de baño del área, se han superado las 100.000 células/ml, valor guía dado por la OMS, para valorar probabilidad moderada de efectos adversos en bañistas. Destacar que es necesario disponer de datos sobre exposición a

  10. Technical Basis for Peak Reactivity Burnup Credit for BWR Spent Nuclear Fuel in Storage and Transportation Systems

    Energy Technology Data Exchange (ETDEWEB)

    Marshall, William BJ J [ORNL; Ade, Brian J [ORNL; Bowman, Stephen M [ORNL; Gauld, Ian C [ORNL; Ilas, Germina [ORNL; Mertyurek, Ugur [ORNL; Radulescu, Georgeta [ORNL

    2015-01-01

    Oak Ridge National Laboratory and the United States Nuclear Regulatory Commission have initiated a multiyear project to investigate application of burnup credit for boiling-water reactor (BWR) fuel in storage and transportation casks. This project includes two phases. The first phase (1) investigates applicability of peak reactivity methods currently used in spent fuel pools (SFPs) to storage and transportation systems and (2) evaluates validation of both reactivity (keff) calculations and burnup credit nuclide concentrations within these methods. The second phase will focus on extending burnup credit beyond peak reactivity. This paper documents the first phase, including an analysis of lattice design parameters and depletion effects, as well as both validation components. Initial efforts related to extended burnup credit are discussed in a companion paper. Peak reactivity analyses have been used in criticality analyses for licensing of BWR fuel in SFPs over the last 20 years. These analyses typically combine credit for the gadolinium burnable absorber present in the fuel with a modest amount of burnup credit. Gadolinium burnable absorbers are used in BWR assemblies to control core reactivity. The burnable absorber significantly reduces assembly reactivity at beginning of life, potentially leading to significant increases in assembly reactivity for burnups less than 15–20 GWd/MTU. The reactivity of each fuel lattice is dependent on gadolinium loading. The number of gadolinium-bearing fuel pins lowers initial lattice reactivity, but it has a small impact on the burnup and reactivity of the peak. The gadolinium concentration in each pin has a small impact on initial lattice reactivity but a significant effect on the reactivity of the peak and the burnup at which the peak occurs. The importance of the lattice parameters and depletion conditions are primarily determined by their impact on the gadolinium depletion. Criticality code validation for BWR burnup

  11. The synergies of PLiM, PLEX, and power uprates: Lessons learned from recent BWR experience

    International Nuclear Information System (INIS)

    Full text: Increasing electricity demand due to population growth and redistribution, high oil and gas prices, concerns for greenhouse gas emissions, and a positive trend in public opinion and government support for nuclear power provide tremendous opportunity for growth in the nuclear industry throughout the world. This can be accomplished in two ways, (1) new plants can be built and (2) the performance of existing plants can be improved through increased reliability and increased in generation capacity known as power uprates. In addition, the operating and design life of existing units can be extended for twenty or even forty years through plant life extension (PLEX). However. these uprates and life extensions are only viable if the plant reliability and capacity factor gains made in recent years continue through the extended operating domainlperiod. A growing number of US and international BWR's have successfully improved economic viability while increasing generation within existing facilities through implementation of uprates and PLEX efforts. The evolution of these efforts is the transition to a synergistic approach of plant modernization (including digital I and C upgrades), Life Cycle Management (LCM), margin recapture, and reliability improvement included in the overall plan with power uprates and PLEX. As the experience base with these programs grows suppliers, like GE, and utilities continue to build on the experience of prior projects, improve project execution, and maximize the investment returns. This paper will present the results of several recent GE BWR projects in the US that have implemented combined efforts of reliability management programs with strategic projects such as power uprates. The paper will focus on the lessons learned froin these efforts to help plants prepare for planning and implementing their own integrated reliability programs. Specific areas to be discussed include project initiation and scoping, project planning, project team

  12. Stress-corrosion crack initiation process for Alloy 182 weld metal in simulated BWR environments

    International Nuclear Information System (INIS)

    For preventing SCC from occurring in the internal structure of materials of the BWR plant, the injection of hydrogen into the core-water so as to reduce the free corrosion potential of the materials were proposed. Because of the lack of basic data of stress-corrosion cracking susceptibility in BWR environment on Ni-based alloys in comparison with stainless steels, the slow strain-rate tensile (SSRT) tests and the creviced bent-beam (CBB) test were conducted for a sensitized Alloy 182 weld metal in high-purity water environments containing dissolved oxygen (DO) and hydrogen (DH) to varied concentrations at 288 C, and the SCC initiation process were examined. The susceptibility of a material to SCC was discussed in terms of the electrode potential effect, and the effects of impurities of the testing water were examined by adding slightly Na2, SO4. In high purity waters and in the electrode potential region higher than - 0.2 V vs. SHE, the interdendritic stress-corrosion cracks were observed both in the slow strain-rate test and the creviced bent-beam test. SEM observations of sub-cracks at the specimen surfaces revealed that stress-corrosion cracks were initiated when the oxide film had cracked to under-hundred microm wide, that no such individual cracks could grow per se, but that those micro-cracks which happened to be formed in each other's vicinity would coalesce into large cracks, one of which made propagated as stress-corrosion cracking, and that the stress-corrosion cracking sensitivity became more acute on addition of impurity. In the electrode potential region lower than 0 V, on the other hand, the stress-corrosion cracks were observed to be initiated at bottoms of corrosion pits formed on the specimen surfaces in the former, whereas both type of stress-corrosion cracks were observed between 0 to -0.2V. No stress-corrosion crack was observed even though much the same corrosion pits in the CBB test at -0.4 V

  13. An advanced frequency-domain code for boiling water reactor (BWR) stability analysis and design

    International Nuclear Information System (INIS)

    for a large reactor could reach 20 gigabytes) that it is not possible to load into RAM memory of an operating system with 32 bit architecture. A special procedure has been developed within the MATLAB environment to remove this memory limitation, and to invert such large matrices and finally obtain the reactor transfer functions that enable the study of system stability. Various applications of the present frequency-domain code to a typical BWR fuel assembly, a BWR core, and to a chemical reactor showed a good agreement with reference results. (author)

  14. Hydrogen uptake of BWR fuel rods. Power history effects at long irradiation times

    International Nuclear Information System (INIS)

    AREVA LTP (Low Temperature Process) Zircaloy-2 cladding for Boiling Water Reactors (BWR) in both RXA (Recrystallized Annealed) and CWSR (Cold Worked Stress Relieved) metallurgical states, has an optimized microstructure with an optimum size of SPP (Secondary Phase Particles) that has reduced the nodular corrosion to a minimum while maintaining a good uniform corrosion performance with acceptable hydrogen pickup. Classically hydrogen uptake is described by the Hydrogen Pick-Up Fraction (HPUF), which is the ratio of the hydrogen generated by uniform oxidation that is eventually picked up by the metal to the total hydrogen generated by oxidation. In the past, the hydrogen uptake database showed a low HPUF with hydrogen concentration close to the saturation value of the metal at operating temperature and correspondingly little hydride formation. The hydrogen concentration was correlated with irradiation time via the HPUF (at an almost constant corrosion and hydrogen production rate). Recently, some significantly higher hydrogen concentration values (300 wppm and more) have been measured for medium and high burnup rods. This effect was also observed on four AREVA fuel rods from BWR (Boiling Water Reactors). This prompted a thorough analysis of the hydrogen pickup database as well as material and environmental factors influencing corrosion and hydrogen uptake. The most important outcome of the investigation was that a low power – low steam condition is associated with increased hydrogen pickup. The linear power is a proxy variable for low heat flux and low steam quality in the coolant, which were identified as important parameters for physical processes that could explain the enhanced hydrogen uptake in some cases. The paper will present the database of the enhanced hydrogen uptake measured in European power reactors and demonstrate the effect of power history on the uptake process. Power histories with high hydrogen uptake included extended low power periods later in

  15. IASCC susceptibility under BWR conditions of welded 304 and 347 stainless steels

    Energy Technology Data Exchange (ETDEWEB)

    Castano, M.L. [CIEMAT, Complutense 22, 28040 Madrid (Spain); Schaaf, B. van der [NRG, Petten (Netherlands); Roth, A. [Framatome ANP, Erlangen (Germany); Ohms, C. [JRC-IE, Petten (Netherlands); Gavillet, D. [PSI, Villigen (Switzerland); Dyck, S. van [SCK - CEN, Mol (Belgium)

    2004-07-01

    In-service cracking of Boiling Water Reactors (BWR) and Pressurized Water Reactors (PWR) internal components has been attributed to Irradiation Assisted Stress Corrosion Cracking (IASCC), a high temperature degradation process that austenitic stainless steels exhibit, when subjected to stress and exposed to relatively high fast neutron flux. Most of the cracking incidents in BWRs were associated to the heat-affected zone (HAZ) of welds. Although the maximum end-of- life dose for this structure is about 3 x 10{sup 20} n/cm{sup 2}, below the threshold fluence of 5 x 10{sup 20} n/cm{sup 2} (equivalent to {approx} 1 dpa) for IASCC in BWR of annealed materials, the influence of neutron irradiation in the weld and HAZ is still an open question. As a consequence of the welding process, residual stresses, microstructural and microchemical modifications are expected. In addition, exposure to neutron irradiation can induce variations in the material's characteristics that can modify the stress corrosion resistance of the welded components. While the IASCC susceptibility of base materials is being widely studied in many international projects, the specific conditions of irradiated weldments are rarely assessed. The INTERWELD project, partially financed by the 5. Framework program of the European Commission, was defined to elucidate neutron radiation induced changes in the HAZ of austenitic stainless steel welds that may promote intergranular cracking. To achieve this goal the evolution of residual stresses, microstructure, micro-chemistry, mechanical properties and the stress corrosion behaviour of irradiated materials are being evaluated. Fabrication of appropriate welds of 304 and 347 stainless steels, representative of core components, was performed. These weld materials were irradiated in the High Flux Reactor (HFR) in Petten to two neutron dose levels, i.e. 0.3 and 1 dpa. Complete characterization of the HAZ of both materials, before and after irradiation is

  16. Evaluation of pressure transitories in BWR type reactors using the BWRDYN code; Evaluacion de transitorios de presion en reactores tipo BWR usando el codigo BWRDYN

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez P, J.A. [ESIME, Unidad Profesional Azcapotzalco, Av. de las Granjas 682, 02550 Mexico D.F. (Mexico)]. e-mail: jrodriguez@ipn.mx

    2007-07-01

    Several simulations of pressure transitory for a nucleo electric power station with BWR/4 type reactor were carried out. The simulated pressure transitories were made for the Peach Bottom 2 Nucleo electric central. Also, it was carried out for the same Plant the simulation of the turbine shot with derivation to the main condenser, of the reference case (benchmark) outlined by the Organization for the Cooperation and the Economic Development and of the Commission Regulatory in Nuclear matter of the United States of America. As tool to carry out the simulations of the transitory ones, the BWRDYN code developed by the Japan Energy Research Institute was used. Among the main suppositions and models that it includes the BWRDYN code its can be mentioned: a) that of punctual kinetics that calculates the neutron flow; for the calculation of the fuel temperature, this it is divided in nodes in the radial and axial directions, the wrapper is considered like a region in the radial direction; c) the pressure is supposed that it is uniform inside the reactor vessel; and d) the thermal hydraulic pattern of the reactor vessel is divided in five regions and the core is divided in several nodes to take into account the distribution of holes in the axial direction. The modeling of the control systems of the feeding water system is also included, of the pressure regulator and of the recirculation system. The systems of what is known as plant balance are also modeled. The numeric results of the simulations provide valuable information of the behavior of the nucleo electric central. The obtained results of the simulation of the reference case agree acceptably with the measurements data, when comparing them with the measurements made in the Peach Bottom 2 Central. The obtained results of each simulation are fundamental to evaluate the transitory one, as well as to delineate the sequence and the impact of diverse events that they happen during the same one transitory. In the case of the

  17. Radial optimization of a BWR fuel cell using genetic algorithms; Optimizacion radial de una celda de combustible BWR usando algoritmos geneticos

    Energy Technology Data Exchange (ETDEWEB)

    Martin del Campo M, C.; Carmona H, R.; Oropeza C, I.P. [UNAM, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico)]. e-mail: cmcm@fi-b.unam.mx

    2006-07-01

    The development of the application of the Genetic Algorithms (GA) to the optimization of the radial distribution of enrichment in a cell of fuel of a BWR (Boiling Water Reactor) is presented. The optimization process it was ties to the HELIOS simulator, which is a transport code of neutron simulation of fuel cells that has been validated for the calculation of nuclear banks for BWRs. With heterogeneous radial designs can improve the radial distribution of the power, for what the radial design of fuel has a strong influence in the global design of fuel recharges. The optimum radial distribution of fuel bars is looked for with different enrichments of U{sup 235} and contents of consumable poison. For it is necessary to define the representation of the solution, the objective function and the implementation of the specific optimization process to the solution of the problem. The optimization process it was coded in 'C' language, it was automated the creation of the entrances to the simulator, the execution of the simulator and the extraction, in the exit of the simulator, of the parameters that intervene in the objective function. The objective function includes four parameters: average enrichment of the cell, average gadolinia concentration of the cell, peak factor of radial power and k-infinite multiplication factor. To be able to calculate the parameters that intervene in the objective function, the one evaluation process of GA was ties to the HELIOS code executed in a Compaq Alpha workstation. It was applied to the design of a fuel cell of 10 x 10 that it can be employee in the fuel assemble designs that are used at the moment in the Laguna Verde Nucleo electric Central. Its were considered 10 different fuel compositions which four contain gadolinia. Three heuristic rules that consist in prohibiting the placement of bars with gadolinia in the ends of the cell, to place the compositions with the smallest enrichment in the corners of the cell and to fix

  18. The threates on the biodiversity of Bisotun Wildlife Refuge and Bisotun Protected Area (BPA & BWR in the west region of Iran

    Directory of Open Access Journals (Sweden)

    MAHDI REYAHI-KHORAM

    2014-04-01

    Full Text Available Reyahi-Khoram M, Rizvandy M, Reyahi-Khoram R. 2014. The threates on the biodiversity of Bisotun Wildlife Refuge and Bisotun Protected Area (BPA & BWR in the west region of Iran. Biodiversitas 15: 65-72. Nature is necessary for the preservation of species and biodiversity richness; as a result, it has been protected for thousands of years. Bisotun Protected Area and Bisotun Wildlife Refuge (BPA & BWR with about 95000 hectares is located in Kermanshah province in the west of Iran. The object of this study is to determine the physical properties and analyze the constraints that threaten the BPA & BWR. This research was conducted during the period from May, 2011 to November, 2012 in BPA & BWR. In this research, various animal and plant species were recognized through documentary analysis and also directs field observations. The obtained result indicates that major threates have occurred in biodiversity and ecosystem of BPA & BWR during 1980-2010. During these years, the study area has completely failed and lost some of its biological diversity. Limiting factors that affect wildlife population growth including destruction and conversion of habitats, unauthorized hunting and high frequency presence of animal and human, have influenced the restoration potential of wildlife, the habitats and other conservation areas.

  19. Analyses of Instability Events in the Peach Bottom-2 BWR Using Thermal-Hydraulic and 3D Neutron Kinetic Coupled Codes Technique

    Directory of Open Access Journals (Sweden)

    Antonella Lombardi Costa

    2008-01-01

    Full Text Available Boiling water reactor (BWR instabilities may occur when, starting from a stable operating condition, changes in system parameters bring the reactor towards an unstable region. In order to design more stable and safer core configurations, experimental and theoretical studies about BWR stability have been performed to characterise the phenomenon and to predict the conditions for its occurrence. In this work, contributions to the study of BWR instability phenomena are presented. The RELAP5/MOD3.3 thermal-hydraulic (TH system code and the PARCS-2.4 3D neutron kinetic (NK code were coupled to simulate BWR transients. Different algorithms were used to calculate the decay ratio (DR and the natural frequency (NF from the power oscillation predicted by the transient calculations as two typical parameters used to provide a quantitative description of instabilities. The validation of the code model set up for the Peach Bottom Unit 2 BWR plant is performed against low-flow stability tests (LFSTs. The four series of LFST have been performed during the first quarter of 1977 at the end of cycle 2 in Pennsylvania. The tests were intended to measure the reactor core stability margins at the limiting conditions used in design and safety analyses.

  20. Standard- and extended-burnup PWR [pressurized-water reactor] and BWR [boiling-water reactor] reactor models for the ORIGEN2 computer code

    International Nuclear Information System (INIS)

    The purpose of this report is to describe an updated set of reactor models for pressurized-water reactors (PWRs) and boiling-water reactors (BWRs) operating on uranium fuel cycles and the methods used to generate the information for these models. Since new fuel cycle schemes and reactor core designs are introduced from time to time by reactor manufacturers and fuel vendors, an effort has been made to update these reactor models periodically and to expand the data bases used by the ORIGEN2 computer code. In addition, more sophisticated computational techniques than previously available were used to calculate the resulting reactor model cross-section libraries. The PWR models were based on a Westinghouse design, while the BWR models were based on a General Electric BWR/6 design. The specific reactor types considered in this report are as follows (see Glossary for the definition of these and other terms): (1) PWR-US, (2) PWR-UE, (3) BWR-US, (4) BWR-USO, and (5) BWR-UE. Each reactor model includes a unique data library that may be used to simulate the buildup and deletion of isotopes in nuclear materials using the ORIGEN2 computer code. 33 refs., 44 tabs